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Ver. 2.76 User`s Manual

1. 71 44 1 1 74 LI 74 4 4 2 Nuclide definition 74 a ate ata ee Aas 75 Dod We te Ra a ee Baek 75 qoM 75 76 d 11 ua xu Rb IR BAK Ru TRO URDU E dc E s TT 4351 Pornnats e ios ooh eb C Roo EGA wem v Woo s POE ORO Rok TI T rE ee A 78 E E a Re E ME 81 bth tn te eet Aalders Ade ie i tad ancy tae Sans aie At Be 82 Be ee PILLS 85 46 90 4 6 1 Formats sea ic area r peen o 8 VERA eee X Rd RO Y oS 90 TDI 90 4 6 3 Macro body aono OX Ro UR RUSO 92 cn be teen ees 93 4 6 5 Surface definition by 94 47 Transform section x d 684 28 06 bee ee Geena ewe ba OR REOS 95 47 Formats 3 loeo om ee won le Bh eee whe led aede d 95 TTE 95 4 7 3 Examples mos er RR EUR E aoe eo a eom OUR oe CER EORR 96 4 7 4 Examples 2 96 48 Importance section rh
2. name description title Title parameters Various type of parameters source Source definition material Material definition cell Cell definition by GG surface Surface definition by GG transform Definition the coordinate transform of GG surface importance Region importance definition weight window Weight window definition volume Region volume definition temperature Cell temperature definition brems bias Bremsstrahlung bias definition photon weight Photon product weight definition forced collisions Forced collision definition magnetic field Magnetic field definition electro magnetic field Electro magnetic field definition counter Counter definition reg name Region name definition for graphical plot mat name color Material name and color definition for graphical plot mat time change time dependent material definition super mirror super mirror definition elastic option elastic option definition timer timer definition delta ray production of rays multiplier multiplier definition 3 2 Reading control Table 3 2 Sections 2 name description t track Track length tally definition t cross Surface crossing tally definition t heat Heat developing tally definition t deposit Deposit tally definition t deposit2 Deposit2 tall
3. 2 2 2 2354 5 36 io 6 37 20 38 21 39 iserr 0 40 Wee Sao wees eee ee ose ee ee eet ee eh eee eee eee eo eee tee ee eo 41 user program frag 0 gt no 1 gt with user program 42 43 iuser 0 44 2 2 45 read ascii or binary frag 46 47 write io 8 gt read binary to ascii 48 write io 1 gt read ascii to binary 49 read in end 993 iasb 50 2 2 2 2 91 7 read the name of input dump file 52 2 2 53 write io 54 write io put the file name of input dump file 55 56 57 58 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 87 88 89 90 91 92 93 94 95 96 97 98 99 198 181 182 183 184 105 106 107 108 109 110 111 112 113 114 115 116 117 118 119 120 121 122 123 124 125 100 687 read in a88 end 998 chin inquire file chin exist exex if exex eqv false then write io
4. 10 TTTTTTTTTTTTTTTTTTT 1 5 oL J Waler e void st 10 10 5 0 5 10 z cm Figure 4 13 Result of the cell section example 4 The Ist and 2nd cells are filled with void and water respectively 45 Cell section 4 5 3 Universe frame In PuiTs you can define some universes with a cell parameter A region of main space for particle transport calculation is filled with a corresponding region in any universe This function is very useful to set repeated structures introduced in Sec 4 5 5 An example using three spaces one main space and two universes shown in Fig 4 14 is explained below The main space includes two rectangular solids One universe has a cylinder filled with water and the other universe has an iron cylinder surrounded by water The 1st cell is filled with a region of the universe 1 and the 2nd cell is filled with that of the universe 2 a Main space 10 m r 5 F 1 5 0 L 1 2 void x C J st 10 LL Lia Lira a daria 10 5 0 5 10 z cm b Universe 1 c Universe 2 10 sf 0 E void EE water Se H m water iron 5 zl L 102 J Se 10 D 0 5 10 10 5 0 5 10 z cm z cm Figure 4 14 a Two rectangular solids b Cylinder filled with water c Iron cylinder in water List 4 12 cell section example 5 Material mat 1 1H 2 160 1 mat 2 Fe 1 cell 1 0 11 12 13
5. If a type is defined by positive number this mesh denotes cosine mesh If a type is defined by negative number the mesh denotes angle mesh Mesh definition is described later 122 5 COMMON PARAMETERS FOR TALLIES 5 6 Mesh definition There are 8 kinds of mesh definition as e type t type x type y type z type r type a type and 1 type The format is common for every mesh types So only the e type definition is described below For CPR 6699 ce other types replace e into t and a For example replace ne as nt nx ny na as tmin xmin ymin amin soon 5 6 1 Mesh type You can use 5 kinds of mesh type as shown below Table 5 2 mesh type mesh type explanation 1 give number of groups and mesh points by data 2 give number of groups minimum and maximum values mesh is divided equally by linear scale 3 give number of groups minimum and maximum values mesh is divided equally by log scale 4 give mesh width minimum and maximum values mesh points are given by linear scale Number of groups is set automatically as resulting maximum value becomes same with given value or takes larger value with small excess as possible 5 give minimum and maximum values and log value of mesh width mesh points are given by log scale Number of groups is set automatically as resulting maximum value becomes sam
6. 12 32 97 magnetic 14 12 4711041106 mat name color mat time change 111 material 3 L2 B1 74 76 77 80 82H88 158 172 matnamecolor 109 multiplier 5 2 116 136 parameters 12 19 74 89 106 131 150 photon weight 12 102 reg name 12 108 source HA 12 45 104 106 190 super mirror 12 112 surface 12 13 41 77180 821 88 20 93 176 t 3dshow 13 19 108 1 17 183 t cross 3 B 13 58 117 128 137 190 t dchain 4 13 117 171 t deposit2 13 21 L17 147 t deposit 2 B 13 1 1 17 L441 162 t dpa 13 117 156 t gshow 13 19 84 108 117 128 179 180 t heat B 13 L17 L41 162 t let 13 117 159 162 t product 3 5 13 19 117 152 t rshow 13 19 108 1 17 28 181 182 t sed 13 17 162 198 t star 13 LL 7 168 t time 3 5 13 11 7 165 t track 5 13 38 106 1 16 1 17 33 136 17 1 190 t userdefined 13 117 L75 t yield 13 D5 L 17 125 149 171 temperature 12 L00 timer 12 L 14 title I2 8 transform 12 78 85 90 P 1 5 P6 volume 12 32 09 1 19 172 weight window 12 98 ANGgL 5 2d type 127 128 134 140 143 145 148 150 155 3dshow 129 a curr 140 a type 2 3
7. 4 2 11 3 42 12 4 42 13 5 4 2 14 About geometrical 4 2 15 Input output filename 4 2 16 OME TS o ee ok m osos om OA ee V 4 2 18 Physical parameters for photon and electron transport based on the original model 4 2 19 Parameters for 5 ucc T Source section llle 4 3 1 Source Multi source less TD RISE ERE 4 3 5 Gaussian distribution source x y z independent 12 12 13 14 14 14 16 4 3 7 Gaussian distribution source 51 4 3 8 Generic parabola distribution source 51 VUE Bele Uc Red RUE UR RU SUR ti Bes 52 T1 5 bg e Meee BORE dO oe ee Ads CEA 53 43 1I stype 12 e Roe Row EOE Rom ex ew RR Roe ele 53 43 12 Cone Sl pe s s packs oR ae RR SOROR ko S E C3 d RR S EC 54 43 13 Reading dumphle s s sora ec VG oem B Nec exe 55 4 3 14 User definition source 57 4 3 15 Definition for energy distribution 60 4 3 16 Definition for angular distribution lees 65 4 3 17 67 4 3 18
8. 182 6 TALLY INPUT FORMAT For example you can obtain Fig 6 6 by the t rshow tally shown below from the example 6 in Sec List 6 5 t rshow example lt lt lt lt lt lt lt lt lt reg definition 101 1 10 1011010 1012 110 101 1 0 0 101 0 0 101 1 0 101 1 101 9 1 0 101 1 1 0 0 0 10 201 lt 101 1 1 0 lt 1 201 lt 101 0 1 0 lt 1 201 lt 101 1 1 0 lt 1 201 lt 101 1 0 0 lt 1 201 lt 101 0 0 0 1 lt 1 201 lt 101 1 0 0 lt 1 201 lt 101 1 1 0 1 201 lt 101 0 1 0 lt 1 201 lt 101 1 1 0 lt 1 Values 1 T rshow 2 mesh xyz 3 x type 2 4 nx 100 5 xmin 10 6 xmax 10 y type 1 8 1 9 5 0 5 0 10 z type 2 11 nz 100 12 zmin 10 13 zmax 10 14 axis xz 15 output 1 16 file cell example6 rshow dat 175 epsout 1 18 reg 19 28 21 value 22 non reg val 23 1 1000001 1 0000 00 201 24 2 1000002 2 0000 00 201 25 3 1000003 3 0000 00 201 26 4 1000004 4 0000 00 201 27 5 1000005 5 0000 00 201 28 6 1000006 6 0000E 00 201 29 7 1000007 7 0000 00 201 30 8 1000008 8 0000 00 201 31 9 1000009 9 0000E 00 201 10 T T T amp oL x L 5 10 10 z cm Figure 6 6 Example of t rshow 617 T 3Dshow section 183 617 T 3Dshow section T 3Dshow gives a gra
9. package Thus you can execute in Windows and Mac without compiling it For Linux you must compile PuiTS by yourself using make command coupled with an appropriate ForTRAN compiler 2 1 Operating environment PuiTs can be executed on Windows XP or later Mac OS X v10 6 or later Linux and Unix operating systems Recommended system requirements for are 2GB of RAM and 6GB at least 4GB is required of available space on hard disk There is no software you have to pre install before using PuiTs However we recommend you to install a text editor that can display line numbers since line number is specified if you make a mistake in your 175 input file Furthermore installation of Ghostscript and GSview is required to display image files created by PuiTS which are written in the EPS format An example of free text editor for Windows is e Crimson Editor http www crimsoneditor com For details of the installation of Ghostscript and GSview see the following web pages e Ghostscript http www ghostscript com e GSview http pages cs wisc edu ghost gsview index htm You have to recompile the source code in order to extend memory usage of PuiTs see Sec or define an original radiation source using usrsors f see Sec 4 3 14 Our recommended Fortran compilers are Intel Fortran Compiler 11 1 or later and gfortran 4 71 or later If you use other compilers errors may occur in compiling or executing PuITS
10. 2 2 Installation and execution on Windows For Windows you can install and execute PuiTs in the following way 1 If you have installed a previous version of PuiTs rename the installed folder to phits old or similar 2 Double click setup eng vbs 3 Define install folder We recommend to select c V 4 Right click phits lecture lec01 lecO1 in and select send to phits 5 Check whether track all eps is created or not If you want to execute PuiTs in memory shared parallel mode you have to change the environmental vari able PHITS to the number of cores you want to use You can specify this variable in phits bat in the phits bin folder From version 2 73 the installed executable file of the OpenMP version is available only on the 64 bit Windows system The installer setup eng vbs performs the following processes 1 Extract phits zip into the specified installation folder 2 Add phits bin in the environment variable PATH 3 Make shortcuts of three batch files phits bat and angel bat in phits bin folder and dchain bat in AphitsVdchain spVbin folder in sendto folder 4 Revise the first line of the nuclear data list file xsdir jnd in the phits data folder as datapath the installation folder phits XS 8 2 INSTALLATION COMPILATION AND EXECUTION OF PHITS 2 3 Installation and
11. sumtally start isumtally 2 D 1 sumtally option 1 2 weighted sum nfile 2 number of tally files result l out 2 0 result r out 3 0 sfile result s out file name of output by sumtally option sumfactor 5 0 D 1 0 normalization factor sumtally end You can obtain the same results by using multi source function but it is more convenient to use sumtally subsection when you would like to change the weighted values for several cases It should be mentioned that the sum of the weighted values is automatically normalized to sumfactor for isumtally 2 The output file obtained from this sumtally section result s out cannot be used for restart calculation 133 6 Tally input format 61 T Track section Using the T Track tally you can obtain the fluence in any specified region In this tally track length is evaluated whenever particles pass through the specified region as shown in Fig and the sum of the track lengths in the unit of cm is scored Then particle fluence in the unit of cm source is determined from the scored track lengths divided by the volume of the region and the number of the source particles track length Figure 6 1 T Track tally track length solid line is calculated For an example you can get information on the detector response in the specified region by utilizing this tally Multiplying the fluence by a cross section
12. ce11 section example 8 1 Material 2 mat 1 1H 2 1601 3 mat 2 Fe 1 4 Celi 5 1 0 10 13 14 2 3 4 6 2 1 1 0 11 12 13 14 15 16 3 LIKE 2 BUT TRCL 1 8 4 LIKE 2 BUT TRCL 2 MAT 2 9 5 1 10 13 14 18 Surface 11 18 18 12 11 PX 2 13 12 PX 2 14 13 PY 2 15 14 PY 2 16 15 PZ 2 17 16 PZ 2 18 Transform 19 trl 30 5 20 tr2 00 6 30 90 120 90 0 90 60 90 30 1 A 4 cm cube filled with water is defined in the 6th line and is put at the origin of the coordinate system Inside of this cube is the 2nd cell regarded as the original cell in this example In the 7th and 8th lines respectively the 3rd and 4th cells are defined with the LIKE n BUT format where n 2 Figure 4 20 shows the result of the example The coordinate system of the 3rd cell is transformed using the cell parameter TRCL 1 where the coordinate transform number 1 is defined in the 19th line in the transform section That of the 4th cell is also transformed with TRCL 2 Moreover the material inside of the cell is replaced with iron defined as the material number 2 in the 3rd line 10 E T T T gt E 5 4 LY 3 T 1 void OF 2 NEN iron x 1 water H LN 1 ory J7 F 10 Lp me roi 10 5 0 5 10 z cm Figure 4 20 Result of the cell section example 8 86 4 SECTIONS FORMAT Nesting structure with lattice A nesting structure can be used
13. D z0 maximum z coordinate cm dir direction cosine from z axis If you set all isotropic If you set data a type subsection is necessary phi D none random azimuthal angle degree dom D 0 0 solid angle degree 1 cos bias distribution projectile energy s type 13 MeV 4 3 8 Generic parabola distribution source x y plane This source is a generic parabola distribution in x y plane Parameters for generic parabola source are shown below The order of parameters is free If a parameter has a default value D the parameter can be omissible Table 4 30 parameters for generic parabola distribution s type 15 16 generic parabola source x9 D 0 0 x coordinate of X parabola center cm y8 D 0 0 y coordinate of Y parabola center cm ri parabola width in x y plane cm 20 minimum z of parabola cm 21 maximum z of parabola cm rn D 2 order of generic parabola dir direction cosine from z axis If you set all isotropic If you set data a type subsection is necessary phi Dznone random azimuthal angle degree dom D 0 0 solid angle degree 1 cos bias distribution projectile energy s type 15 MeV 52 4 SECTIONS FORMAT 4 3 9 Sphere and spherical shell distribution source Parameters for sphere and spherical shell source are shown below The order of parameters is free If a parameter has a default value D th
14. Next for 201 205 this combined region has volume 5 in the echo since this combined regions have 5 cells of bottom level This is also not required to re define here if the volume is set in the volume section For 161 lt 160 1 2 3 6 1 1 the region 161 is included as a lattice in region 160 In this expression in the lattice coordinate system 8 lattices of the region 160 from 1 to 2 in s direction 3 to 6 in direction and 1 in direction are used for the tally In the echo the number of regions in bottom level is echoed 1 In the case you have to specify the volume by yourself by the volume definition below For 201 202 283 204 161 162 163 some regions are defined in each level but these are all closed by so it means one region as a whole In this case given volume by the echo is not correct so set volume manually by the volume definition below For 98 188 128 lt 61 62 63 D there are two independent regions in each level so 4 regions are defined here In this case given volume by the echo is not correct too so set volume manually in the volume section You can set volume as below mesh reg 1234 5 lt 12 13 17 volume reg vol 1 1 0998 2 5 0000 3 6 0000 4 1 0000 10001 6 0000 10002 5 0000 In above example region numbers from 1 to 4 are set normally as you can see but regions 5 lt 12 and C 13 17 have numbers 10001 and 1000
15. amp C dmpd isdmp k k 1 isdmp 8 else write ia amp C dmpd isdmp k 1 isdmp 8 end if end if goto 100 500 continue write io end of read and write the data write io number of processed records is 3 amp 18 write io close id close ia goto 999 jrec 1 195 197 992 continue 198 write io Error ID should be 1 20 199 goto 999 200 993 continue 201 write io Error the ascii or binary frag is wrong 202 goto 999 203 994 continue 204 write io Error the number of records is wrong 205 goto 999 206 995 continue 207 write io Error the answer should be 9 or 1 208 goto 999 209 996 continue 210 write io Error the ID numbers is wrong 211 goto 999 212 997 continue 213 write io Error the number of data is wrong 214 goto 999 215 998 continue 216 write io Error file name is wrong 217 goto 999 218 999 continue 219 stop 220 end The input parameters are read from normal input i e from console in an interactive way When you execute the program it asks you as gt read binary to ascii 1 gt read ascii to binary You put 0 for binary 1 for ascii Next it asks you the name of target dump file put the file name of input dump file You put the name of target dump file put the number of data in a record The program ask
16. at every moment in the Pa Ts simulation namely at the same timing for calling the dumpall option A subroutine for output all information is written in the default usrtally f You can output only your required information by revising the file In T Userdefined you can use two parameters one is file for specifying a file name and the other is udtparai i 0 9 for specifying a numerical value These parameters can be used in the subroutine usr tally without recompiling PTs Table 6 35 t userdefined parameter name value explanation file file name Output file names used in subroutine usrtally The maximum number of files that you can use is 50 Device numbers of these files are from 151 to 200 udtparai omissible Parameters used in subroutine usrtally i 0 9 You can define from udtpara0 to udtpara9 List 6 3 Example of input for T Userdefined tally 1 file outputl dat lt its device number is iudtf 1 151 2 file output2 dat its device number is iudtf 2 152 3 udtpara 10 0 lt udtpara 0 4 udtpara3 20 0 lt udtpara 3 You can use the following parameters in subroutine usrtally 1 NCOL This is an intrinsic variable in the program and denotes identification of process NCOL 1 start of calculation 2 end of calculation 3 end of a batch 4 source 5 detection of geometry error 6 recovery of geometry error 7 termination by geometry
17. name value explanation ctmin i omissible D 9999 minimum value for i th counter ctmax i omissible D 9999 maximum value for i th counter trcl omissible coordinate transformation number or definition for r z or xyz mesh gslat 1 default 0 1 show lattice boundary in gshow 0 no 613 T Dchain section 171 6 13 T Dchain section This tally is used for generating input files for DCHAIN SP Figure 6 4 illustrates the flowchart of the connec tion calculation between PuiTs and DCHAIN SP PHITS DCHAIN SP DCHAIN SP data library Neutron activation cross sections with 175 group energy structure Nuclearreaction and transport calculations d Decay data library including gamma ray spectrum Files produced by T dchain Data library aboutratio of electron capture and beta decay nuclear production yield neutron energy spectrum with 175 group energy structure below 20 MeV Calculated results At arbitrary time Y Production yield Y Radioactivity Bq Y Decay heat W Y Gamma ray spectrum DCHAIN SP Calculation of production yield basic input file of DCHAIN SP Execution using shell script information about link to the folder having DCHAIN SP data library Figure 6 4 Concept of the connection calculation between PaiTs and DCHAIN SP In the PaiTs calcula
18. 1 the results are overwritten in same files On the other case of itall 2 the results after every batch are written in different named file Results are named by user specified name batch number The final results are written in the user specified file By using this functions you can terminate a calculation at any time with checking a latest result Also you can monitor the latest results with graphical plot automatically made by 175 See section 5 7 16 rijk written in the batch now file is the initial random number of the current batch For example in cases of unsuccessful termination of you can reproduce the calculation of the specified batch using the value of rijk 2 9 Array sizes 11 2 9 Array sizes You should check and modify the array sizes described in the param inc file The mdas is the most important variable It specifies the total size of arrays for geometry tally output nuclear data and bank You can find out the current use in a input echo corresponds output dat in previous example The bank size can be set in the parameter section If the bank becomes full odd arrays in mdas are used The default param inc is shown below List 3 3 param inc 1 dee ve ee dee ve de ve de ve de de dede dede dede eee ee ee ee de de de de de dede ee dede de dee eee ede e de de de dede dede dede de KKK 2 d 3i param inc 4 5 dede dede e ve e ve ve ve de ve de de de
19. 10 11 12 13 14 15 16 3 2 1 1 4 Surface 5 10 SZ 3 5 6 11 PX 6 75 12 6 8 13 6 9 14 6 10 15 PZ 6 11 16 PZ 6 A part surrounded by the parentheses in the 2nd line corresponds to the region of the 1st cell in the example 2 In this example a region combined inside of the cube and that of the sphere in the example 1 is defined with the union operator as the Ist cell The result is shown in Fig 80 4 SECTIONS FORMAT 10 m E a TOP ODGEOT P Ese opes apo mp Eg psg oy void x cm b 10 L 10 5 0 5 10 z cm Figure 4 12 Result of the cell section example 3 In the next example division of a cube into two regions by a spherical surface is shown List 4 11 ce11 section example 4 1 Material 2 mat 1 1H 2 160 1 3 cell 4 1 0 10 5 2 1 1 0 19 11 12 13 14 15 16 6 3 1 1 2 7 Surface 8 18 SZ 3 5 9 11 PX 6 10 12 PX 6 11 13 PY 6 12 14 PY 6 13 15 PZ 6 14 16 PZ 6 This surface section is the same of the example 3 In the 5th line the 2nd cell is defined with Li blank as an overlap region between the outside of the sphere which is the 10th surface and the inside of the cube defined by the parentheses The cell is filled with water defined in the material section and its situation is shown in Fig The inside of the sphere is the 1st cell and void
20. Material 2 den nuc lt 3 MAT 1 4 1 0000000E 04 1H 5 1 7238000 02 208Pb 6 4 6801000E 04 204Pb 7 7 9430000E 03 206Pb 8 7 2838000E 03 207Pb 9 MAT 2 10 1 0000000E 09 1H 11 4 6801000E 05 14N 12 7 9430000E 06 160 List 4 7 material example 3 1 Material 2 1 80196 49 5 9595d 5 3 80198 49c 3 9611d 3 4 80199 49 6 7025d 3 5 80200 49c 9 1776d 3 6 80201 49 5 2364d 3 7 80202 49 1 1863d 2 8 80204 49 2 2795d 3 9 c 10 m3 4009 37c 1 2362E 1 11 mt3 be 01 h20 25C 13 m4 1001 37c 6 6658d 2 8016 37c 3 3329d 2 14 mt4 lwtr 01 15 c b4c natural boron 25 density 16 m5 6812 37c 6 8118d 3 17 5011 37c 2 1825d 2 18 c liquid h2 28K 19 m6 1001 49 3 1371d 2 1011 49c 1 0457d 2 20 mt6 orthoh 00 parah 00 45 Cell section 77 45 Cell section 4 5 1 Formats In this section cells can be defined by surfaces described in the surface section The format for the definition is based on the General Geometry GG You should set a cell as a closed space and you can make a virtual space for particle transport calculation by combining the defined cells In PuiTS an outer region must be explicitly defined as a cell Only C and can be used as a comment mark but the cannot be used as a comment mark here since this character is used for the cell definition File including and variable definition can be used in this section
21. NASA naz ncut ndata ne nedisp negs neispl nesting structure neutron capture neutron optics 60 nevap nfile 131 NLIB nlost nm nn no ionization no reaction nocoh non npidk nspred ntmax nuclear nuclear data nucleus nuclide num 101 numb number of group 123 number of history 19 20 O CUIT 140 ob curr 140 of curr 140 Open MP 5I 9 OpenMP output 21 84 126 140 141 144 150 155 158 165 outtime 172 P 84 91 INDEX p type parallel parallel calculation parallel computing 5 9 param inc parameters section part 97 98 103 107 114 116 124 134 136 138 particle definition 124 particle density peut PE phi photo nuclear photon PHYS PLIB polarization 105 Pulse magnet 28 pwt PX PY PZ pz0 q type 65 66 914 qp 14 quadrupole electromagnet r I24 134 138 41 145 149 152 156 161 1631 165 r in T40 091 R JOMD 2123 r out 1401091 r type 120 122 r z 17 L 19 120 140 r0 49 54 r1 149 511 52 4 92 94 190 2 52 541 92 94 190 random number 162 RCC rdam i REC reg 19 47 55 57 84 861 88 9711100 10211104 106 109 113 114 117119 124 128 138 140 141 143 144 156 167 168 170 172 1811 183 190 I9T regio
22. You can use the skip operator non These three columns are always necessary to define the mat time change function 112 4 SECTIONS FORMAT 4 21 Super Mirror section The reflection of low energy neutron by super mirror is defined by this section We assume the following empirical formula to describe the reflectivity of the super mirrors f Ro if Q lt Q 5Ro 1 tanh MmMQA WD 1 a Q Q if Q gt Q where Q is the scattering vector in 1 defined by 47 sin 0 Q k kj The value of m is a parameter determined by the mirror material bilayer sequence and the number of bilayers Q is the critical scattering wave vector for a single layer of the mirror material At higher values of Q the reflectivity starts falling linearly with a slope o until a cutoff at mQ The width of the cutoff is denoted W These parameters are defined as Super Mirror r in r out mm qc am wm 2001 2020 3001 3 0 99 0 0217 3 8 0 003 2500 3500 3 0 99 0 0217 3 8 0 003 2600 3600 3 0 99 0 0217 3 8 0 003 The reflection surface is defined by the surface between r in and r out You can use the format 2 5 8 9 and you can use the lattice and universe style as 6 lt 10 1 9 0 lt a in these definitions The remaining parameters in above expression denote by mm Ro by by qc in Aa by amin A and W by wm in AT We restrict this function only to neutrons for the case that it
23. 1 cos bias distribution e8 projectile energy MeV e type type of energy distribution wgt Dz1 0 weight of source particle factor D 1 0 normalization of source particle omissible one can also specify below parameters t type D 0 time distribution reg D all specify the region ntmax D 1000 maximum re try number when reg is specified trcl D none transform number or definition of transform 56 4 SECTIONS FORMAT By the parameter of dump the number of the dump data in one record is specified If this number is given by positive number the data is read as binary data If negative the data is read as asci data In next line the data sequence of one record is described The relation between the physical quantities and id number is the followings Table 4 37 id number of dump data 1 physical quantities kf x y e wt tme cl c2 c3 sx sy sz id number 1 2 3 4 5 6 7 819 10 11 12 13 14 15 16 Table 4 38 id number of dump data 2 physical quantities name nocas nobch no id number 17 18 19 20 Here kf means the kf code of the particles see Table 3 4 x z are coordinates u v w denote the unit vectors of the direction of the particle e is the energy MeV or MeV nucleon for nucleus wt is the weight time is the initial time ns c1 c2 c3 are the
24. 145 148 150 155 158 161 tmax i TMP tmp tn totfact transform transform number TRC TRCL 47 77 78 85 129 135 140 143 146 151 trcl trcle 106 trclm 106 trxcrd dat tw TX TY typ TZ U udtpara 175 unit 125 126 134 138 141 143 145 147 149 153 universe UNIX usrelst usrmgt usrsors f 212 usrtally f Vavilov VOL vol 99 118 119 135 143 146 148 151 155 158 volmat 129 134 135 143 146 151 155 158 161 volume 32 P9 118 1 19 135 143 146 148 151 155 volume and area calculation 19 52 190 volume correction 129 voxel w ang w dst w hgt w mnh w mnw 183 w wdt wel i we2 i WED weight cutoff 103 weight window wem width 129 135 140 143 145 15 1 155 158 16 1 164 Windows 2 71 9 Wobbler magnet 0 wwi x 124 125 134 138 141 145 150 152 156 161 x ray 37 x txt 129 134 140 43 145 148 150 153 158 16 T x type 120 122 128 180 182 x0 49455 57 1 19 183 190 1 9 50 53 55 577 xnum 37 53 153 xsdir 35 74 XY PI xy Bil 24 127 128 134 135 033 140 14 0145 150 xyz 4 19 117 120 128 140 179 xz 135 140 141 150 155 156 158 161 163 165 168 RAIKAS CE T ELS 150 LES 22
25. 201 1 1 0 90 U 2 301 0 36 35 32 31 LAT 1 U 3 FILL 1 0 1 0 0 0 42 24 401 2 10 0 10 U 4 402 0 10 U 4 2 1 1 Surface 18 0 5 11 PX 6 12 PX 6 13 PY 6 14 PY 6 15 PZ 6 16 PZ 6 21 PX 2 22 PX 2 25 PZ 2 26 PZ 2 31 PX 1 32 PX 1 35 PZ 1 36 PZ 1 98 BOX 10 10 10 2000 9 200 9 9 20 The virtual space made by this input is shown in Fig The nine square poles are defined with the lattice parameter Furthermore three of these consist of 4 units of the other lattice The 1 8 1 in the 8th line denotes the transformation of the coordinate system that the origin is shifted by in the x and z direction When you specify any cell using mesh reg in tally sections you can use the lattice and universe styles as 402 lt 301 1 1 0 lt 101 8 0 0 lt 1 where the lattice coordinate is represented by s t u See also Sec 5 1 2 for this format 10 Lt T T T T TTT T T LU T 17 5 F water OF E void L iron s 10 Leppert 10 5 0 5 10 z cm Figure 4 22 Result of the cell section example 10 88 4 SECTIONS FORMAT Voxel phantom In you can make a virtual space using voxel phantom for calculation on complex structures such as the human body or organism First a little cube is defined as a unit of the lattice with LAT 1 Second you set a repeated structure of a large size using the unit Third you
26. 4 62 63 5 volume combined lattice or level structure 6 non reg vol reg definition Ta 1 10001 8 1000E 01 all 8 2 10002 5 0000 00 201 205 9 3 10903 1 0000 00 161 lt 160 131 D 10 4 10004 1 0000 00 161 lt 160 231 D 11 5 10005 1 0000E 00 161 lt 160 14 1 D 12 6 10006 1 0000 00 161 lt 160 24 1 D 13 7 10007 1 0000E 00 161 lt 160 151 D 14 8 10008 1 0000 00 161 lt 160 251 D 15 9 10089 1 0000 00 161 lt 160 161 D 16 19 10010 1 0000 00 161 lt 16098 26 1 D 17 11 10011 4 0000 00 C C 201 204 lt C 161 163 2 D 18 12 10012 2 0000E 00 98 188 lt 61 19 13 10013 1 0000 00 120 lt 61 20 14 10014 2 0000E 00 90 100 lt 62 63 D 21 15 10015 1 0000 00 120 lt 62 63 D In the input it looks only 5 regions defined but in the input echo you can see 15 regions are defined for tally In this input echo region numbers are defined automatically starting from 10001 and the volume of each cell is set 1 because of no volume definition 5 1 Geometrical mesh 119 We explain the detail of 15 regions appears in the volume description of this input echo First for all 81 cells are defined in the bottom level so the volume of all is set 81 If the volume of the cell is defined correctly in the volume section you don t need to define the volume here again
27. 75 E61 163 y txt 29 34 40 L3 145 148 L50 753 8 T6 T y type 120 122 128 180 182 INDEX y0 49 55 57 L19 183 90 y1 491 50 53455 57 yp 53 yq 53 yz 124 128 134 135 138 140 141 145 150 152 z 12434 138 141 145 129 50 ES2 ES6 61 163 z txt 129 134 140 143 145 148 50 755 58 6 1 z type 120 122 128 180 182 z0 49155 57 L83 90 z1 4915153155 57 zlin 181 zlog 181 ZP 9 1 zx 124 128 PHITS ver 2 76 User s Manual Ver 2 30 2011 08 18 Ver 2 30a 2011 12 02 Ver 2 30b 2012 08 23 Ver 2 52 2012 12 27 Ver 2 60 2013 08 22 Ver 2 62 2013 09 26 Ver 2 63 2013 10 23 Ver 2 63a 2013 11 02 Ver 2 64 2013 11 19 Ver 2 64a 2014 01 09 Ver 2 65 2014 01 30 Ver 2 66 2014 02 21 Ver 2 66 2014 05 22 Ver 2 70 2014 08 30 Ver 2 71 2014 09 26 Ver 2 72 2014 10 21 Ver 2 73 2014 11 05 Ver 2 74 2015 01 30 Ver 2 75 2015 02 09 Ver 2 76 2015 03 17 PuiTs development members Koji Niita Norihiro Matsuda Shintaro Hashimoto Yosuke Iwamoto Hiroshi Iwase Tatsuhiko Sato Takuya Furuta Tatsuhiko Ogawa Shinichiro Abe Hiroshi Nakashima Tokio Fukahori Keisuke Okumura Tetsuya Kai Satoshi Chiba and Lembit Sihver Research Organization for Information Science amp Technology RIST Japan Atomic Energy Agency JAEA High Energy Accelerator Research Organizat
28. Data are written by below format y x x ix ix 1 do 1 1 C 1 data ix iy 1 end do nx 1 data are written in a line and total ny 1 lines It is useful to use in the tabular soft like Excel 128 5 COMMON PARAMETERS FOR TALLIES 5 7 12 gshow definition This option can be used in all tallies without t gshow and t rshow If you set gshow option with xyz mesh Xy yz xz axis and 2d type 1 2 or 3 ANGgL can create a graphical plot with region boundary and material name or region name or lattice number on the two dimensional output You can also obtain graphical plots directory from the PzuiTs calculation by the epsout option gshow 9 1 2 3 4 In above example 0 means no gshow option 1 means gshow with region boundary 2 means gshow with region boundary and material name 3 means gshow with region boundary and region name 4 means gshow with region boundary and lattice numbers When you increase the resolution of the plot by resol parameter the indication of region name material name and lattice number on the graph are sometimes disturbed In this case you should increase the mesh points instead of resol You can see your geometry plot on a graph without transport calculation by setting icntl 8 inthe parameters section and this gshow option You should check whether regions are correct and a xyz mesh resolution is good or not before long ti
29. Error the file does not exist goto 999 end if if iasb eq 8 then open id file chin form unformatted status old else open id file chin form formatted status old end if write io write io put the number of data in a record read in end 997 isdmp 0 write io write io put the ID numbers of data in a record read in end 996 isdmp i i 1 isdmp 8 do 1 isdmp 0 if isdmp k gt 20 or isdmp k le 0 goto 992 jsdmp isdmp k k end do write io write io dump data 30 a4 dmpc isdmp j j 1 isdmp 9 write io write io put the file name of output read in a88 end 998 chot inquire file chot exist exex if exex eqv true then write io write io Warning the file already exists write io Do you want to overwrite write io Yes lt 0 No lt 1 read in end 995 iyes if iyes ne 0 goto 999 end if if iasb eq 0 or iuser ne 0 then open ia file chot form formatted status unknown else open ia file chot form unformatted status unknown end if write io write io put the number of records to read write io all lt 8 or positive integer read in end 994 irec write io write io start read and write the data jrec 0 jrec jrec 1 if irec gt 80 and
30. GeV excitation energy MeV kinetic energy MeV weight time nsec coordinate cm y coordinate cm Z coordinate cm 6 TALLY INPUT FORMAT 615 T Gshow section 615 T Gshow section T Gshow gives graphical geometry output for region boundary by xyz mesh You can obtain these results without transport calculations with icntl 7 option in the parameters section Table 6 36 t gshow parameter name value explanation mesh XYZ geometry mesh only xyz mesh you need geometry mesh subsection below this option axis Xy yz XZ 2 dimensional file file name Define file names as same number of axis output 1 region boundary 2 region boundary material color 3 region boundary material name 4 region boundary material color material name 5 region boundary region name 6 region boundary material color region name 7 region boundary LAT number 8 region boundary material color LAT number resol 1 default The resolution in displaying region lines is multiplied by this value width 8 5 default The thickness of displayed region lines title omissible title angel omissible angel parameters x txt omissible x axis title y txt omissible y axis title epsout O default 1 If epsout is set to 1 results are plotted into eps files This eps file is named by replacing the extension into trcl omissible coordinate
31. Microscopic treatment of ionization process without using the continuous slowing down approximation 2 High energy photo nuclear reaction model applicable to energies above 20MeV 3 Transports of high energy electrons positrons and photons by incorporating the 5 codd Request for future improvements as well as report of bugs and defects are very much welcome More information on PuiTs is available from its web site http phits jaea go jp REFERENCES 205 Acknowledgement We would like to thank the developers of NMTC JAM Hiroshi Takada Shin ichro Meigo Makoto Teshi gawara Fujio Maekawa Masahide Harada and Yujiro Ikeda for their collaborations References 1 H Iwase K Niita T Nakamura Development of general purpose particle and heavy ion transport Monte Carlo code J Nucl Sci and Technol 39 1142 2002 2 T Sato Iwase Nose Nakashima L Sihver PHITS a particle and heavy ion transport code system Radiation Measurements 41 1080 2006 3 Niita et al High Energy Particle Transport Code NMTC JAM JAERI Data Code 2001 007 Japan Atomic Energy Research Institute 2001 4 Y Nara N Otuka A Ohnishi Niita S Chiba Relativistic nuclear collisions at 10A GeV energies from p Be to Au Au with the hadronic cascade model Physical Review C61 024901 1999 5 K Niita S Chiba T Maruyama H Takada T Fukahori Y Nakahara and A Iwamoto
32. Table 4 14 parameter 13 parameter value explanation ivoxel D 0 read and write voxel data in binary not using file 18 1 read from voxel data in binary file 18 write down voxel data in binary on file 18 dumpall D 0 dumpall option no dump 1 write down all information on file 15 as binary data l write down all information on file 15 as ASCII data idpara D 3 dumpall file name option in the parallel calculation wk uname file name of 11 15 1 wk uname file name of 1 15 number 3 file name of 11 15 number wk uname wk is the default directory name uname is a user name read in from environment variable LOGNAME For time shortening you can use ivoxel parameter When you perform P Ts calculation with ivoxel 2 voxel data are output in file 18 in binary and then the calculation is stopped continued until ver 2 30 From the next calculation with ivoxel 1 a process of the data output is omitted and the calculation time is shortened By icntl 12 PuiTS re calculates whole transport by reading the information from dumpall file which is cre ated if you use the dumpall option The re calculation can describe whole transport events which were calculated before One needs the same input file as used in the previous calculation maxcas and maxbch cannot be changed but are read from the file It is very powerful when you want to calculate different tallie
33. data sequence define the data sequence gslat 1 default 0 1 show lattice boundary in gshow 0 no 140 6 TALLY INPUT FORMAT Output options output f curr b curr of curr ob curr can be used in xyz or r z mesh Note that in xyz mesh these options are available only for z direction In the t cross tally you can use the dump option only with reg mesh and only with reg axis If the dump option is set the meshes of e type a type and t type have only the meaning of the maximum and minimum values The output option is set to be current a curr or oa curr When you use this dump parameter axis and file are restricted to one axis and one file and unit is always 1 The dumped data are written on a file named ee dmp where indicates the file name specified by file The normal output of the tally is written on From this file you can get the information on the total normalization factor To do so you had better set one mesh for e type a type and t type In the former version of PHITS before 2 66 the normal output was written on a configuration file cfg and the dumped data were written on If you set mesh reg for geometry mesh in this section you must define crossing surface by region number for in and out region as an example below mesh reg reg number of crossing surfaces r in r out area 2 8 10 0 3 8 5 0 45 45 2 0 13 5 14 lt 5 7 0 13 6 14 lt 6
34. default same with no definition When you set number of materials define these material numbers in the next line You cannot set number of materials by negative region numbers next line 258 material numbers reginbox omissible regions in the box for display all all default same with no definition If the matinbox is defined for this region this region is not displayed resol 1 default The resolution in displaying region lines is multiplied by this value width 0 5 default The thickness of displayed region lines file file name Define file names as same number of axis title omissible title angel omissible angel parameters X txt omissible X axis title y txt omissible y axis title z txt omissible Z axis title epsout 0 default 1 If epsout is set to 1 results are plotted into eps files This eps file is named by replacing the extension into eps Definition rules for reg and reginbox are the same as that for the region mesh in section 5 1 1 For saving calculating time an outer region defined by the radius r out is introduced additionally You have to use a larger r out value when you use large geometry or you want to put the light source and view point far away This new definition of the outer region can be seen in input echo Therefore you can not use an input echo by icntl 11 as an input for next calculation Shadow is not created if
35. for manual parallel computing rseed D 0 0 initial random number option rseed lt 0 get a initial random number from starting time rseed 0 6647299061401 default rseed gt 0 use rseed as initial seed of random number maxcas D 10 Number of history per batch The upper limit is 2147483647 maxbch D 10 Number of batch The upper limit is 2147483647 maxbnk 0 10000 size of bank array istdev D 0 Control parameter for calculation procedure of statistical uncertainties and the restart mode 2 The restart calculation mode is activated but if there is no past tally result a new calculation is started with istdev 2 1 The restart calculation mode is activated but if there is no past tally result a new calculation is started with istdev 1 0 istdev is automatically set to 1 for memory shared parallel computing and 2 for the other cases 1 A new calculation is started Statistical uncertainties are estimated from the variances of each batch result 2 A new calculation is started Statistical uncertainties are estimated from the variances of each history result You cannot select this option in the memory shared parallel mode ireschk D 0 Control parameter for tally consistency check 0 Check consistency between new and old tally settings 1 No check This option is useful when you set a very complex tally whose settings are not fully written in the tally output file In the PuiTs parallel c
36. from the originally activated target are not included in the DCHAIN SP calculation Tetsuya Kai et al DCHAIN SP 2001 High Energy Particle Induced Radioactivity Calculation Code JAEA Data Code 2001 016 2001 in Japanese 172 6 TALLY INPUT FORMAT Table 6 34 t dchain parameter name value explanation mesh reg Geometry mesh Currently ONLY region mesh reg can be specified You need to write the geometry mesh subsection below this option reg cell number file file name Input file name of DCHAIN SP You can use any extention except for dtrk dyld dout title omissible Title timeevo number Number of irradiation and cooling steps in DCHAIN SP calculation next line time factor Time step of irradiation and or cooling Normalized factor for beam intensity Time should be calculated from the end of last step not from the start of the first irradiation The allowable units are seconds s minutes m hours h days d and years y One or more blank character must be placed between the number indicating the time and the units See the example of input for t dchain tally in List 6 1 outtime next line number time Number of output timing in the DCHAIN SP calculation Output timing If a positive value is given as output timing it is calculated from the start of the first irradiation step If a negative value is given as output timing it is calculated from
37. in t yield and t product we can tally the yield and product quantities below dmax 2 Third the heat from neutrons is usually obtained from Kerma factors in the data base region In this mode the heat from neutrons is Zero but the heat is calculated from energy loss of all charged particles and nucleus Fourth DPA values is obtained even for the energy below dmax 2 without DPA data base 43 Source section 43 Source section 45 You can set source information in this section The source type is specified by the number of s type N Table 4 22 source type source type explanation s type 1 cylinder or circle pencil s type 4 cylinder with energy distribution s type 2 rectangular solid or rectangle s type 5 rectangular solid with energy distribution s type 3 Gaussian x y z independent s type 6 Gaussian with energy distribution x y z independent s type 7 generic parabola x y z independent s type 8 generic parabola with energy distribution x y z independent s type 9 sphere or spherical shell s type 10 sphere or spherical shell with energy distribution s type 11 uniform distribution in a phase space vertical with beam direction s type 12 reading the data from decay turtle output s type 13 Gaussian x y plane s type 14 Gaussian with energy distribution x y plane s type 15 generic parabola x y plane s type 16 generic parabola with
38. is an error fc lt 1 multiply forced collision probability by fcl instead the weight is reduced by 1 fci times We have two options between the multi scattering and the weight cut off in the forced collision region When fcl 0 secondary particles produced by forced collisions are treated by the normal process In this case weight cut off is not performed When fcl gt 0 the forced collision is also applied to secondary particles In this case weight cut off is performed Even if a particle is killed by this weight cut off of course the particle is tallied before killed There is a possibility that all particles are killed by this weight cut off if you set the weight cut off and the forced collisions without consideration You should give attention about it 104 4 SECTIONS FORMAT 415 Magnetic Field section 4 15 1 Charged particle You can set a magnetic field in the 75 calculation Cell number reg magnetic field type typ half distance of magnets gap cm magnetic field intensity mgf transformation trc1 and time dependence time should be defined as Magnetic Field reg typ gap mgf trcl time 1 4 10 00000 5 956540 3 non 2 4 10 00000 6 416140 1 non 3 2 10 00000 7 611980 9 0 0 4 2 10 00000 3 516000 9 pi 2 158 lt 61 4 13 00000 7 880140 2 non 150 lt 62 4 13 00000 7 440800 2 non C 150 lt 63 4 13 00000 9 441010 2 non 158 lt 64 4 13 00000 8 295220 2 non 158 lt 65 4 1
39. isumtally 131 itall itstep 106 iunr ivout ivoxel izst JAM JAMQMD JENDL jmout JOMD K X K Y K Z kf code 1124 kf code kmout KUROTAMA KX KY KZ 1 dst phi 183 1 the 183 l type 159 Landau LAT lattice 4 47 78 821 84H88 97H100 102H104 107 114 209 lattice coordinate system let letmat letmat1 letmat2 level level density level structure 119 lib library 19 22 74 75 156 158 168 LIKE n BUT LIKE n BUT line 183 Line Connecting line connection 122 lineal energy 162 Linux little lost particle Ipolar Lynch s formula Mac macro body magnetic field make 9 MARS PF mass mass density MAT mat BI 74 76 109 11 T 1 T6 136 158 matadd material 5 164 16 material name 128 material number 101 1 151 155 15 maxbch maxbnk maxcas maximum maximum value MCNP mesh 84 86H88 177120 123 134 135 13 155 167 16 mesh definition mesh type 122 mesh width mgf minimum minimum value mirror 183 Moliere 5 ON IA ico ee ION oo l nl 17 lee No 210 mother MPI S 9 mset mt multi source multiplier muon capture muon capture reaction I Muon induced nuclear reaction muon induced nuclear reaction mxlv na name
40. jrec gt irec goto 500 continue if iasb eq 8 then read id end 688 err 690 193 194 126 127 128 129 130 131 132 133 134 135 136 137 138 139 140 141 142 143 144 145 146 147 148 149 150 151 152 153 154 155 156 157 158 159 160 161 162 163 164 165 166 167 168 169 170 171 172 173 174 175 176 177 178 179 180 181 182 183 184 185 186 187 188 189 190 191 192 193 194 195 196 amp dmpd isdmp k 1 isdmp 8 else read id 30 1p1d24 15 end 688 err 690 amp dmpd isdmp k 1 isdmp 8 end if goto 689 688 if irec gt 0 then rewind id goto else goto end if 690 continue iserr 687 500 iserr 1 write io Error in dump file no i5 goto 687 689 continue 8 PROCESSING DUMP FILE if iuser ne 0 then do k 1 20 if jsdmp k gt dmpp k dmpd k end do kf nint dmpp 1 dmpp 2 y dmpp 3 z dmpp 4 dmpp 5 dmpp 6 w dmpp 7 e dmpp 8 wt dmpp 9 t dmpp 10 nl nint dmpp 11 n2 nint dmpp 12 n3 nint dmpp 13 sx dmpp 14 sy dmpp 15 sz dmpp 16 n8 nint dmpp 17 nc nint dmpp 18 nb nint dmpp 19 no nint dmpp 20 if iuser eq then if iasb eq then write ia 30 1p1d24 15
41. should be the same II maxcas written in the input file is not used in the restart calculation of the batch variance mode III The consistencies of input parameters except for those given in the tally sections are not checked Hence you have to make them identical by yourself in the restart calculation 22 4 SECTIONS FORMAT 4 2 3 Cut off energy and switching energy Table 4 3 parameter 3 parameter value explanation emin 1 D 1 0 proton cut off energy MeV emin 2 D 1 0 neutron cut off energy MeV emin i D 1 0 cut off energy for i th particle MeV i 3 10 i particle id see Table 3 4 emin 11 0 2 0 cut off energy for others MeV emin i D 1 e 9 cut off energy for i th particle MeV i 12 19 i particle id see Table 3 4 i 15 19 energy unit is MeV nucleon esmin D 0 001 minimum energy for range calculation for the charge particles MeV esmax D 300000 maximum energy for range calculation for the charge particles MeV cmin i D emin i nuclear reaction cut off energy for i th particle MeV any nuclear reactions under cmin i are not treated i 15 19 for these nucleus energy unit is MeV nucleon dmax 1 Dzemin i maximum energy of library use for i th particle A value itself given by these parameters is included in a lower limit and not included in a upper limit For example a proton at just the energy of emin 1 is not cut off PuiTs uses librari
42. this mode the effect of thermal motion of materials is not considered It means that we always assume T 9 in this mode These parameters are automatically set if you specify e mode 1 or 2 unless explicitly specified igamma 2 is selected For consistency reason the combination igamma 1 and e mode 1 is also supported Event generator mode Ver 2 is the improved version of the legacy version i e event generator mode Ver 1 In reactions emitting multiple neutrons previous event generator mode samples the first ejectile neutron from the cross section data and emission of the subsequent particles is simulated by the statistical decay model While ver 2 samples all the ejectile neutrons from the cross section data and the statistical decay model is used merely to simulate prompt gamma ray production As for capture reactions previous event generator mode assumes that the target nucleus absorbs incident neutron and particle emission is simulated by the statistical decay model In this case ejectile particle species are fully determined by the statistical decay model While ver 2 selects the ejectile particle species depending on the reaction channel i e in n reaction emission of only one alpha particle and gamma rays are allowed By this mode we can obtain the following new observables which cannot be detected without this mode First the deposition energy distribution in t heat tally is available for low energy regime below dmax 2 Second
43. wk is the default directory name uname is a user name read in from environment variable LOGNAME It is noted that the default of incut and igcut were changed to be 0 In the parallel computing files corresponding to each PE Processor Element are created for writing the output If you set inpara igpara or ippara 0 or 1 a file is made in the directory named by wk uname on each of the nodes If you set inpara igpara or ippara 1 or 3 the each PE number is put at the end of the filename The each PE writes down its result on only the corresponding file 42 Parameters section 4 2 11 Output option 3 Table 4 12 parameter 11 31 parameter value explanation itall D 8 options for tally output after every batch 0 no output 1 in same file 2 in different files file name specified file name batch number itstep D 8 option for timing of tally for changing momentum like magnetic field 0 tally at reaction or surface cross normal 1 tally at each step of the transport imout D 8 option for specifying the output format of material section e g mat 12 208Pb 33c 1 e g mat 12 Pb 208 33c 2 e g m12 82208 33c MCNP type jmout D 8 option for specifying the output format of material density in material section 0 no conversion 1 converting particle density kmout D 0 option of nuclear data information no display 1 writing in input echo matadd D
44. yZ XZ TZ 2 dimension mass Mass distribution If the case nucleus is specified isotope distribution charge Charge distribution Nucleus can not be specified chart Nucleus chart x N y Z Nucleus can not be specified dchain for dchain sp output All isotopes are output only mesh reg For this tally only one axis parameter is defined in a t yield section file file name Define a file name to output resfile omissible D file Define a file name of the past tally in the restart calculation Even if several axis parameters were defined you should specify only one resfile output omissible change the timing of the score product default Nuclei produced by nuclear reaction are tallied cutoff Nuclei stopped by energy cutoff are tallied If nuclei are not transported this is the same as product info 0 1 With stable nuclei and magic number for chart factor omissible D 1 0 normalization factor title omissible title angel omissible angel parameters 2d type 1 2 3 4 5 6 7 options for 2 dimensional plot omissible X txt omissible X axis title y txt omissible y axis title z txt omissible Z axis title If you specify output cutoff the parameters of part mother are neglected When igamma 3 in parameters section you can obtain information on the isomer production based on EBITEM model by setting axis chart dchain in this tally 6 6 T Yield section Table 6 15 t yield p
45. 1 material name 2 region name 3 and LAT number 4 are plotted by the option rshow default 1 2 3 When mesh reg axis xy yZ XZ region border 1 material name 2 and region name 3 are plotted by the option You need xyz mesh section below this option ginfo 0 default No geometry check in the case of gshow or rshow gt 0 1 Check geometry and draw its two dimensional view with error information 2 Check geometry draw its two dimensional view and outputting a geometry error file err resol 1 default The option multiplies region line resolution by resol times with gshow or rshow option width 8 5 default The option defines the line thickness for gshow or rshow option volume omissible The option defines volume for each region for reg mesh You need volume definitions below this option Default values are given in input echo in the case of no definition reg vol volume definition See 5 1 2 iechrl 72 default Number of maximum column for volume input echo volmat omissible D 9 The option corrects a volume value for each mesh when material is defined by xyz mesh 0 means no correction Value of volmat means the number of scans for one side of xyz mesh epsout 8 default 1 If epsout is set to 1 results are plotted into eps files This eps file is named by replacing the extension into ctmin i omissible D 9999 minimum value for i th
46. 2000 3000 4000 5000 z cm o Figure 4 9 duct source option example 2 74 4 SECTIONS FORMAT 44 Material section 4 4 1 Formats Material 15 defined in this section There are two formats for material definition as shown below First the conventional format as Material m nucleus density nucleus density nucleus density nucleus density MAT m keyword value nucleus density nucleus density MIm S a b identifier MATE m In addition other definition format can be used as Material Mm nucleus density nucleus density nucleus density nucleus density Mm keyword value nucleus density nucleus density nucleus density nucleus density MIm S a b identifier Mm Here m can be specified up to material number 9999 unless over defined 4 4 0 Nuclide definition The nucleus can be defined by various format as 208Pb Pb 208 82208 Hydrogen is defined as 1H H 1 1001 You can use natural isotope ratio if you use no mass style as Pb 82000 If you want to use nuclear data add library number double digit and data class a character a z after nuclide definition after period as 208Pb 24c Pb 208 24c 82208 24c Note that the format of the natural isotope ration cannot be used when the library has no information on it In the case that you do not add such extension PuiTs searches the cross section directory file file 7 D xsdir from the top li
47. 47151 55 571 65 66 12 1 122 138 abnormal end 198 abort 10 absorption agl 66 ag2 66 all 116 134 136 138 141 144 149 152 158 159 amp 172 andit 26 angel 134 140 143 45 148 150 55 158 161 163 AnGzL I0 1 126 127 129 T8T D00 angle 138 angle mesh 121 angle straggling area 140 190 191 ascat1 27 ascat2 27 ATIMA axis 21 25 38 124 125 127 128 134 135 138 140 b curr 140 Baba bank basic motion batch batch now Bertini bias 101 blank bnum Boolean operator 771 79 BOX bremsstrahlung C X C Y C Z cdiam 162 cell definition cell number cell parameter CGVIEW charge chart cluster plot cmin i color color plot 127 comment mark 206 INDEX compilation 7 9 compile COND contour 127 coordinate transform number 85 90 COS cosine Coulomb diffusion 27 counter CPU time cpu time ctmax 129 135 140 143 146 148 15 1 155 158 161 ctmin 129 135 140 143 146 148 15 T 155 158 16 T Cugnon current cut off energy cut off time cut off weight 24 cutoff 165 CX CY CZ data file dchain decay decay turtle dedxfnc dedxfncl dedxfnc2 delayed neutron deltO delta ray deltb deltc deltg deltm deltt density deposit deposit energy 162 detail
48. 5 3 LET mesh 5 4 Time mesh oy 4o RUE GR RA Eos RUE SOR NOE RU Y RUE 5 Angle Mesh ee xum Y Y QORUSCRUNUE SE EA ee NOE E Ee ee ADR 5 6 Mesh definiti n i e wa EU EGO eee EE Ea Se YR 25 0 Me shtypel 4 Sac Peri Pee SOROR 502 etype Wisk o dU ur tL bh be eae E ee ee 6 3 e type 2 3 6 4 e type 4 56 9 etype z5 i ks ae oak bo a ER PRES Pos y Pe Or 4 b 2 4 Other tally definitions sis 2556 4004 SU 5 7 1 Particle definition 5 75 2 axis definon 4 3 4 30 v HORROR PA EYE Y bom BSR vu 5 7 4 resfile definition 5 75 unit definition ap as y e AEGA E UR E E AOp R E e N E DGA e e SA 5 7 6 factor definition 5 7 7 output definition 5 7 8 info definition 5 79 title definition 2 AE e E AEA E OR D A A en ane eee ors E Se fe Rane ELT 5 7 14 x txt y txt z txt 5 7 15 volmat definition so como o Eoo Roo GR Tomo om RC GR S CE oe C 5 7 17 5 7 18 resolution and line thickness 5 Jd DE Tally input for
49. From ver 2 72 we fixed a bug occurs in setting igamma 2 and corrected an error that the GEM model produces di neutron Furthermore we changed the definition of na and nn in source section using a type You cannot set these parameters to be negative In the former version an error would occur when you set na or nn to be negative with giving angular distribution by degree From ver 2 71 we fixed a bug about electron positron annihilation occurred when EGS5 was used From ver 2 70 the following functions were implemented Transport algorithm for photons electrons and positions in EGS5 Electron Gamma Shower Version 50 was incorporated You can use this algorithm instead of the original one by setting negs 1 parameters section In addition 11 20 must be specified At this moment you cannot set negs 1inthe OpenMP version of PaiTs The maximum number of material is limited to 100 when negs 1 See Sec 12 T9 in detail This improvement was supported by Dr Hirayama and Dr Namito of KEK High energy photo nuclear reaction can be treated up to 100 GeV by implementing non resonant photo nuclear reaction mechanism in JAM Muon induced nuclear reaction can be treated up to 100 GeV by considering the generation of virtual photon from muon You can activate this model by setting imuint 1 parameters section The event generator mode ver 2 was improved to precisely determine the charged particle spectra on the basis
50. Iida of Kochi University and Dr Kazuhiro Oyamatsu of Aichi Shukutoku University e Intra Nuclear Cascade with Emission of Light Fragment INC ELF was implemented Uozumi research group performed this development under collaboration between Kyushu University and JAEA A user defined tally named t userdefined was introduced in order to deduce user specific quantities from the simulation Re compile of 175 is required to use this tally See Sec 6 14 in detail The neutron Kerma factors for several nuclei such as CI were revised The photo and electro atomic data libraries were newly developed based on JENDL 4 0 and the Livermore Evaluated Electron Data Library EEDL respectively From ver 2 30 the radiation damage model for calculating DPA Displacement Per Atom in PuiTs was improved using the screened Coulomb scattering We also added the multiplier section to be used in the t track section From ver 2 28 you can use options of dumpall and dump for t cross t time and t product tallies also on the MPI parallel computing When these options are used in parallel computing PHITs makes PE 1 files for writing the dump information from each node where PE is the total number of used Processor Elements 175 can also read the dump files in the parallel computing From ver 2 26 we added the function to generate knocked out electrons so called rays produced along the trajectory of charged particle Setting th
51. Lethargy SR source 1 cm Lethargy SR source 1 nsec SR source 1 cm nsec SR source 1 MeV nsec SR source 1 cm MeV nsec SR source 1 Lethargy nsec SR source 31 32 33 34 35 36 ee pend 1 cm Lethargy nsec SR source 153 Lethargy in unit 5 6 15 16 25 26 35 or 36 is a natural logarithmic unit of energy and defined by In E E using a reference energy Eef and a particle s energy If you set these units you can obtain results per Lethargy which are calculated by Lethargy widths In Eni at each energy bins given in the energy mesh subsection Here Enign and are maximum and minimum values of the energy bins respectively 154 6 TALLY INPUT FORMAT Table 6 18 t product parameter 3 name value explanation axis eng reg x y Z r xaxis value of output data Xy YZ XZ IZ 2 dimensional t time axis file file name Define file names as same number of axis resfile omissible D file Define a file name of the past tally in the restart calculation Even if several axis parameters were defined you should specify only one resfile output source source particle nuclear default particles from nuclear reaction including elastic nonela particles from nonelastic collision elastic particles from elastic collision decay particles from decay fission particles from fission factor omissible D 1 0 nor
52. Output including geometry errors When ginfo 2 and PHITS detects a geometry error a geometry error file named err is outputted indicates the original tally output file name without extension In this file the x y z coordinates together with the overlapping cell numbers are written as follows Errors of cell definition in EPS Page No 1 Overlapped Cell IDs y z coodinates Cells 0 indicate undefined region 100 102 4 847761E 00 1 234568 11 1 211940E 00 0 0 4 241791E 00 2 500000E 00 8 079602E 01 The first line indicates that cell number 100 and 102 are overlapped at the point of x 4 847761E 00 y 1 234568E 11 z 1 211940E 00 The second line indicates that undefined region is detected at the point of x 4 241791 00 y 2 500000E 00 z 8 079602E 01 You can easily find geometry errors using this geometry check function It should be noted that this function can detect geometry error only when the error occurs on the grid points of the xyz mesh of the tally Thus geometry errors outside the tally region cannot be detected Even in the tally region a small error region may also be undetected because the error region might not contain any grid point 198 11 ADDITIONAL EXPLANATION FOR THE PARALLEL COMPUTING 11 Additional explanation for the parallel computing There are two types of parallel computing method one is the distributed memory parallel computing using MPI protocol and the other is the s
53. The number of the particle generation at the each energy point is proportional to w i e type 9 19 You can specify the same energy distribution as is the case of e type 8 18 Unlike e type 8 18 the distribution is described by giving data set of energy points e i and weights of the source particle w i by hand The number of source particles generated in each point is the same for all energy point but integrated values of the weight of source particles are adjusted to be proportional to w i You can also change the number of source particles generated in each point by specifing pCi For 19 case energy is given by wave length ne Number of energy points Data must be given from the next line by the format below In default p type 0 equal number of particle is generated at each point e i w i i 1 ne The number of source particles generated in each point is proportional to p i p type 0 1 D 0 generation option for 0 1 1 for all i is assumed without the following data for 1 p 1 must be given from the next line by the format as p i i 1 ne 43 Source section Table 4 43 parameters for source energy distribution 4 parameter explanation e type 2 12 Differential spectrum dy dE i is given by Gaussian distribution For 12 case energy is given by wave length A center of Gaussian dist
54. all isotopes of Pb If you want to specify multiple mother groups use multiple t yield tallies nucleus omissible You can specify output nuclei all all default same with no definition When you set number of nuclei define their nuclei in the next line Nucleus If you specify with mass Without mass all isotopes of Pb elastic 0 1 default Contribution of a recoil nucleus in elastic collisions 0 without this contribution 1 with this contribution unit 1 2 1 1 source 2 1 cm source ndata G default 1 If you set 1 nuclear production cross section data are used for nuclear irradiation in cases of proton induced reactions on a N O targets as shown below 150 The following nuclear reactions are included in the available nuclear data for ndata 1 He n xH x 4C 160 x c 60 n x O 160 p x c xPH 160 c He p xyH o 160 p nic x Be 160 n xH 160 n HPC 1606 xyH 16 x BN x Be 160 x Be 160 n x BN x Be 6Q p x Be 160 o 6 TALLY INPUT FORMAT xc 160 Be 6Q n x N x c 6Q p x Be 160 p MN x C I6O n x 0C 160 n o Table 6 14 t yield parameter 2 name value explanation axis reg X y Z x axis for output Xy
55. charge number of the particle MTYP baryon number of the particle RTYP rest mass of the particle MeV OLDWT weight of the particle at x y z a QS This data is written only for ITYP 12 13 namely electron and positron QS is dE dx for electrons QS dE dx of electron at x y z 42 Parameters section 41 4 1 1 71 IBLZ2 ILEV1 ILEV2 These mean IBLZ1 cellidat x y z IBLZ2 cellid after crossing ILEV1 level structure id of the cell at x y z ILEV2 level structure id of the cell after crossing a ILATI This is a variable of level structure of cell The next data are written only for ILEV1 gt 0 as write io C ILAT1 i j i 1 5 j 1 ILEV1 b ILAT2 This is a variable of level structure of cell The next data are written only for ILEV2 gt 0 as write io C ILAT2 i j i 1 5 j 1 ILEV2 5 COSTH UANG 1 UANG UANG 3 These variables mean as follows These had come to be output from ver 2 30 COSTH cosine of an angle of incidence in a surface crossing UANG 1 2 3 x y z component of a normal vector of its surface respectively NSURF internal number of the surface Note that this is different from the surface number defined in the surface section 6 NAME NCNT 1 NCNT 2 NCNT 3 These mean NAMEB collision number of the particle NCNT 1 2 3 values of counter 1 2 and 3 7 WT U V W These mean WT weight of the particle at xc yc zc U V W unit vector o
56. color If no definition the default values are used You can use the format 4 7 4 7 9 10 format can not be used If you need to use blanks in name definition the name must be closed by as the example If you want to use you should write VC In the name you cannot use The maximum number of characters of a name that you can define is 30 The color definition is based on the format in ANGzL Set color by symbol bbb yy name orange blue or HSB numeric H hue S chroma B brightness In the case HSB numeric definition close each numeric by If only one HSB numeric is defined chroma and brightness are set 1 Color symbols names and HSB numerics are shown from next page 110 4 SECTIONS FORMAT Table 4 56 gray scale Table 4 58 Color definition by names and HSB numerics Symbol HSB Output Name Naame Output HSB W 1 0 white darkred 1 000 1 000 0 600 0 0 8 lightgray red m 1 000 1 000 1 000 K 0 6 gray pink E 1 00 0 500 1 000 J 0 4 darkgray pastelpink 0 900 0 500 1 000 F 0 2 matblack orange 0 933 1 000 1 000 E 0 0 m black brown 0 900 1 000 0 500 darkbrown Fo 0 900 1 000 0 300 pastelbrown 0 900 0 600 0 500 orangeyellow S 0 867 1 000 1 000 Table 4 57 Color definition by symbols camel E 0 800 0 700 0 700 mm HSB Output NE pastelyellow 0 800 0 700 1 000 R 1 000 T yellow 0 800 1 000 1 000 RR
57. distribution and angular distribution described by analytic functions The list of third multi source is shown below List 4 2 Example of multi source 1 2 totfact 3 source 4 s type 5 proj 6 20 7 z1 8 9 1 19 dir 11 e type 12 1 13 2 14 nm 15 set 16 f x 17 source 18 s type 19 proj 20 21 22 23 dir 24 e type 25 1 26 27 nm 28 set 29 set 30 f x 31 lt source gt 32 s type 33 proj 34 20 35 21 36 37 38 1 39 2 40 41 42 set 43 f x 44 dir 45 a type 46 1 47 48 nn 49 g x 20 21 eg2 r8 ag2 Source 3 9 72 4 proton 2 29 5 1 e 6 1 3 200 c18 1 e 4 x 1 5 exp x c18 e 4 photon 1 2 5 1 5 1 3 5 1 200 c18 1 e 1 c20 1 e 1 2 35482 exp x c10 2 2 c20 2 za 4 neutron 29 30 5 6 1 2 1 3 200 c10 92 469 20 5 644 10 c10 c20 exp sqrt x x41876 c18 938 sqrt x 1876 data 5 0 1 200 exp x 1 2 0 3 2 68 4 SECTIONS FORMAT In this example there are three source subsections started from lt source gt In the first source subsection we define a cylinder source from z 2cm to z 29cm with 5cm radius and we set r1 4 This r1 4 means that the region inside the cylinder
58. energy distribution x y plane s type 17 reading dump file s type 18 cone s type 19 cone with energy distribution s type 100 user definition source edit the usrsors f and compile the PxiTs 46 4 SECTIONS FORMAT 4 3 1 Source Multi source By this multi source function one can define plural sources specified by s type Each source begins source number which defines the relative weight of the multi sources By totfact a global normalization is de fined Note that you should not write source in the next line of the line where reg parameter was written Table 4 23 multi source parameter explanation source defines a multi source the relative weight is defined by this number totfact D 1 global normalization factor If this is given by a positive number the source particle is generated according to this ratio If negative the same particle is generated in each multi source section changing the weight according to the ratio iscorr D 0 Multi source correlation option 0 Normal multi source 1 Correlated multi source In this case sources from each multi source group are generated as an event This option is useful for estimating detector response by nuclear reactions producing several secondary particles Note that the locations of all sources generated in an event are not the same unlike in the case of 1scorr 2 3 2 Correlated multi source In this case the locations
59. execution on Mac Installation Double click phits_installer included in the Mac folder of the DVD or USB flash drive and specify an installation folder for 175 Then phits folder which includes all contents of PuiTs such as executable files source code documents for lecture and sample input files of P iTs is created in the specified folder Note 1 You cannot change the folder name after installation If you want to change the name you have to install again Note 2 In the case that the phits folder already exists in the specified installation folder it would be renamed phits today s date current time Execution You can execute 175 by drag and drop an input file onto a blue icon of PuiTS on Dock Results of PuHiTS are created in the folder containing the input file If you want to execute 175 in the memory shared parallel mode you have to change the setup file of PHiTs on Dock according to the following procedure 1 Right click the icon on Dock 2 Select option Finder A folder phits office phits bin will be displayed 3 Right click the icon in bin folder 4 Select display contents of package 5 Open a file Contents document wflow by a text editor 6 Comment out a line around the 63rd line where the executable file for the single core is specified as follows phitsexe Users phits office phits bin phits273 mac exe 7 Rew
60. for writing options By default they have zero value If you give value 1 output files are given IP numbers as wk j9999 temp ncut dat 005 where 005 is the IP numbers If you give 3 into inpara igpara and ippara the default file path wk j9999 is not added 3 puts IP number at the end of file as same as 1 11 1 5 Read in file definition in the PHITS Read in files for are the Decay Turtle source file It gives only small effect to network traffic But this is sometimes 100MB size and is read in every events It gives a large effect to network traffic So you should copy the Decay Turtle data file and put them in each PE as wk j9999 turtle sours dat and define as file wk j9999 turtle sours dat in the PuiTS input 11 2 Shared memory parallel computing 11 2 1 Execution The Pa Ts calculation using the shared memory parallel computing can be executed by the following command phits lin exe phits inp where phits_lin exe indicates the executable file compiled with OpenMP option and phits inp does the PuiTs input file You can use any name for the input file namely the restriction of the PxiTs input file name to phits in is not valid in this case To specify the number of cores for the parallel computing an environment variable _ NUM THREADS should be defined It should be noted that this variable should be set to the real number of CPU cores not the number of t
61. has to be connected with atomic number by the character for indicating an isotope Important notices for using t dchain e Only one t dchain tally per PuiTs input file is allowed e The following parameters must be defined in the Parameters section jmout 1 display the atomic number density of materials file 21 set the place of the data folder for DCHAIN SP e You have to define the volume of each tally region in the Volume section Files generated by t dchain are listed below e Basic input file of DCHAIN SP file name is set in t dchain tally 174 6 TALLY INPUT FORMAT e Neutron energy spectrum with 1968 group energy structure below 20 MeV calculated by created t track n flux When more than two regions are set each file name is 01 n flux 02 f flux e Nuclear production yields calculated by created t yield nmtc _yield e Information about the link to the folder having DCHAIN SP data library dch_link dat e Files for restart calculation of PaiTs dtrk dyld err dyld dout 6 14 T Userdefined section 175 6 14 T Userdefined section This tally is used for estimating and outputting the physical quantities that cannot be calculated by the other tallies In order to use this tally you have to change usrtally f and re compile PriTS by yourself When T Userdefined is defined in your input file PuiTS calls subroutine usrtally
62. independent This generic parabola distribution is consist of independent parabola in each x y z direction Parameters for generic parabola source are shown below The order of parameters is free If a parameter has a default value D the parameter can be omissible Table 4 28 parameters for generic parabola distribution s type 7 8 generic parabola source D 0 0 x coordinate of X parabola center cm xl X parabola width cm y8 D 0 0 y coordinate of Y parabola center cm yl Y parabola width cm 20 minimum z of parabola 21 maximum z of parabola cm rn D 2 order of generic parabola dir direction cosine from z axis If you set all isotropic If you set data a type subsection is necessary phi Dznone random azimuthal angle degree dom D 0 0 solid angle degree 1 cos bias distribution projectile energy s type 7 MeV 43 Source section 51 4 3 7 Gaussian distribution source x y plane This source is a Gaussian distribution in x y plane Parameters for Gaussian source are shown below The order of parameters is free If a parameter has a default value D the parameter can be omissible Table 4 29 parameters for Gaussian source s type 13 16 Gaussian source x9 D 0 0 x coordinate of Gaussian center cm y8 D 0 0 y coordinate of Gaussian center cm ri FWHM in x y plane cm 20 minimum z coordinate cm 21
63. into ctmin i omissible D 9999 minimum value for i th counter ctmax i omissible D 9999 maximum value for i th counter trcl omissible coordinate transformation number or definition for r z or xyz mesh gslat 1 default 0 1 show lattice boundary in gshow 0 no 136 6 TALLY INPUT FORMAT Using multiplier option in this tally you can multiply results of the t track tally by factors depending on energies of particles If you define a data set in multiplier section any factors can be used The basic formatis given as C where is a normalization factor and k is the ID number of the set It is noted that k should be negative Format of the multiplier subsection is given as follows multiplier number of material part neutron emax 1000 mat 1 mset2 1 C1 201 C 2 202 2 1 2 201 202 The line of multiplier specifies the number of material where the multiplication is considered You can use all instead of the number For this case one should also use all for mat column below The second line of part defines the particles considered The maximum number of the particle is 6 and all can be also used which is default The multiplication affects only these considered particles The third line of emax defines the maximum energy of the multiplication If emax is omitted it is automatically defined as the maximum energy given in the multiplier
64. iron box including water its inside When you specify any cell using mesh reg in tally sections you can use the lattice and universe styles as 401 lt 101 0 8 0 lt 1 where the lattice coordinate is represented by s t u See also Sec 5 1 2 for this format It is noted that you cannot use formats as 301 101 2 2 2 2 2 2 1 because not all the 101 2 2 2 2 2 2 cell have the 301st cell Figure 4 23 Results of the cell section example 11 in 3D images The structure in the right panel is removed its iron surface from the original one in the left panel 45 Cell section 89 For time shortening you can use ivoxel in the parameters section When you perform calculation with ivoxel 2 voxel data are output in file 18 in binary and then the calculation is stopped From the next calculation with ivoxel 1 a process of the data output is omitted and the calculation time is shortened If you use a very huge voxel data using infl may become to be convenient 90 4 SECTIONS FORMAT 46 Surface section 4 6 1 Formats Surface is defined in this section Only C and can be used as a comment mark but can not be used as a comment mark here The file including and variable definition can be set in this section If you want to use continuation lines it is enough to put more than 4 blanks at the line head instead of the line sequential mark at the end of line The order of format is surface number coordinate transfo
65. itall 1 setting the eps file is created after every batch calculation You can monitor the results in real time by displaying the eps file with the ghostview and by setting refresh function for a file updating by typing w key on the ghostview 5 7 17 counter definition You can make a gate to the tallying quantities by using the counter defined by counter section Set mini mum ctmin i and maximum value ctmax i for each counter The i is the counter number from 1 to 3 By default ctmin i 9999 ctmax i 9999 When multiple counters are specified the common part of these terms are tallied 5 7 18 resolution and line thickness definitions You can increase the resolution of the region boundaries in the gshow rshow and 3dshow with keeping xyz mesh by resol Default value is 1 it is same as xyz mesh resolution If you set resol 2 the resolution becomes 2 times for each side It is useful to draw smooth line for xyz mesh Also you can obtain clear graphics by set resol larger for the 3dshow Even if you set resol larger memory usage is not changed The width shows the line thickness for gshow rshow and 3dshow Default value is 0 5 5 7 19 trcl coordinate transformation By this trcl option you can transform the coordinate of the r z and xyz mesh There are two ways to define the transformation as below trcl number trcl B B Bs Bs Bg B Bg Bo M 130
66. omitted real material is assumed If you select the material that is not used in your geometry you have to define its material density in material section If you would like to calculate LET in water you have to define water with 1 g cm in material sectiont When you set letmat 0 PHITS automatically calculates dE dx for water with 1 g cm for electrons and positrons Please see particletherapy in the recommendation setting in more detail dedxfnc omissible D 0 0 without 1 use usrdfn1 f 2 use usrdfn2 f As examples the default program of usrdfn1 f returns the dose equivalent calculated from deposit energy multiplied with the Q L relationship defined in the ICRP60 while that of usrdfn2 f simply does the energy loss without multiplying any factor e type 1 2 3 4 5 energy mesh You need energy mesh subsection below this option t type 1 2 3 4 5 time mesh omissible You need time mesh subsection below this option output dose score the energy loss of charged particles and nuclei deposit score deposit energy distribution You need e type subsection 6 4 T Deposit section 145 Table 6 9 t deposit parameter 2 name value explanation unit 0 1 2 3 4 0 Dose Gy source only for output dose 1 Dose MeV cm source 2 Dose MeV source 3 Number 1 source only for output deposit 4 Number 1 nsec source only for output deposit axi
67. on the basis of universe frame in Sec For example the universe 1 is filled with the universe 2 and the universe 2 is filled with the universe 3 Moreover the 3rd can be also filled with another universe Then you can define the nesting structure The maximum number of the nesting level is 10 which corresponds to a parameter mx1v given in file param inc In the next example there are nine square poles defined with LAT 1 and three of these have a different structure from the others List 4 16 ce11 section example 9 1 Material 24 mat 1 1H 2 160 1 3 mat 2 Fe 1 4 cell 5 1 0 11 12 13 14 15 16 FILL 1 6 101 0 26 25 22 21 LAT 1 U 1 7 FILL 1 1 1 1 0 0 8 223 232 322 9 201 1 1 0 90 U 2 10 301 2 10 0 18 U 3 11 302 0 18 U 3 12 2 1 1 13 Surface 14 19 CY 1 5 15 11 PX 6 16 12 PX 6 17 13 PY 6 18 14 PY 6 19 15 PZ 6 20 16 PZ 6 21 21 PX 2 22 22 PX 2 23 25 PZ 2 24 26 PZ 2 25 98 BOX 10 10 10 2000 0200 00 20 Definition of the Ist cell and the unit of lattice in the 5th and 6th lines respectively is the same of that in the cell section example 6 However a format of the cell parameter FILL written in the 7th and 8th lines is different In the 7th line regions treated in this calculation are given in the lattice coordinate system The numbers in the next line correspond to the universe number filling each lattice at s f where the order is
68. real material is assumed If you select the material that is not used in your geometry you have to define its material density in material section If you would like to calculate LET in water you have to define water with 1 g cm in material sectiont When you set letmat 0 PHITS automatically calculates dE dx for water with 1 g cm for electrons and positrons Please see particletherapy in the recommendation setting in more detail dedxfncl omissible D 0 for region r1 0 without 1 use usrdfn1 f 2 use usrdfn2 f dedxfnc2 omissible D 0 for region 12 0 without 1 use usrdfn1 f 2 use usrdfn2 f As examples the default program of usrdfn1 f returns the dose equivalent calculated from deposit energy multiplied with the Q L relationship defined in the ICRP60 while that of usrdfn2 f simply does the energy loss without multiplying any factor el type 1 2 3 4 5 energy mesh for region rl You need energy mesh subsection below this option e2 type 1 2 3 4 5 energy mesh for region r2 You need energy mesh subsection below this option t type 1 2 3 4 5 time mesh omissible You need time mesh subsection below this option unit 1 2 1 Number 1 source 2 Number 1 nsec source axis engl eng2 t x axis value of output data 12 e21 t el t e2 2 dimensional el t e2 t file file name Define file names as same number of axis resfile omissible D file Define a file name of the past tally in the
69. reg region mesh 24 reg 100 lt cell number 3 file testDC spd file name of DCHAIN SP input 4 title t dchain test calc 5 amp 1 8E12 source power source sec 6 7 timeevo 4 number of irradiation and cooling steps 8 3 8 h 1 0 irradiation for 3 hours 9 2 0h 0 0 lt cooling for 2 hours 10 3 5 h 1 0 lt irradiation for 3 5 hours 11 15 5h 0 0 cooling for 15 5 hours 12 13 outtime 3 number of output timing 14 3 0 h lt 3 hours later from the 1st irradiation start time 15 1 0 h lt 1 hour later from the end of the last irradiation step 16 3 0 h lt 3 hour later from the end of the last irradiation step Calculation steps for irradiation and cooling time timeevo start Last irradiation time 3h 1h 3h Output times of calculation results outtime amp Not allowed to set Figure 6 5 Relation between steps for irradiation and cooling time and output time List 6 2 Example for the setting of target material compositions and volumes for target 1 target 1 target material composition ON non reg vol omissible 1 1 8000 0 lt serial number cell number volume tg list 2 lt number of the nuclides H 1 6 689E 02 lt Element ID Atomic Number 0 16 3 345E 02 and Density of the atom 10 24 3 2 2 2000 0 lt serial number cell number volume tg list 1 lt Number of the nuclides Fe 56 8 385E 02 The symbol of the chemical element
70. region except outer void to control the production of rays As the secondary particle rays with energies above E are explicitly generated and transported For lower energies than the deposition energies from 6 rays are included in LET A minimum energy of Em you set is 0 001 MeV IkeV It is noted that in case of very low En or setting of a material thiner than 10ug cm a behavior of the charged particle slightly changes This is because the effective stopping power of the charged particles becomes smaller than its real value due to too many delta ray productions A default value of Em is l e 10 i e rays are not produced in the PuiTs calculation except for setting the Em parameter in this section The region number and Ep are given by reg and del respectively Set these parameters as follows delta ray reg del 1 0 1 11 1 0 You can use the format 2 5 8 9 But you need to close a value by C if it is not a single numeric value You cannot use the lattice and universe style as 6 lt 10 1 8 0 lt u 3 If you want to replace the order of region number reg and the threshold energy del set as del reg You can use the skip operator non Even if you use GG use the symbol not 11 but reg here 116 4 SECTIONS FORMAT 4 25 Multiplier section In this section you can define a multiplier set which consists of factors depending on energies of particles to multiply r
71. respectively leakage Kinetic energy of particles going out to the outer region And total Total deposit energy recoil Kinetic energy of residual nuclei when you set cut off energy emin 15 19 ionization Deposit energy by energy loss of charged particles low neutron Deposit energy calculated by neutron Kerma factors photon Deposit energy by Kerma factors If electron 1 contributions of electrons below cut off energy others Excitation energy of residual nuclei When you set igamma 1 this value comes to be 0 owing to photon emission Neutrons photons and protons below cut off energy are not tallied in the ncut gcut and pcut component but in the stopped particle if incut 0 igcut 0 and ipcut 0 in the parameter section When gt 0 igcut gt 9 ipcut gt 9 they are tallied in the ncut gcut pcut part 142 6 TALLY INPUT FORMAT Table 6 6 t heat parameter 2 name value explanation output all In addition to above continued Contributions of d t He a and residual nuclei to recoil Contributions of and the others to ionization Contributions of particles specified by part are output However they are not plotted in eps file stopped particle Kinetic energy of stopped proton neutron n n and the other particles in materials Contributions of particles specified by part are output However they are not plotted in eps file others Remaining excita
72. section or dmax i i 1 2 or 14 when you use nuclear data library The number of mat column is the material number which is considered to be multiplied The columns of mset1 mset2 define the multiplier set The maximum 6 multiplier can be set For each set the result is printed out You can define several multiplier subsections in one t track section but you should set the number of the multiplier sets to be equal in each subsection Some parameter sets built in PHiTS can be used If you set k 1 a value of 1 weight is used as the multi plication factor For k 2 a value of 1 velocity is used For k 120 material density is used Therefore you can obtain mass in the region setting icnt1 5 With k 101 102 112 or 114 the conversion factor of pro ton neutron electron or photon respectively is used These conversion factors were estimated with a condition of Antero Posterior geometry AP irradiation The unit of the dose conversion factors is uSv h n sec cm It should be noted that the interpolation method of conversion factor has been changed in PuiTs ver 2 00 from linear linear to log log You can also use the following format like FM card of MCNP multiplier number of material part proton emax 150 mat mset1 mset2 1 C 0 1236 1 1 4 C 0 0 2 0 0060 2 1 4 0 0 3 C 0 0032 3 1 4 0 0 multiplier number of material part neutron emax 150 mat mset1 mset2 0 1236 11
73. set If you skip maximum energy set the maximum energy of the library is defined The mat is the material number for library use the fac is a normalization factor the 1ib is material number which contains the library and the mt is DPA record number in the library In the library made by Dr Harada mt 445 for proton mt 444 for neutron The fac and mt are omissible If you skip the mt definition 444 is used Material number defined by the lib should be defined in the material section The y type data are assumed for library data reading as shown below m41 4009 12 1 m42 13027 12 1 m43 26054 12y 3 3066d 04 26056 12y 5 2290d 02 26057 12y 1 2542d 83 26058 12y 1 5963d 04 You can change the order mat fac lib mt like mat lib mt fac You can use the skip operation non 69 T LET section 69 T LET section By the LET tally you can get the information on track length and dose as a function of LET dE dx of a certain material This tally counts an energy loss of charged particles and nuclei and thus you must use the Event Generator mode e mode 1 if you would like to transport low energy neutrons Note that this tally does not consider the contribution of the electron and positron below their cutoff energy emin to the result Table 6 23 t let parameters 1 next line number of materials 25 8 name value explanation mesh reg r z xyz geometry mesh you need geometry mesh subsection below
74. simulate reaction processes attributed to induced neutrons below 20 MeV because of com plex resonance structures Therefore nuclear data libraries are very useful for the simulation To utilize the data library emin 2 and dmax 2 in the parameters section have to be set appropriately e g emin 2 1 0e 10 and dmax 2 20 0 01 2 How can we simulate motion of photons electrons and positrons 1 2 As the default setting of 175 photons electrons and positrons are immediately cutoff when they are cre ated In order to transport these particles you have to obtain their atomic data libraries such as jphlib01 and jellib01 These libraries are included in the 175 package from version 2 52 In addition you have to set emin 12 14 and dmax 12 14 in the Parameters section The typical minimum and maximum values of these parameters are 1 0e 3 and 1 0e3 for 12 14 and 12 14 respectively although dmax 14 can be extended up to 1 0e5 However if you set emin 12 and emin 13 to 1 0e 3 computa tional time becomes very long Thus the recommended emin 12 and emin 13 in most cases are 1 0e 1 Please see recommendation in more detail 01 3 What is the setting of nuclear reaction models giving the most accurate result A1 3 In general the default models give the best results in most cases from version 2 50 It should be noted that you have to use nuclear data library to simulate neutrons below 20 MeV see
75. state used 1 appropriate for material in the gaseous state used ESTEP n make sub step number n for electron transport it is ignored when n is smaller than built in default value NLIB id change default neutron library number id PLIB id change default photon library number id ELIB id change default electron library number id HLIB id change default proton library number id COND conductor settings lt 0 non conductor 0 Default non conductor if there exist at least 1 non conductor otherwise conductor gt 0 conductor if there exist at least 1 conductor 4 4 5 S a p settings In the transport of low energy neutrons S o B library may be required This library can be set as follows materialID where m is the material number and materialID is ID number written in xsdir such as lwtr 20t See XS ts1 tsl table for detailed information for these data 76 4 4 6 Examples Some examples are shown below 4 SECTIONS FORMAT List 4 5 material example 1 MAT 1 1H 208Pb 204Pb 206Pb 207Pb MAT 2 1H 14N 160 gt Uu n H A oH Material 1 0000000E 04 1 7238000E 02 4 6801000E 04 7 9430000E 03 7 2838000E 03 1 0000000E 09 4 6801000E 05 7 9430000E 06 By default the order is nuclide then density You can specify them in reverse by putting the den and as List 4 6 material example 2 1
76. the end of last irradiation step The format for specifying the timing is the same as that for timeevo except for this positive and negative rule You cannot specify timing after all steps defined in timeevo is finished If you would like to output the timming when no radioactive nuclide exists e g 0 0 m you have to set iprtb2 0 in the t dchain section amp omissible D 1 0 Power of source source second target 0 1 omissible D 0 OFF 0 need not to write information of target Information of target is automatically determined from Material Ce11 and Volume sections ON 1 need to write information of target f you want to add nuclides that are not defined in Material section in the DCHAIN SP calculation and or you do not set the volume in Volume section you should write target 1 and give the related information in List 6 2 See the example of target subsection for target 1 in List 6 2 In addition to these parameters you can also specify the DCHAIN SP parameters in t dchain section The specifiable parameters are imode jmode idivs iregon inmtcf ichain itdecs itdecn isomtr ifisyd ifisye iyild iggrp ibetap acmin istabl igsdef iprtb1 iprtb2 rprtb2 iprtb3 igsorg ebeam prodnp The meanings of these parameters are given in the manual of DCHAIN SP 613 T Dchain section 173 List 6 1 Example of input for t dchain tally 1t mesh
77. time to calculate See Sec 4 2 21 for event generator mode At this moment a part of event generator mode Ver 2 in the OpenMP version of PHITS is not available 99285 Aa 1 elog 9 X Xo Eq 4 in G R Lynch and Dahl Nucl Instrum Methods Phys Res B 58 6 10 1991 28 4 SECTIONS FORMAT 4 2 8 Model option 4 Table 4 9 parameter 8 parameter value explanation usrmgt D 1 option for user subroutine of time dependent magnetic field 1 usrmgtl f is used which includes Wobbler magnet 2 usrmgt2 f is used which includes Pulse magnet usrelst D 1 option for elastic option 1 usrelst1 f is used which is for Bragg scattering 2 usrelst2 f is used which is a sample program 4 2 9 Output options 1 Table 4 10 parameter 9 parameter value explanation infout D 7 Option to specify output information in file 6 See notes under this table for the following numbers I LII I HII LIV I II III L IL IV I IL IV I II IIL IV VI I II II IV V VI nrecover D 0 Number of output of warning messages when the recovery of lost particles succeeds I Parameter infout controls output information in the summary file file 6 The information is divided into the following 6 categories You can select the output information infout I Basic information LOGO except for PHITS developers calc
78. to center coordinate of top face R radius vl v2 v3 base point coordinate RHP optional hexangular prism hl h2 h3 height vector from base point or prism rlr2r3 vector from base point to first surface HEX sl s2 53 vector from base point to second surface tl 12 13 vector from base point to third surface REC right elliptical cylinder V V V center coordinate of bottom face Hy vector from Vy V V to center coordinate of top face Vix Vi Viz major axis vector of ellipse orthogonal to H Vax Vo Vz minor axis vector of ellipse orthogonal to H and V TRC truncated right angle cone V V V center coordinate of bottom face of cone H H height vector from V V V Ri radius of bottom face Ro radius of top face ELL ellipsoid If Rm gt 0 Vix Viy Viz coordinate of the first focus Vax Vo Vz coordinate of the second focus Rm major axis length If Rm lt 0 Vix Viy Viz center coordinate of ellipsoid Vax Vo Vz major axis vector Rm minor axis length WED wedge V V V coordinate of the top Vix Vi Viz vector to the first triangle face Vox Voy Vz vector to the second triangle face V3 height vector You cannot set R to 0 in definition of TRC If you want to define a usual cone i e not truncated cone using TRC you should set to a small value 46 Surface section 4 6 4 Examples 93 List 4 20 surface section example 2 corresponding the ce11 section example 2 1 surface 2
79. to n of that file in If there is no 1 PxiTs includes all lines of the specified file You can use following style to specify line numbers m m From line number n to the end and from top to line number respectively The file insertion can be nested more than once The including file can be nested more than once When you use the command line interpreter Command prompt on the Windows system for executing PuiTS you have to be careful If inflis used you should write the following text in the first line of the input file file input dat Here input dat is the input file name See section 2 7 3 4 User definition constant You can set your own constant as set 1 52 3 c2 2 pi c3 cl 8 This set definition can be written in anywhere Defined user constants be used as numerical values in your input file User constants can be re defined any time and these values are kept until re defined In the 3rd case of above example c3 another user constant c1 is called in a user constant definition In the case the value in which the user constant c1 keeps at that time is used So even if you re define the c1 below the c3 definition the value of c3 defined here is not changed pi is set to the value of z by default 3 5 Using mathematical expressions Mathematical expressions can be used in your input file It is ForTRAN style Available functions are shown in Table For exa
80. transformation number or definition for r z or xyz mesh gslat 1 default 0 1 show lattice boundary in gshow 0 no ginfo 2 default Region error check 0 No geometry check 1 Check geometry and draw its two dimensional view with error information 2 Check geometry draw its two dimensional view and outputting a geometry error file err 180 6 TALLY INPUT FORMAT output 7 8 can be used only when cells in bottom level are the lattice themselves and they give lattice number in the format as 4 1 2 For example Fig in Sec 4 5 4 is generated by the input shown below List 6 4 t gshow example 1 T gshow 25 mesh xyz 3 x type 2 4 nx 100 5 xmin 10 6 xmax 10 Ti y type 1 8 ny 1 9 5 0 5 0 10 z type 2 11 nz 100 12 zmin 10 13 zmax 10 14 axis xz 15 output 8 16 file cell example6 dat 17 epsout 1 616 T Rshow section 616 T Rshow section T Rshow gives graphical geometry output for region boundary with color plot region in proportion to physical quantity of the region Usually the results obtained by other 175 calculation using the reg mesh are used as the input data for this value of physical quantity You must run with icntl 9 option in the parameters section in order to execute this tally You can give color variation by the linear scale or the log scale by the ANGgL parameter zlog or zlin Default Is z
81. two sheets as the center being the coordinate of the top along the direction of each axis If you set to be 1 for 1 the upper sheet is used and the lower sheet is used in the case of 1 When the value is not given both sheets are used It should be noted that you have to use a plane passing the top when you define a region in 11 section using only one side of the cones you have to use three surface a plane passing the top a side sheet of the cone and an underside of the cone in the definition You can define a plane by setting x y z coordinates of 3 points In this case a region including the origin is of negative sense When you use TX TY TZ to define ellipse torus or torus you cannot transform their coordinates by setting transform section 92 4 SECTIONS FORMAT 4 6 5 Macro body Table 4 53 macro body card symbol type numerical input explanation V V base point coordinate BOX optional BOX Alx Aly Alz vector from base point to first surface all angles are 90 A2x A2y A2z vector from base point to first surface A3x A3y A3z vector from base point to third surface RPP rectangular solid minimum and maximum each surface is vertical with xyz Yu Ynax minimum y and maximum y Z nin Lmax minimum z and maximum z SPH sphere V V V center coordinate same with general sphere S R radius V V V center coordinate of bottom face RCC cylinder H vector from V V V
82. values of counters and sx sy sz are the unit vectors of the direction of spin respectively name is a collision number of the particle nocas is a current history number of this batch nobch is a current batch number no is a cascade id in this history These are assumed as real 8 for the binary data 1 1 24 15 data format for the ascii data For an example one record has 9 data as kf e wt x y z v To read this data we write the parameters as dump 9 18923456 7 43 Source section 57 4 3 14 User definition source If you edit usrsors f you can use your original source function by s type 100 If the following parameters are set these values have the priority If a parameter has a default value D the parameter can be omissible Table 4 39 the parameters can be specified in s type 100 s type 100 user definition source If below parameters are specified these values have priority over the user defined data x9 minimum x coordinate cm xl maximum x coordinate cm minimum y coordinate cm yl maximum y coordinate cm 20 minimum z coordinate cm 21 maximum z coordinate cm SX D 0 x component of spin sy D 0 y component of spin SZ D 0 z component of spin dir direction cosine from z axis If you set all isotropic If you set data a type subsection is necessary phi Dznone random azimuthal angle degree dom D 0 0 solid angle degree 1 cos bi
83. you should set de1t6 to be 1 10 of its thickness deltg Dz1 0 A maximum of flight mesh cm on the magnetic field deltt D 1 0 A maximum of flight time msec on the time dependent magnetic field 42 Parameters section 35 4 2 15 Input output file name Table 4 16 parameter 15 parameter value explanation file 2 D cgview in CGVIEW input file name when icnt1l 2 file 3 D cgview set CGVIEW setup file name when icntl 2 This file becomes CGVIEW setup file 4 D marspf in MARS PF input file name when icntl 4 file 6 D phits out Summary output file name If not specified standard output file 7 D c phits data xsdir jnd cross section directory file name file 11 D nuclcal out nuclear reaction output file name file 12 D fort 12 cut off neutron output file name file 13 D fort 13 cut off y ray output file name file 18 D fort 10 cut off proton output file name file 15 D dumpall dat dump file name for dumpall 1 option file 18 D voxel bin file name when you use ivoxel 1 2 file 28 D c phits XS egs Directory containing the library data for EGS5 file 21 D c phits dchain sp data Directory containing the library data for DCHAIN SP file 7 must be written with full pathname From ver 2 74 file 14 parameter is not necessary to be specified in PHITS input file even setting igamma gt 1 4 2 16 Others Table 4 17 parameter 16 paramete
84. z axes and scale of the space in any universe agree with those in the other universe If the different value is used for PX in the 14th 15th lines the cube does not include a part of the cylinder as shown in Fig 10 7 I T T TTT T TTT T TTT E 5L 102 202 F 7 void 101 4 5 0r 4 water L iron st 10 Cepeda dEaa ra 10 5 0 5 10 2 Figure 4 16 Result of cell section example 5 except that the region is shifted in the x direction 4 5 4 Lattice definition For making repeated structures a cell parameter LAT lattice parameter is very useful In this section definition of a unit structure of the lattice and its simple usage are explained showing some examples See Sec 4 5 5 for more practical description Quadratic prism and hexangular prism shown in Fig 4 17 can be used as a unit structure by LAT 1 and LAT 2 respectively You make one universe having the repeated structure of the lattice Then you fill any region with the universe It is noted that the each unit must also be filled with another universe which is defined with any 45 Cell section 83 material or void The numbering each component of the units in Fig corresponds to the order of the surface number written in the cell definition and the lattice coordinate system which will be explained below depends on the order 3 2 LAT 1 1 4 Figure 4 17 Unit structure of lattice An e
85. 0 02 1 6 tr2 0 0000000E 00 0 0000000 00 2 5800000E 03 Fs 3 0000000 02 9 0000000E 01 2 1000000E 02 8 9 0000000E 01 0 0000000 00 9 0000000E 01 9 3 0000000 01 9 0000000E 01 3 0000000E 02 1 In this example tr1 rotates the coordinate by 135 degrees around y axis and transports 140 cm to z direction while tr2 rotates 300 degrees around y axis and transports 258 cm to z direction Because of TRn with you can give angles in units of degree directly for B i 1 9 4 7 4 Examples 2 List 4 22 transform section example 2 1 Transform 2 set c10 90 angle of around Z degree 3 set c20 30 angle of around Y degree 4 set c30 0 angle of around X degree 5 6 tri 000 7 cos c10 180 pi cos c20 180 pi 8 sin c10 180 pi cos c30 180 pi cos c10 180 pi sin c20 180 pi sin c30 180 pi 9 sin c10 180 pi sin c30 180 pi cos c10 180 pi sin c20 180 pi cos c30 180 pi 10 sin c10 180 pi cos c20 180 pi 11 cos c10 180 pi cos c30 180 pi sin c10 180 pi sin c20 180 pi sin c30 180 pi 12 cos c10 180 pi sin c30 180 pi sin c10 180 pi sin c20 180 pi cos c30 180 pi 13 sin c20 180 pi 14 cos c20 180 pi sin c30 180 pi 15 cos c20 180 pi cos c30 180 pi 16 1 In this example tr1 rotates the coordinate by c10 degree around z axis c20 degree around y axis and finally c30 degree around x axis You can set c10 c20 c30 and rotate the coodinate to any di
86. 0 933 ose pastelgreen 0 700 0 600 1 000 RRR 0 867 _ yellowgreen 0 700 1 000 1 000 Y 0 800 EH yellow green 0 600 1 000 1 000 0 733 m _ darkgreen E 0 600 1 000 0 600 yyy 0 667 mm E mossgreen 0 500 1 000 0 300 0 600 green bluegreen ERI 0 500 1 000 1 000 GG 0 533 pastelcyan 0 400 0 400 1 000 GGG 0 467 pastelblue 0 250 0 400 1 000 C 0 400 ES cyan cyan 0 400 1 000 1 000 CC 0 333 cyanblue 0 400 1 000 0 500 CCC 0 267 Eq blue 0 200 1 000 1 000 0 200 um blue violet 0 133 1 000 1 000 0 133 violet purple m 0 100 1 000 0 500 BBB 0 067 um magenta magenta ES 0 067 1 000 1 000 winered al 0 002 0 800 0 700 pastelmagenta E 0 067 0 600 1 000 pastelpurple al 0 100 0 400 0 500 pastelviolet 0 133 0 400 1 000 4 20 Mat Time Change section 111 4 200 Mat Time Change section By this section you can change the material of certain cells to the other material as a function of time This function is useful to describe a shutter of beam line TO chopper and the other devices for neutron optics The unit of time is nsec Mat Time Change mat time change 1 50 0 11 2 100 9 12 3 1000 0 0 In the above example the material 1 is changed to material 11 at t 50 0 nsec 2 to 12 at 100 nsec and 3 to void at 1000 nsec If you want to replace the order of the initial material mat time time and the final material change set as mat change time
87. 000 mat mset1 mset2 1 C 1 201 C2 202 2 1 2 201 202 The line of multiplier specifies the number of material where the multiplication is considered You can use all instead of the number For this case one should also use 11 for mat column below The second line of part defines the particles considered The maximum number of the particle is 6 and all can be also used which is default The multiplication affects only these considered particles The third line of emax defines the maximum energy of the multiplication If emax is omitted it is automatically defined as the maximum energy given in the multiplier section The number of mat column is the material number which is considered to be multiplied The columns of mset1 mset2 define the multiplier set The maximum 6 multiplier can be set For each set the result is printed out You can define several multiplier subsections in one t track section but you should set the number of the multiplier sets to be equal in each subsection 117 5 Common parameters for tallies PuiTs has the following tally functions Table 5 1 Tally sections name explanation t track Track length tally definition t cross Surface crossing tally definition t heat Heat developing tally definition t deposit Deposit tally definition t deposit2 Deposit2 tally definition t yield Residual nuclei yield tally d
88. 013 814553 Other articles that describe the features of PHITS are e H Iwase T Nakamura Development of general purpose particle and heavy ion transport Monte Carlo code J Nucl Sci Technol 39 1142 1151 2002 e K Niita T Sato H Iwase H Nose H Nakashima and L Sihver Particle and Heavy Ion Transport Code System PHITS Radiat Meas 41 1080 1090 2006 e L Sihver D Mancusi T Sato K Niita H Iwase Y Iwamoto N Matsuda H Nakashima Y Sakamoto Recent developments and benchmarking of the PHITS code Adv Space Res 40 1320 1331 2007 e L Sihver T Sato K Gustafsson D Mancusi Iwase Niita Nakashima Y Sakamoto Y Iwamoto and N Matsuda An update about recent developments of the PHITS code Adv Space Res 45 892 899 2010 e K Niita N Matsuda Y Iwamoto H Iwase T Sato H Nakashima Y Sakamoto and L Sihver PHITS Particle and Heavy Ion Transport code System Version 2 23 JAEA Data Code 2010 022 2010 e K Niita H Iwase T Sato Y Iwamoto N Matsuda Y Sakamoto H Nakashima D Mancusi and L Sihver Recent developments of the PHITS code Prog Nucl Sci Technol 1 1 6 2011 2 Installation compilation and execution of PHITS The source code of PxiTs is written in FORTRAN and can be compiled and executed on various operating system such as Windows Mac and Linux For Windows and Mac the executable file compiled by Intel Fortran was included in the
89. 08Pb See Table B 4 for particle identification You can also use the kf code number If you define all particles as part all Maximum 6 particles can be define in a tally If you want to tally more particles use another tally sections of the same kind of tally If you want to tally some particles as a group you can use as the following The maximum number inside the is 6 part proton neutron all pion 3112 208Pb In this case as the first group the sum of proton and neutron contribution is tallied the second is the sum of all 5 groups of the particle are printed out in this tally For nucleus you can use the expression like 208Pb and Pb The later case Pb denotes all isotopes of Pb 5 7 2 axis definition X axis value for output is described here There are many kinds of axis shown as depend on kinds of tallies or geometrical meshes eng reg x y Z t Xy yz ZX rz cos the mass charge chart dchain let t eng eng t t el el t t e2 e2 t e12 e21 axis eng 5 7 Other tally definitions 125 You can set multiple axis per one tally by axis eng x y Or axis eng axis x axis y If you define multiple axes output results are written in different files So you need to specify multiple output files as shown in the next subsection when multiple axes are defined It should
90. 1 1 0 0 1 0 1 1 0 1 0 0 1 1 0 i e a lattice at 1 1 0 is filled with the universe 2 and that at 1 1 0 is filled with the universe 3 The universe 2 is defined in the 9th line as space filled with water On the other hand the universe 3 defined in the 10th and 11th lines has an iron cylinder at the origin The result of this example is shown in Fig One can see that three lattices at 1 1 0 0 0 0 and 1 1 0 have the iron cylinder When you specify any cell using mesh reg in tally sections you can use the lattice and universe styles as 302 lt 101 0 0 0 lt 1 where the lattice coordinate is represented by s t See also Sec 5 1 2 for this format 10 TTTTTTTTTTTTTTTTTTT 0 0 1 0 1 1 0 4 1 1 0 water OF 1 0 0 1 0 0 m void x 0 0 NEN iron Fo 6250 01 0 fa 5T 11 0 J 10 Cepeda tat 10 5 0 5 10 z cm Figure 4 21 Result of the cell section example 9 45 Cell section More complex example is shown below 87 List 4 17 ce11 section example 10 11 12 13 14 15 16 17 18 19 28 21 22 23 24 25 26 27 28 29 30 31 32 ES Material mat 1 1H 2 1601 mat 2 1 Cell 1 9 11 12 13 14 15 16 FILL 1 101 0 26 25 22 21 LAT 1 U 1 FILL 1 1 1 1 0 0 223 181 23001 2 30101 22
91. 1 treatment of different densities in same material in GG 0 same material number 1 using new material number Normally the tallies are called at the reaction point or at the surface crossing Thus the particle track in the magnetic field for an example is shown as a straight line between collisions or between one collision and surface crossing If you specify itstep 1 the trajectory is described correctly as a curve The maximum step for the magnetic field is set by deltm 32 4 2 12 Output option 4 4 SECTIONS FORMAT Table 4 13 parameter 12 parameter value explanation iggcm D 0 option of GG warnings 0 no echo 1 in input echo ivout D 0 volume display options in the input echo 0 in volume section ipout 1 importance display options in the input echo D 0 for GG 0 in importance section this function is only available when all particles are set for the same importance value icput D20 CPU time count options 0 without count 1 with count ipara D 0 parameter display options 0 only described parameters 1 all parameters nwsors D 0 write down the information on nwsors source particles on file 6 CPU time counting is not available by default for saving calculation time If you want to know CPU time for each process set icput 1 If you set ipara 1 you can confirm all parameters in the PxiTs code 42 Parameters section 33 4 2 13 Output option 5
92. 1 rpp 15 15 55 9 60 3 2 rpp 5 5 55 0 20 4 4 15 15 5 5 0 20 5 5 20 28 55 0 40 6 6 rpp 20 20 5 5 0 20 7 7 rpp 28 28 5 5 40 60 8 3 010 4 94 4 SECTIONS FORMAT 4 6 5 Surface definition by macro body ce 99 When you use a surface defined by a macro body in the cell definition means inside of the macro body and means outside of the macro body Each surface composing a macro body can be used in the cell definition In that case you should write macro body number with and surface number Surface number is shown below Table 4 54 surface number in macro body symbol surface number explanation surface vertical with the end of Alx Aly Alz surface vertical with the origin of Alx Aly Alz surface vertical with the end of A2x A2y A2z surface vertical with the origin of A2x A2y A2z surface vertical with the end of A3x A3y A3z surface vertical with the origin of A3x A3y A3z surface at X surface at X nin surface at Ymax surface at surface at Zmax surface at Zin SPH sphere surface side face of cylinder surface vertical with the end of H surface vertical with the origin of H BOX RPP ON amp _ amp RCC surface vertical with the end of r1 r2 r3 opposite face for surface 1 surface vertical with the end of s1 52 53 opposite face for surface 3 surface vertical with the end of 11 12 3 opposite face for
93. 12 2 Questions related to error occurred in compiling or executing PHITS Q2 1 I got an error in compiling PaiTs How can I compile PuiTS A2 1 The status of most variables used in was changed from static to dynamic Consequently 2 50 or later cannot be compiled by old Fortran compilers such as 77 and 277 Therefore FORTRAN com pilers recommended by PuiTs office are Intel Fortran Compiler 11 1 or later and gfortran 4 71 or later See 2 4 Compilation using makefile for Linux amp Mac section in detail Q2 2 Segmentation fault occurred during the execution of PHITS A2 2 It might be due to the overflow of the memory used in PuTs In that case you have to increase the maximum size of memory acceptable to 175 The maximum size is defined as mdas parameter in param inc in the src directory Thus you have to increase this number and re compile 175 You may also have to increase latmax parameter if you would like to use a huge lattice structure such as voxel phantom See Manual 2 9 Array sizes in more detail 202 12 FAQ Q2 3 An error occurred when I try to use infl in my PuiTs input file A2 3 When infl command is used in your 175 input file let name input dat you have to type file input dat at the first line of input dat file Or you have to make another input file let name phits in whose first lineis file input dat and use phits in as the input file of the Pa Ts For example p
94. 14 15 17 FILL 1 2 0 11 12 13 14 17 16 FILL 2 101 1 1 0 10 13 14 U 1 102 0 101 U 1 201 2 10 0 10 13 14 U 2 202 1 1 0 201 U 2 9 1 1 2 Surface 19 CY 5 11 PX 6 12 PX 6 13 PY 6 14 PY 6 15 PZ 6 16 PZ 6 17 PZ 0 82 4 SECTIONS FORMAT The universe 1 and 2 are defined in the 7th 8th lines and the 9th 10th lines respectively using cell parameter U These universes have a similar structure that a cylinder is put at the origin of the coordinate space but their components of inside or outside of the cylinder are different from each other as shown in Fig In the 5th and 6th lines the 1st and 2nd cells are respectively defined as regions filled with the corresponding part of the each universe using cell parameter FILL The result of this example is shown in Fig One sees that the 1st cell consists of the 101st and 102nd cells in the universe 1 and the 2nd cell consists the 201st and 202nd cells in the universe 2 10 TTTTTTTT TTTTTTTTT s 7 void 5 0r 4 water C iron 5 102 J 202 3 10 r 10 5 0 5 10 z cm Figure 4 15 Result of the cell section example 5 You cannot use an undefined region in the universe If the 102nd cell is not defined in the 8th line as a void region you cannot fill the Ist cell with the universe 1 In addition you should know that all universes have the same definition for the coordinate system position of the origin directions of x y and
95. 2 If there is no resfile for a tally it is regarded as new one If resfile for all tallies cannot be found a new calculation is started with istdev abs istdev 3 If resfile exists PuiTs reads from the file about the information on the variance mode istdev total weight resc2 total history number resc3 history number per batch maxcas and the next random seed ri jklst and results and relative errors of the past calculation 4 Check the consistency between tally parameters given in the current and past PuiTs input files If they are not consistent each other Pa Ts stops the calculation and output an error message It should be noted that the consistencies of not all tally parameters are checked in this process 5 Check the consistency of istdev and maxcas in the batch variance mode only among the resfiles If they are consistent the restart calculation is performed using those valued If the inconsistency is found the calculation is stopped 6 Change the initial random seed to rijklst obtained from the first resfile If rijklst written in resfiles are different from one another a warning message is outputted 7 When the restart calculation is finished the tally results are outputted in the file specified by file In the case that resfile is not specified the past tally results are overwritten Important notice I All past tally results should be calculated in the same variance mode i e istdev in all resfile
96. 2 These big values are given in an input echo automatically You can see and paste this settings from the input echo If you want to change the order of region number reg and volume vol set as vol reg You can use the skip operator non In the input echo numbered entry is given in non column When axis reg the numbered entry is used as a value of X axis Even if you use GG use the symbol not cell but reg here When you define regions in the bottom level set same region twice as 3000 lt 3000 1 2 3 61 1 5 1 3 r z mesh When you use the r z scoring mesh first offsets for x and y coordinate of the center of cylinder can be defined as mesh y0 NJ pH This can be omissible Then define r and z mesh as 120 5 COMMON PARAMETERS FOR TALLIES Mesh definition is described later 5 1 4 xyz mesh When you use the xyz scoring mesh set x y and z mesh as Mesh definition is described later 5 20 Energy mesh Energy mesh begins as e type 1 5 el type and e2 type are also used in DEPOSIT tally Mesh definition is described later 5 3 LET mesh LET mesh begins as 5 4 Time mesh 121 Mesh definition is described later 5 4 Time mesh Time mesh is defined as Mesh definition is described later 5 5 Angle mesh Angle mesh in cross tally is defined as
97. 2 The track length or fluence of heavy ions calculated by t track or t cross is strange A3 2 It might be due to the miss define of the energy mesh in the tally section The energy of heavy ions should be defined in MeV in the tally section although it should be written in MeV nucleon in the Parameters section Q3 3 Results obtained by T LET and or T SED tally are strange A3 3 You have to check the density of material selected by letmat If you select the material that is not used in your geometry you have to define its absolute atomic densities 1H 6 893407e 2 160 3 446704e 2 in Material section Q3 4 How can we estimate the statistical uncertainty from the tally output A3 4 Version 2 50 or later the standard deviations or standard errors are correctly outputted in the tally results See 4 2 2 Number of history and bank section in detail Q3 5 Can I use dump function when I execute in the distributed memory parallel computing A3 5 From version 2 30 it works Please ask PuiTSs office about its detailed usage Q3 6 Tally results in a box obtained using mesh reg and mesh xyZ are inconsistent with each other A3 6 PHITS automatically calculate the volume of tally regions only in the cases of mesh xyz or r z Thus if you set mesh reg and you do not specify volume section the volume of the tally region is assumed to be 1 cm 12 4 Questions related to source generation Q4 1 How can we norma
98. 3 00000 3 694830 2 non 158 lt 66 4 13 00000 2 099350 2 non The column of trcl is omissible The zero for trcl means no transformation The time is a parameter of user defined time dependent magnetic field The column of time is also omissible The for time means no time dependence Two subroutines usrmgt1 f usrmgt2 f are included in the source as user defined subroutines for the time dependent magnetic field The former is for Wobbler magnet and the latter is for pulse magnet for neutron optics You can choose these two subroutine by usrmgt 1 2 in the parameter section For the Wobbler magnet time means phase of the magnet starting time for pulse magnet respectively In the above expression reg is region number typ can take 2 or 4 for dipole electromagnet or quadrupole electromagnet respectively mgf denotes the strength of the magnetic field KG and 1 is the coordinate transformation number defined in transform section You can use the format 2 5 8 9 and you can use the lattice and universe style as C 6 lt 10 1 9 0 lt u 3 But you need to close a value by C if itis not a single numeric value By using this format you can set different magnetic field for each lattice If a cell is re defined the value which is defined at first is used In the case of dipole magnet the distances gap make no sense but set any numeric The magnetic field is available not only in the voi
99. 30 0 2 1 non 7 193 0 00000 35000 0 0 1 non We can not take into account of the gravity nor additional dipole magnet For 60 case it is assumed that the spin always keeps parallel or anti parallel to the magnet field For 61 case we solve the coupled equation of motion between the spin and the magnetic field Then the spin flip can be occurred in the region with weak magnetic field The strength of the magnetic field is specified in the unit of T m in mgf column For the types above 100 we consider the coupled equations of the spin and the magnetic field In addition the effects of the gravity and additional dipole field can be taken into account 106 is sextupole 184 quadrupole and 182 dipole respectively The strength of additional quadrupole magnet z direction is give by the column of gap in the unit of T For 181 type the magnetic field is defined by the user program file usrmgf1 f In this user program the data measured by the neutron optics group in JAERI are read from the file and used the calculation The strength of this field is renormalized by the value of mgf For 101 type the magnetic field is also defined by the user program file usrmgf3 f In this user program there is a simple sextupole magnet field as same as in 106 type The neutron goes into the magnetic field with the initial spin if it is defined in the source section If not the initial spin is defined at the moment when the neutron goes into the
100. 4 6 8 1 0 1 33 0 543 0 0060 2 1 4 6 8 C 1 0 1 34 0 321 0 00323 1 4 6 8 1 0 1 35 0 678 WwW Ne In above example the mset1 is for heat and the mset2 is zero for proton attenuator set for neutron 62 T Cross section 137 62 T Cross section Using the T Cross tally you can obtain the current or flux actually fluence on any specified surface In this tally whenever a particle crosses the surface current is simply added by 1 while flux is added by 1 cos 6 where 0 is the angle between the direction of the particle trajectory and the normal vector to the surface In the current and flux each other are similar but different physical quantity The difference is due to the surface element which is used to calculate the number of the crossing particle per unit area The current is evaluated with division by the area of the surface 5 shown in Fig On the other hand the flux is done with division by S cos The value of S is given in the geometry mesh subsection as area for reg mesh The is calculated automatically for r z and xyz mesh derection of particle trajectory Figure 6 2 Relation between the two areas and S cos 0 Since the flux in this tally is evaluated with weight of 1 cos 6 the result is equivalent to that obtained from the t track tally for an extremely thin region Consequently you can obtain information on the detector response in the specified surfac
101. 4 6 parameter 6 parameter value explanation ielas D 2 elastic scattering option 0 exclude elastic scatter 1 include neutron elastic scatter 2 include neutron and proton elastic scatter ielms D 100 number of angle group for elastic scattering inmed D 1 nucleon nucleon cross section options for Bertini model 0 free nmtclb25 dat 1 Cugnon old nmtclb95 dat 2 Cugnon new nmtclb30 dat nevap D 3 options for Evaporation model 0 without evaporation model 1 using DRES model 2 using SDM model 3 using GEM model ismm D 0 Control parameter of Statistical Multi fragmentation Model SMM 0 SMM is not used 1 SMM is used When a JQMD calculation is performed switching time from JQMD to GEM changes from 100fm c which is the default value to 75fm c igamma D 8 decay option for residual nuclei 0 without y decay 1 with y decay 2 with y decay based on EBITEM model 3 with decay and isomer production based on model Until ver 2 73 file 14 trxcrd dat is required for igamma 1 3 isobar D20 options for isobar model 0 without isobar 1 with isobar ipreeq D 8 options for pre equilibrium model when nevap 1 0 without pre equilibrium model 1 with pre equilibrium model level D 3 level density option when nevap 1 1 8 A L2 with Baba s parameters 3 with Ignatyuk s parameters Itis noted that inmed 1 is the default value Using the Stati
102. 4 7 Schematic image of the duct source We show some example of the duct source option in the following In the first example we use the rectangle source and beam line the same size of the source and beam line dimensions Here we show the input for the duct source option 72 4 SECTIONS FORMAT List 4 3 duct source option example 1 1 Source 2 3 set c1 200 d10 4 set c2 500 d11 5 set c3 5000 d12 6 set c4 5 0 x 2 Zi set c5 5 0 y 2 8 set c10 5 0 dxw 9 set c20 5 0 dyw 10 set c30 0 001 dpf 11 12 s type 2 13 proj neutron 14 20 0 15 c4 2 16 x1 4 2 17 c5 2 18 yl c5 2 19 20 0 0 20 21 0 0 21 dir 1 0 22 phi 0 0 23 24 dom 10 25 dl8 cl 26 dli c2 27 d12 c3 28 c10 29 dyw 2 30 dpf c38 at 20 at 20 In the first part of above source section we define some constants which are necessary for the duct source option 410 411 412 size of source dyw dpf In the second part we define the position and xy region of the source direction of the beam line and the energy of source particle In the third part we define the duct source options We calculated particle transport in the beam line from 5 m up to 50 m by this duct source and the current wall current by using the cross tally The results are shown in Fig 4 8 compared with an ideal case in which the current and the wall current are proportio
103. 5 COMMON PARAMETERS FOR TALLIES The first definition is to specify the transformation number defined in transform section The next one is to define the transformation directly here with 13 parameters as same as in transform section If the data are not written in a line you can write them in multiple lines without the line sequential mark But you need to put more than 11 blanks before data on the top of the sequential lines In the 3dshow tally trcl can be used to transform the box This will be explained in the t 3dshow tally section 5 7 20 dump definition In the t cross t time t product tallies information on the particles can be dumped on the file By the parameter of dump the number of the dump data in one record is specified If this number is given by positive number the data are read as binary data If negative the data are read as ascii data In next line the data sequence of one record is described The relation between the physical quantities and id number is the followings Table 5 3 id number of dump data 1 physical quantities kf x y time cl c2 3 sx sy sz id number 1 2 3 4 5 6 7 819 10 11 12 13 14 15 16 Table 5 4 id number of dump data 2 physical quantities name nocas nobch no id number 17 18 19 20 Here kf means the kf code of the par
104. 6 21 22 23 24 25 26 u 6 lat 1 fill 1 1 0 0 0 0 2 2 8 8 5 2 8 60 21 22 23 24 25 26 u 7 fill 1 1 0 0 0 0 2 3 2 lat 1 9 3 1 3 97300 02 3 u 2 6 5 18 4 4 18280 02 3 u 2 11 13 8 47130E 04 3 u 3 12 14 3 1 23620 01 3 u 3 13 8 1 1 14 surface 15 1 rpp 15 15 5 5 5 55 16 21 px 5 17 22 px 5 18 23 py 5 19 24 py 5 20 25 pz 15 21 26 pz 5 22 41 px 15 23 42 15 24 43 py 5 25 44 py 5 26 45 pz 15 27 46 pz 5 28 5 20 28 5 5 5 35 29 6 20 20 5 5 5 15 30 7 20 28 5 5 35 55 31 3 010 4 In above geometry the whole body is rectangular solid and it has rectangular solid lattices including cylinders inside You can make graphical plot for the geometry by the 3dshow as List 6 7 t 3dshow example 1 t 3dshow 2 output 3 3 heaven x 4 resol 2 53 width 9 1 6 x0 0 7 yO 0 8 20 25 9 e the 70 10 e phi 50 11 e dst 1000 12 l the 50 13 l phi 25 14 l dst 2000 15 w wdt 60 16 w hgt 40 17 w dst 158 18 file dshow dat 188 6 TALLY INPUT FORMAT The output result is You can add region boundary by option line 1 as You can see how lattices are set up Next let material number 5 be transparent and add shadows by material 1 shadow 2 617 T 3Dshow section 189 Let s define a box box 1 box 8 10 30 100 10 30 98 10 100 100 The defined box part becom
105. 7 0 13 7 14 lt 7 7 9 The default order for this definition is r in r out area If you want to change the order define as r in r out area You can use the skip operator non You can use the format 2 5 8 9 and you can use the lattice and universe style as 6 lt 18 1 0 8 lt u 3 But you need to close a value by C if it is not a single numeric value If you set output flux obtained flux is one way from r in to r out If you want to set both way flux set as the third line of above definition If you set mesh r z two kinds of crossing surface are defined One is the number of nz 1 crossing surfaces for z defined by r ri 1 The other is the number of nr 1 crossing surfaces for defined by z z 1 If r surface coincides with the surface of outer void the flux on this surface is not tallied If you set mesh xyz the number of nz 1 crossing surfaces for z are defined by x xi and y In this case x and y crossing surfaces are not defined When you set mesh rz xyz crossing particles are detected in both ways at defined surface The forward definitions are positive direction in z surface and from center to outside in r surface 63 T Heat section 63 T Heat section T Heat gives deposit energy for optional region Deposit energy by low energy neutron photon and electron can be also tallied in this tally The heat from neutrons is usually obtained
106. 8688 fission 155 170 flight mesh 34 fluence 133 137 flux 137 140 190 Fortran 7 9 T4 1271 200 gamma decay for residual nuclei 25 gap 104 GAS 75 gcut GEM 25 GG 12 B1 2 P7100 02 TO3 TT 7 119 GG General Geometry 77 ghostview 129 ginfo 135 140 23 L45 E51 155 E58 161 164 67 GQ pI gravity groups 122 gshow 19 108 28 129 135 40 143 145 151 155 gslat 135 140 43 146 15 1 155 158 161 64 167 heat 41 heaven 183 heavyion 170 HEX 92 HLIB 75 INDEX HSB 109 iaprim iauger ibad ibod ibound ibrdst icntl icput icrhi ICRU Report 162 icxsni idam 1 idbg ides idpara idwba iechrl 135 143 146 148 155 158 61 164 167 170 iedgfl iegsout iegsrand ieispl ielas ielctf ieleh ielms igamma igchk igcut igerr iggcm Ignatyuk igpara ih2o imagnf imout impacr importance imucap imuint INC ELF incelf INCL inclg include include files incohr incut infl info infout inmed inner void 77 inpara input echo INDEX installation Intel Fortran interpolation 116 inucr ionization potential ipara ipcut iphot iphter ipngdr ipnint ipout ippara iprdst ipreeq iprofr iprtb2 iraylr ireschk irqmd irskip iscorr isobar istdev istrg
107. 97 4 9 Weight Window 98 4 10 Volume section omo oo Ro RO ke ROO E ADR SO Xx 99 411 Temperature section RI 100 4 12 Brems Bias 101 4 13 Photon Weight 102 4 14 Forced Collisions 103 4 15 Magnetic 14 104 TOPIC 104 HEIN TEMERE 105 doe awe dna ud A oe V 106 4 17 Counter section 107 4 18 Reg Name section som mm RR Run A Re REUS 108 4 19 Mat Name Color 109 4 20 Mat Time Change 111 4 21 Super Mirror 112 4 22 Elastic Option 113 4235 rm et section xeu do esame Ro Um Ress A S 114 4 24 deltatay section e 4 4 34 be SE RC RO Rows Bom do UR RS 115 4 25 Multphner section ll rs 116 lil Common parameters for tallies 5 1 Geometncal mesh lees 5J 1 Regionmesh x x 4x4 Xu E REESE m v dus 5 1 3 rzmesh 5 1 4 xyz mesh 5 2 Energy mesh
108. A1 1 Q1 4 What kind of simulation does event generator mode suit for 1 4 Event generator mode suits simulations by which the event by event information is necessary to be ob tained e g detector response calculations and design of semi conductor devices It is also useful for the simulation that must determine energy and type of charged particles produced by low energy neutron in teractions In concrete event generator mode generally suits does the simulations using T Deposit T LET T SED T Yield and or T Product tallies On the other hand it is not suit for the sim ulations only using T Track and or T Cross tallies such as shielding calculation See 2 2 21 Event Generator Mode section in more detail Q1 5 When should I change the mode for the statistical uncertainty the setting of istdev 1 5 We generally recommend the history variance mode istdev abs 2 where the statistical uncertainty depends on the total history number maxcas maxbch except for the case of shared memory parallel com puting where only the batch the batch variance mode istdev abs 2 can be selected However the computational time occasionally becomes extremely long in the history variance mode especially in the case of tallies using a lot of memories e g xyz mesh tally with very fine structure When you perform the calculation with such conditions please change to the batch variance mode and set maxbch to be more than 10
109. Analysis of the N xN reactions by quantum molecular dynamics plus statistical decay model Physical Review C 52 2620 1995 6 J J Butts and Robert Katz Theory of RBE for Heavy Ion Bombardment of Dry Enzymes and Viruses Radiation Research 30 855 871 1967 7 Y Sakamoto Sato S Tsuda Yoshizawa S Iwai S Tanaka and Y Yamaguchi Dose conversion coefficients for high energy photons electrons neutrons and protons JAERI 1345 2003 8 T Sato Watanabe and Niita Development of a calculation method for estimating the specific energy distribution in complex radiation fields Radiat Prot Dosim 122 41 45 2006 9 T Sato Y Kase Watanabe Niita and L Sihver Biological dose estimation for charged particle therapy using an improved PHITS code coupled with a microdosimetric kinetic model Radiat Res 171 107 117 2009 10 International Commission on Radiation Units and Measurements Microdosimetry ICRU report 36 Mary land ICRU 1983 11 Hirayama et al The EGSS code system SLAC R 730 2005 and KEK Report 2005 8 2005 Index source angular distribution decay brems bias cell 3 12 13 75 77180 82H88 91 93 97 08 100 counter AN 107 129 delta ray 5 12 L 15 elastic option 12 113 electro magnetic field 12 47 L06 end 13 14 12 103
110. FORMAT T Star gives star density which is the distribution of the nuclear reactions Reactions for electron by libraries are not included Table 6 31 t star parameter 1 number of materials next line 258 name value explanation mesh reg r z Xyz geometry mesh you need geometry mesh subsection below this option part all default maximum 6 particles in a t star particle name projectile particle of the reaction material omissible You can specify materials for scoring all all default same as no definition When you set number of materials define these material numbers in the next line You can set number of materials by negative In the case specified materials are not included for scoring material numbers mother omissible all number of mother nuclei next line 208Pb Pb You can specify mother nuclei all default same with no definition When you set number of mother nuclei define their mothers in the next line You can set number of mothers by negative In this case specified mothers are not included for scoring Nucleus if you specify with mass Without mass all isotopes of Pb If you want to specify multiple mother groups use multiple t star tallies nucleus omissible all number of nuclei next line 208Pb Pb You can specify output nuclei all default same with no definition When you set number of nuclei define their nuclei in
111. Fig Note that directions of this coordinate correspond to those of the usual coordinate x y 2 and are defined by the order of the surface number written in the cell definition When you specify any cell using mesh reg in tally sections you can use the lattice and universe styles as 201 lt 101 1 0 lt 1 where the lattice coordinate is represented by s t u See Sec 5 1 2 for this format as well You can see lattice coordinates by the t gshow tally with output 7 or 8 The next is an example using hexangular prism LAT 2 List 4 14 cell section example 7 1 Material 2 mat 1 1H 2 160 1 3 cell 4 1 0 11 12 13 14 15 16 FILL 1 5 101 9 31 32 33 34 35 36 24 23 LAT 2 U 1 FILL 2 6 201 1 1 0 98 U 2 7 2 1 1 8 Surface 9 11 PX 6 18 12 PX 6 11 13 PY 6 12 14 PY 6 13 15 PZ 6 14 16 PZ 6 15 23 PY 2 16 24 PY 2 17 set 1 2 18 31 PZ cl1 cos pi 6 19 32 PZ 1 6 20 33 P 1 0 1 tan pi 2 c1 21 34 P 1 1 tan pi 32 1 22 35 P 1 1 tan pi 3 c1 23 36 P 1 1 tan pi 3 c1 24 98 BOX 10 10 10 2000 0 20 0 00 20 A hexagon with LAT 2 is defined in the 5th line using 6 surfaces defined in the 17th 23th lines The hexagonal prism is restricted in the y direction by 24 23 in the cell definition and is filled with the universe 2 namely water as written in the 6th line The Ist cell has the repeated structure defin
112. GS5 output files Delete all EGS5 output files when PHITS calculation is finished Some files remains when you terminate the PHITS calculation by yourself 1 Keep egs5 inp pegs5 dat and pegs5 msfit and delete the others 2 Keep all EGS5 output files See EGS5 manualfor the detail of each file iegsrand D 1 Option for random number used in EGSS If you set 0 or positive value to this parameter you cannot use the MPI parallelization nor the restart calculation function lt 0 use random number generated by PHITS 0 use random number generated by EGS5 with the default initial random seed 314159265 gt 0 use random number generated by EGS5 with the initial random seed iegsrand iedgfl D 1 Option for K and L edge fluorescent photons 0 Do not explicitly treat K and L edge fluorescent photons 1 Explicitly treat L edge fluorescent photons iauger D 1 Option for K and L edge Auger electrons 0 Do not explicitly treat K and L edge Auger electrons 1 Explicitly treat L edge Auger electrons iraylr D 1 Option for coherent Rayleigh scattering Do not consider coherent scattering 1 Consider coherent scattering lpolar D 8 Option for linearly polarized photon scattering NOT valid at this moment 0 Do not consider linearly polarized photon scattering 1 Consider linearly polarized photon scattering The maximum number of material is limited to 100 in this mode and th
113. If you want to use continuation lines it is enough to put more than 4 blanks at the line head instead of the line sequential mark at the end of line The ce11 is defined in order by the data cell number material number material density cell definition and cell parameter as keyword style These are explained in Table 4 49 The format is shown below Cell cell number mat number mat density cell def cell parameter LIKE n BUT cell parameter format and repeated structure with lattice can be used See Sec in which we describe how to use them with some examples The cell parameters are listed and explained in Table 4 50 Table 4 49 cell definition format item explanation cell number You can use any number from 1 to 999999 material number Set 0 for void 1 for the outer region or material number defined in material section material density If the cell is void or the outer region no input When the given value is positive or negative it is particle density 107 atoms cm or mass density g cn respectively A material density defined in the material section is renormalized to the particle density given here Thus different density materials which have the same composition with original one can be set in this section new parameter matadd is prepared in order to add different material number cell definition Cell geometry is defined by both surface numbers in the surface section
114. M code which is an origin of code structure of PuiTs 1 4 Recent Improvements Essences of improvements after version 2 24 are described below From version 2 76 following functions were implemented e Muon nuclear interaction model based on the virtual photon production theory was implemented Char acteristic X ray production from muonic atoms as well as associating muon capture reaction can be also considered in the new version e Adjustment parameters for determing the magnitude of angular straggling for nspred 2 were introduced e Bugs due to the problem of Intel Fortran 2015 were fixed From ver 2 75 we fixed a bug that the function of sum tally does not work when you use an input file including some sections of tally and corrected a bug occurs in setting e mode 2 From version 2 74 following functions were implemented e Version of DCHAIN SP included in the PHITS package was changed from DCHAIN SP2001 dchain264 exe to DCHAIN SP2014 dchain274 exe DCHAIN SP2014 was improved from DCHAIN SP2001 in terms of the following aspects 1 The input format was changed 2 The number of energy groups of neutron activation cross section libraries was increased from 175 to 1968 3 A new function was implemented to output the source section of PHITS from the activities calculated by DCHAIN SP 1 INTRODUCTION 4 A new function was implemented to output the time dependence of radioactivities in each region in the input
115. Number of maximum column for volume input echo volmat omissible D 9 The option corrects a volume value for each mesh when material is defined by xyz mesh 0 means no correction Value of volmat means the number of scans for one side of xyz mesh epsout 0 default 1 If epsout is set to 1 results are plotted into eps files This eps file is named by replacing the extension into ctmin i omissible D 9999 minimum value for i th counter ctmax i omissible D 9999 maximum value for i th counter trcl omissible coordinate transformation number or definition for r z or xyz mesh gslat 1 default 0 1 show lattice boundary in gshow 0 no dresol Comissible D 0 0 Parameter for representing the detector resolution Valid only for output deposit When you set dresol c and dfano F deposition energy E of each event is fluctuated by following the Gaussian with standard deviation y0 FE dfano Comissible D 0 0 Parameter for representing the detector resolution Valid only for output deposit When you set dresol c and dfano F deposition energy E of each event is fluctuated by following the Gaussian with standard deviation 402 FE When output deposit a result with part all does not equal to a sum of results obtained by setting part individual particles When output dose a result with part all equal to a sum of results obtained by setting part indiv
116. PHITS Ver 2 76 User s Manual English version Contents 1 Introduction 2 3 4 1 1 Recent Improvements lle 1 2 Development members 1 3 Reference of PHITS Installation compilation and execution of PHITS 2 l Operating environment 2 2 Installation and execution on 2 3 Installation and execution on 2 4 Compilation using make command for Windows and Linux 2 6 Compilation of ANGEL Input File 3 1 Sections 3 2 Reading control 3 3 Sections format 4 1 4 2 4 3 Title secion 2l 422 1__ 4 2 2 Number of history and Bank 4 2 3 Cut off energy and switching energy 4 2 4 Cut off time cut off weight and weight window 4 2 5 Model option 1 4 2 7 Physical parameters for low energy neutron 4 3 6 Generic parabola distribution source x y z independent Inserting hiles o R9 eX 3 4 User definition constant 3 5 Using mathematical expressions 3 6 Particle identification 4 2 6 1 2 4 2 7 1 3 42 8 Modeloption 4 lens 429 5 1 4 2 10 Outputoptions 2
117. SED section 163 Table 6 27 t sed parameters 2 name value explanation se type 1 2 3 4 y or z mesh unit is defined by se unit You need energy mesh subsection below this option specified in ne emin emax etc If you encounter Warning Z bin is not enough then you have to change emin emax and ne parameters This warning indicates that the microdosimetric function cannot calculate the y or z distribution because of too small range or too poor resolution of its mesh For example you have to set se type 3 emin 0 01 emax 10000 0 ne 60 or more for calculating y distribution for cite diameter 1 um cdiam 1 0 se unit 2 unit 1 2 3 4 1 Track cm keV um source 2 Dose MeV keV um source corresponding to y f y 3 Track cm In keV um source 4 Dose MeV In keV um source corresponding to y d y 5 Track cm source 6 Dose MeV source The units are for the case of se unit 2 For se unit 1 and 3 keV um is replaced by MeV and Gy respectively axis sed reg x y Z r Xy YZ XZ x axis value of output data 2 dimensional file file name Define file names as same number of axis resfile omissible D file Define a file name of the past tally in the restart calculation Even if several axis parameters were defined you should specify only one resfile factor omissible D 1 0 normalization factor ti
118. U Report 3619 Usage of t sed is similar to that of t let Table 6 26 t sed parameters 1 name value explanation mesh reg r z xyz geometry mesh you need geometry mesh subsection below this option part all default maximum 6 particles in a t sed particle name material omissible You can specify materials for scoring all all default same as no definition number of materials When you set number of materials define these material numbers in the next line You can set number of materials by negative In the case specified materials are not included for scoring next line 258 material numbers letmat omissible material id for LET dE dx If omitted real material is assumed If you select the material that is not used in your geometry you have to define its material density in material section If you would like to calculate LET in water you have to define water with 1 g cm in material sectiont When you set letmat 0 PHITS automatically calculates dE dx for water with 1 g cm for electrons and positrons Please see particletherapy in the recommendation setting in more detail se unit 1 2 3 Unit of deposition energy in microscopic site 1 deposit energy in MeV 2 lineal energy y in keV um 3 specific energy z in Gy cdiam omissible D 1 0 Diameter of the microscopic site in um You can select the value from 0 001 to 2 0 6 10 T
119. acteristic X ray production from muonic atoms and nuclear absorption are considered 0 This reaction mechanism is not taken into account 1 This reaction mechanism is taken into account imuint D 0 Options for muon induced nuclear reaction based on the virtual photon theory 0 This reaction mechanism is not taken into account 1 This reaction mechanism is taken into account emumin D 200 0 Minimum energy of muon induced nuclear reaction MeV emumax D 1 0e 6 Maximum energy of muon induced nuclear reaction MeV npidk D 0 treatment of minus charged decay particles below cut off energy 0 make absorbed by force 1 make decayed imagnf D 0 Magnetic field 0 without Magnetic field 1 with Magnetic field ielctf D 0 Electro Magnetic field 0 without Electro Magnetic field 1 with Electro Magnetic field andit D 0 A angular distribution for Bertini 0 50 isotropic 50 forward 1 all isotropic 2 all forward icxsni D 0 Option for reaction elastic and total cross sections in nucleon nucleus collisions 0 Pearlstein Niita formula 1 KUROTAMA model 2 Sato formula icrhi D 1 option for total cross section for Nucleus Nucleus collision 0 Shen formula 1 NASA formula 2 KUROTAMA model If a particle which has decay channel takes lower energy than cut off the particle decays completely In such decay particles minus charged particles with npidk 89 are forced to take reaction for the purpose of force
120. ail model for photon MeV ides D 8 electron creation options by photon 0 create electron or brems photon 1 not create electron nocoh D 8 coherent scattering options for photon 0 with coherent scattering 1 without coherent scattering iphot D 8 photon creation options by electron 0 create photon not create photon ibad D 0 angular distribution option for brems 0 full brems tabular angular distribution 1 simple brems angular distribution approximation istrg D 8 straggling 0 sampled straggling for electron energy loss expected value straggling for electron energy loss bnum D 1 brems photon 0 not create brems photon gt 0 number of analog brems photons xnum D 1 x ray photon 0 not create x ray photon gt 0 number of analog x ray photons enum D 1 secondary electron 0 not create secondary electron gt 0 number of analog secondary electrons numb D 0 brems process 0 nominal brems production gt 0 produce brems on each substep 38 4 SECTIONS FORMAT 4 2 19 Parameters for EGS5 Table 4 20 parameter 19 parameter value explanation negs D20 Option for the usage of EGS5 0 do not use EGSS i e use the original model for photon electron and positron transport Parameters given in Table 4 19 are activated only in this mode 1 use EGS5 for photon electron and positron transport You have to specify file 20 in this mode EGS5 iegsout D 0 Option for controlling the E
121. alculation number of batch should be an integer multiple of all number of PE 1 If not PuiTs converts automatically the batch number as it becomes an integer multiple and as the total number of history becomes almost same with given total histories In this case some comments are output at the end of an input echo The procedure for calculating statistical uncertainties was revised from version 2 50 The function to restart the PuiTS calculation based on the tally results obtained by past PuiTs simulations was implemented in order to increase the history number when the number is not enough In this mode the initial random seed is also read from the past tally file In the calculation of statistical uncertainties you can select two modes batch variance mode and history variance mode which calculate the standard deviations using variances between tally results of each batch and history respectively In both modes standard deviation c is calculated by N 25 NX Izi NN 1 0 where is the total batch number istdev 1 the total history number istdev 2 x are tally results and the source weight of each sample respectively and X and w are the mean values of the tally results and source weights of N samples respectively The ratio of o to X is written as relative error in the tally output file When 42 Parameters section 21 you use the shared memory parallel computing you can select on
122. als are not included for scoring next line 258 material numbers mother omissible You can specify mother nuclei all all default same with no definition number of mother nuclei When you set number of mother nuclei define their mothers in the next line You can set number of mothers by negative In this case specified mothers are not included for scoring next line 208Pb Pb Nucleus if you specify with mass Without mass all isotopes of Pb If you want to specify multiple mother groups use multiple t product tallies e type 1 2 3 4 5 energy mesh You need energy mesh subsection below this option t type 1 2 3 4 5 time mesh omissible You need time mesh subsection below this option a type 1 2 1 2 angle mesh 1 2 cos 1 2 degree You need angle mesh subsection below this option 67 T Product section Table 6 17 t product parameter 2 name value explanation unit 1 2 3 4 5 6 11 12 13 14 15 16 21 22 23 24 25 26 31 32 33 34 35 36 1 1 source 2 1 cm source 3 1 MeV source 4 1 cm MeV source 5 1 Lethargy source 6 1 em3 Lethargy source 11 1 nsec source 12 1 cm nsec source 13 1 MeV nsec source 14 1 cm MeV nsec source 15 1 Lethargy nsec source 16 1 cm Lethargy nsec source 21 1 SR source I cm SR source 1 MeV SR source 24 1 cm MeV SR source 1
123. and Boolean operators Li blank AND OR and NOT Parentheses and can be also used See Sec 4 5 2 for detail LIKE n BUT A cell using this format is the same as the n cell except only parameters described after BUT cell parameter This format is keyword value As keyword VOL volume TMP temperature TRCL transform U universe LAT lattice and FILL can be used In the LIKE n BUT format MAT material and RHO density can be used in addition When you define some cells having different densities from each other with the same material number the cells come to be with other material number except for the first cell 78 4 SECTIONS FORMAT Table 4 50 cell parameter item explanation VOL Volume cm of the cell is given TMP Temperature MeV of the material in the cell is given TRCL Coordinate transform for position of the cell is done using coordinate transform number defined in the transform section or the transform format U Universe number Number of the universe including the cell is defined You can use any number from 1 to 999999 See Sec 4 5 3 for detail LAT Lattice number Setting LAT 1 or 2 you can define quadratic prism or hexangular prism respectively See Sec 4 5 4 for detail FILL Set universe numbers to fill the cell with the universe MAT This is used with LIKE BUT MAT m format You can define the same cell except that its material
124. arameter 3 name value explanation gshow default 1 2 3 4 When meshzxyz axis xy yZ XZ region border 1 material name 2 region name 3 and LAT number 4 are plotted by the option rshow default 1 2 3 When mesh reg axis xy yZ XZ region border 1 material name 2 and region name 3 are plotted by the option You need xyz mesh section below this option ginfo 0 default 1 2 No geometry check in the case of gshow or rshow gt 0 Check geometry and draw its two dimensional view with error information Check geometry draw its two dimensional view and outputting a geometry error file err resol width 1 default 8 5 default The option multiplies region line resolution by resol times with gshow or rshow option The option defines the line thickness for gshow or rshow option volume reg vo 1 omissible The option defines volume for each region for reg mesh You need volume definitions below this option Default values are given in input echo in the case of no definition volume definition See 5 1 2 iechrl 72 default Number of maximum column for volume input echo volmat omissible D 9 The option corrects a volume value for each mesh when material is defined by xyz mesh 0 means no correction Value of volmat means the number of scans for one side of xyz mesh epsout 8 default 1 If ep
125. arameters for this source type are shown below The order of parameters is free If a parameter has a default value D the parameter can be omissible Table 4 32 parameters for s type 11 s type 11 uniform distribution in a phase space vertical with beam direction D 0 0 x coordinate of beam center cm 1 ratio of maximum radius minimum radius for x direction cm mrad D 0 0 y coordinate of beam center cm 1 ratio of maximum radius minimum radius for y direction cm mrad 20 minimum 7 cm 21 maximum z cm rx gradient of ellipse in a phase space on x direction rad ry gradient of ellipse in a phase space on y direction rad wem emittance z cm x mrad dir direct cosine 1 or 1 only projectile energy MeV 4 3 11 s type 12 In this source type decay turtle output is read as source Parameters for this source type are shown below The order of parameters is free If a parameter has a default value D the parameter can be omissible The input file is rewinded and re used from the first particle again if all of source in decay turtle is read before the calculation finishes Table 4 33 parameters for s type 12 s type 12 decay turtle reading D 0 0 x coordinate offset of beam cm y8 D 0 0 y coordinate offset of beam cm 20 D 0 0 z coordinate offset of beam cm dir direction cosine 1 or 1 only file decay turt
126. as distribution projectile energy s type 7 MeV e type type of energy distribution wgt D 1 0 weight of source particle factor D 1 0 normalization of source particle t type D 0 time distribution reg D all specify the region ntmax D 1000 maximum re try number when reg is specified trcl D none transform number or definition of transform 58 4 SECTIONS FORMAT We show a sample program of usrsors f as following In the first comment part there is a list of the variables which is necessary to define the source Next there is a list of kf code which specifies the source particle In the last part of the comment the random number functions one is an uniform random number the other is a Gaussian random number are shown The first part of the program is an example of the initialization which describes the open and close the data file The remaining part shows a list of the variables which user should define in this subroutine List 4 1 6 usrsors f 1 de ve vede de dee dee ee e de de de de de dede de dede dee dede e ede e e de de de dede dede dede dede de dee ede ee e de de de dede de dede dede ke ke ke ke kek kek keke ee 2 subroutine usrsors x y z u v w e wt time name kf ncl nc2 nc3 3 amp SX Sy SZ 4 sample subroutine for user defined source 5 j variables j 6 X y Z position of the source 7 u V W unit vector of the particle direction 8 x e kinet
127. as the energy differ ential value expressed in particles MeV For e type 2 3 5 6 7 12 14 15 16 you can define the energy differential spectrum using various functions For e type 8 9 18 19 you can define the source intensity discretely If a parameter has a default value D the parameter can be omissible Table 4 40 parameters for source energy distribution 1 parameter explanation e type 1 11 You can specify any energy distribution by giving data set of energy bins e i and integrated values of the particle generation probability w i by hand The number of the particle generation in the bin is proportional to w i and the specified energy distribution is statistically described For 11 case energy is given by wave length ne Number of energy group If it is given by positive number source particles are generated so that the energy differential fluxes in the unit of 1 MeV become constant in each bin On the other hand if ne is negative the fluxes in the unit of 1 Lethargy become constant in each bin Data must be given from the next line by the format as CeG w i i 1 ne 1 The integrated number of the particle generation in the each energy bin is proportional to w i e type 4 14 You can specify the same energy distribution as is the case of e type 1 11 Unlike e type 1 11 the distribution is described by giving data set of energy bins e i and weight
128. ate cm xl maximum x coordinate cm y8 minimum y coordinate cm yl maximum y coordinate cm 20 minimum z coordinate cm 21 maximum y coordinate cm when z1 z0 rectangle source dir direction cosine from z axis If you set all isotropic If you set data a type subsection is necessary phi Dznone random azimuthal angle degree dom D 0 0 solid angle degree cos bias distribution projectile energy s type 2 MeV 50 4 SECTIONS FORMAT 4 3 5 Gaussian distribution source x y z independent This Gauss distribution is consist of independent Gaussian in each x y z direction Parameters for Gaussian source are shown below The order of parameters is free If a parameter has a default value D the parameter can be omissible Table 4 27 parameters for Gaussian source s type 3 6 Gaussian source x9 D 0 0 x coordinate of Gaussian center cm xl FWHM in x direction cm y8 D 0 0 y coordinate of Gaussian center cm yl FWHM in y direction cm 20 D 0 0 gt coordinate of Gaussian center cm 21 FWHM in 2 direction dir direction cosine from z axis If you set all isotropic If you set data a type subsection is necessary phi Dznone random azimuthal angle degree dom D 0 0 solid angle degree 1 cos bias distribution projectile energy s type 3 MeV 4 3 6 Generic parabola distribution source x y z
129. atically without any symbol Note that more than 4 blanks are required at the line head of connected line Details of this function are explained later Line dividing Short lines can be displayed in a line by dividing as idbg 06 ibod 1 Q But this function is not available where the format is defined such as in the mesh description Comment marks You can use the following comment marks 90 P The comment out is effective from the comment mark to the line end You can also use as a comment mark if you put in the first 5 column at line head with blanks as In the cell and surface sections is used for cell definitions so only is available as the comment mark in these cell and surface sections Blank lines Blank lines and lines which begins from a comment mark are skipped 14 3 INPUT FILE 7 Section reading skip If you add off after a section name as Section Name off the section is skipped is not read 8 Skip in sections You can skip from any place in sections by putting qp at the line head Lines from qp to the end of the section are skipped 9 Skip all can be used as a terminator of a input file It works same as the end 3 3 Inserting files You can include other files in any place by infl filename nm m You should specify a name of a file to be inserted in and the number of lines from n
130. ation on calculations of each nuclear reaction models is outputted in detail e count number of using the model with each incident particle e real number of success for the model calculation e probability of the model calculation 4 2 10 Output options 2 Table 4 11 parameter 10 parameter value explanation incut D 0 neutron output options below cut off 0 no output 1 output in the ncut file specified as file 12 2 output in file 12 with time information igcut D 0 y ray and electron output options below cut off 0 no output 1 output y ray data in the gcut file specified as file 13 2 output y ray in file 13 with time information 3 output y ray electron and positron data in file 13 ipcut D 0 proton output options below cut off 0 no output 1 output in the pcut file specified as file 10 gt 02 output in file 10 with time information inpara D 0 ncut file name options in the parallel calculation 0 wk uname file name of 11 12 1 wk uname file name of file 12 PE number 253 file name of file 12 PE number igpara D 0 gcut file name options in the parallel calculation 0 wk uname file name of 11 13 1 wk uname file name of ile 13 PE number 3 file name of file 13 number ippara D 0 pcut file name options 0 wk uname file name of file 10 1 wk uname file name of 1 10 number 3 file name of file 10 number wk uname
131. be noted that you can define only one axis in a t yield section from ver 2 50 This restriction was implemented to calculate statistical uncertainties correctly If you want to define several axes in the t yield tally you have to set the corresponding number of t yield sections in a input file 5 7 3 file definition The format to define name of output file is file file 001 file 002 file 003 As described before when you set multiple axis set output files for each axis like following example file 001 file 002 file 003 5 7 4 resfile definition The format to specify a file name of past tally in the restart calculation is resfile file 001 where the file name must be written with full pathname Even if several resfile parameters are set in a tally section only the earliest one is used resfile is set to file by default In this case results of the past tally are overwritten 5 7 5 unit definition Set output unit as 126 5 COMMON PARAMETERS FOR TALLIES unit number The unit number and its meanings are described in each tally explanation 5 7 6 factor definition You can set normalize factor by this format factor number This value is multiplied to output values When you use the t gshow tally this factor defines line thickness instead 5 7 7 output definition Set output type as output name of output Deta
132. by 3 parameters dir phi and dom The relation between these is shown in Fig The direc tion is noted by a thick arrow The dir is a direction cosine against the z axis The phi is an azimuthal angle from the x axis in degree If you do not set it a value of the azimuthal cosine is selected randomly Using the parameter dom spreads out the direction determined by dir and phi by solid angle 2z 1 cos where y dom given in degree In the Pa Ts calculation the angle is given randomly within the solid angle When you set dir all the direction of the source beam becomes isotropic If you want to use any angular distribution a subsection started from a type is required in which you should give the distri bution by numerical data or analytic functions In s type 9 and 16 the definition of dir is different In s type 11 and 12 you can set only dir 1 or 1 You can use the transform of coordinate by 1 parameter which specify the transform number or the definition of transformation it self The relation of wgt and factor is reciprocal 4 SECTIONS FORMAT cos0 dir y dom Figure 4 2 Source direction and parame ters dir phi dom If the spin is not defined or zero the neutron goes into the magnetic field without spin In this case the initial spin of neutron is determined at the entrance of the magnetic field by the direction of the magnetic field and the polarization factor If the spin is defined in this section the n
133. case given by degree g x Any analytical function of x FoRTRAN style x denotes angle One can use intrinsic functions and constants C e g g x exp cl x 2 nn Number of angular group agl minimum cut off for angular distribution ag2 maximum cut off for angular distribution a type 6 16 Youcan specify the same angular distribution as is the case of a type 5 16 Unlike a type 5 16 the number of source particle generated in each bin is the same for all angle bin but integrated values of the weight of source particles are adjusted to be proportional to g x You can also change the number of source particles generated in each bin by specifing q i for 6 case angle is given by cosine for 16 case given by degree g x any analytical function of x ForTRAN style one can use intrinsic functions and constants C nn Number of angular group In default q type 0 equal number of particle is generated in each cell The integrated number of source particles generated in each bin is proportional to q i agl minimum cut off for angular distribution ag2 maximum cut off for angular distribution q type 60 1 D 0 generation option for 0 q i 1 for all i is assumed without the following data for 1 qG must be given from the next line by the format as q i i 1 nn 43 Source section 4 3 17 Example of multi source 67 We introduce an example of multi source which includes energy
134. cattering energies 0 Do not consider Doppler broadening 1 Consider Doppler broadening incohr and ibound automatically become 1 impacr D 1 Option for EII Electron impact ionization 0 Do not consider EII 1 Consider EII ieispl D 8 Option for splitting of x rays generated by electron impact ionization 0 No splitting 1 Splitting neispl 0 Number of electron impact ionization x rays for splitting when ieispl 1 ibrdst D 1 Option for determining of bremsstrahlung polar angle 9 Angle given by m E 1 Sampling iprdst D 1 Option for determining of polar angles of pair electrons Angle given by m k 1 Sampling iphter D 1 Option for determining angular distributions of photoelectrons 0 Emission in direction of incident photon 1 Sampling ibound D 1 Option for Compton cross section 0 Use free Compton cross section 1 Use bound total Compton cross section iaprim D 1 Option for correcting bremsstrahlung cross section 0 Use Motz et al empirical 1 Normalize integrated cross section to ICRU 37 radiative stopping power 2 No correction 39 40 4 SECTIONS FORMAT 4 2 20 Dumpall option By icntl 12 PaiTs re calculates whole transport by reading the information from dumpall file which is cre ated if you use the dumpall option The re calculation can describe whole transport events which were calculated before One needs the same input file as used in the previous calculation maxcas and maxbch canno
135. cle MTYP baryon number of the particle RTYP rest mass of the particle MeV OLDWT wight of the particle at x y z 9 QS This is dE dx for electrons at x y z 10 IBLZI IBLZ2 ILEV1 ILEV2 IBLZ1 cell id at x y z IBLZ2 cell id after crossing ILEV1 level structure id of the cell at x y z ILEV2 level structure id of the cell after crossing a ILATI This is a variable of level structure of cell b ILAT2 This is a variable of level structure of cell 11 COSTH UANG 1 UANG 2 UANG 3 NSURF COSTH cosine of an angle of incidence in a surface crossing UANG 1 2 3 x y z component of a normal vector of its surface respectively NSURF internal number of the surface This is different from the surface number defined in the surface section 12 NAME NCNT 1 NCNT 2 NCNT 3 NAME NCNT 1 2 3 collision number of the particle values of counter 1 2 and 3 6 14 T Userdefined section 177 13 WT U V W WT Wight of the particle at xc yc zc U V W unit vector of momentum of the particle 14 E T X Y Z E energy of the particle at x y z MeV T time of the particle at x y z nsec X Y Z position coordinate of the preceding event point cm 15 EC TC XC YC ZC EC energy of the particle at xc yc zc MeV TC of the particle at xc yc zc nsec XC YC ZC position coordinate of the particle cm 16 SPX SPY SPZ SPX SPY SPZ unit vector of spi
136. counter ctmax i omissible D 9999 maximum value for i th counter trcl omissible coordinate transformation number or definition for r z or xyz mesh dump number of data For mesh reg the information is dumped on the file If dump is negative data is written by ascii if positive by binary next line data sequence define the data sequence gslat 1 default 0 1 show lattice boundary in gshow 0 no 611 T Time section 167 In t time tally you can use the dump option only with output cutoff If the dump option is set the meshes of e type and t type have only the meaning of the maximum and minimum values and unit is set to be 1 When you use this dump parameter axis and file are restricted to one axis and one file and unit is always 1 The dumped data are written on a file named where indicates the file name specified by filez The normal output of the tally is written on From this file you can get the information on the total normalization factor To do so you had better set one mesh for e type a type and t type In the former version of PHITS before 2 66 the normal output was written on a configuration file cfg and the dumped data were written on By this dump option you can create similar files to ncut gcut and pcut files for the sequential calculations of the other transport code 168 6 12 T Star section 6 TALLY INPUT
137. ctrons and positions vary with their cut off energies The energies are conserved in an event induced by photon atomic interactions such as the photo electric effect e A new tally t dchain was implemented to generate input files of DCHAIN SP which can calculate the time dependence of activation during and after irradiations Please see Sec in detail e Macro bodies of Right Elliptical Cylinder REC Truncated Right angle Cone TRC Ellipsoid ELL and Wedge WED are implemented From ver 2 50 the following functions are implemented e The procedure for calculating statistical uncertainties was revised The function to restart the PHITS calcu lation based the tally results obtained by past PuiTs simulations was implemented in order to increase the history number when the number is not enough Please see Sec in more detail This improvement was performed by Mr Daichi Obinata of Fujitsu Systems East Limited and was supported by Center for Computational Science amp e Systems Japan Atomic Energy Agency JAEA 1 2 Development members 5 The shared memory parallel computing using OpenMP architecture became available in PHiTs though some restrictions still remain see Sec 11 2 For this purpose we drastically revised the source code of PuiTs and old Fortran compilers such as 77 and g77 cannot be used for compiling PuiTs anymore See Sec D 4 in detail This work was supported by Next Generation Integrated Simulation of Living Matt
138. current by surface crossing omni means the energy integrated of curr omni forward current by surface crossing ob curr omni backward current by surface crossing a curr angle mesh current by surface crossing angle mesh omni current by surface crossing x txt omissible x axis title y txt omissible y axis title z txt omissible 7 axis title gshow 8 default 1 2 3 4 When mesh xyz axis xy yz xz region border 1 material name 2 region name 3 and LAT number 4 are plotted by the option ginfo 0 default No geometry check in the case of gshow gt 0 1 Check geometry and draw its two dimensional view with error information 2 Check geometry draw its two dimensional view and outputting a geometry error file err resol 1 default The option multiplies region line resolution by resol times with gshow option width 8 5 default The option defines the line thickness for gshow option epsout default 1 If epsout is set to 1 results are plotted into eps files This eps file name is named by replacing the extension into ctmin i omissible D 9999 minimum value for i th counter ctmax i omissible D 9999 maximum value for i th counter trcl omissible coordinate transformation number or definition for r z or xyz mesh dump number of data For mesh reg the information is dumped on the file If dump is negative data is written by ascii if positive by binary next line
139. d absorption If it is not absorbed then the particle is made decayed KUROTAMA model gives reaction cross sections of nucleon nucleus and nucleus nucleus for wide incident energy region See the document dbelow for detail You have to refer this document when you use the results obtained by the KUROTAMA model in your publications Cross sections of the muon induced nuclear reaction depend on emumin If you change emumin values of the cross sections also change in the whole energy range 8 K lida A Kohama and Oyamatsu J Phys Soc Japan 76 044201 2007 42 Parameters section 4 2 7 Model option 3 Table 4 8 parameter 8 parameter value explanation idwba D 0 Option for DWBA spectra 0 without discrete spectra of DWBA 1 with discrete spectra of DWBA gravx D 0 x component of gravity direction gravy D 0 y component of gravity direction gravz D 8 z component of gravity direction ndedx D 2 option for dE dx of charged particle and nucleus 0 SPAR for nucleus NMTC for the others ATIMA for nucleus and proton NMTC for the others MA SPAR for nucleus proton pion and muon NMTC for the others ih20 D 1 Water only for H2O Ionization Potential option for ATIMA lt 0 default 75 eV gt 0 Ionization Potential for water eV nspred D 0 Option for Coulomb diffusion angle straggling 0 without Coulomb diffusion 1 with Coulomb diffusion by the NMTC original model 2 with Co
140. d region but also in the material where the normal reaction can be occurred Z axis is assumed to be the center of the magnetic field The direction of the magnetic field is positive direction of y axis for dipole i e the positive charge particle is bent to positive direction of x axis when it goes to positive direction of z axis For quadrupole the positive particle is converged in x axis diverged in y axis when it goes to positive direction of z axis You need the coordinate transformation by trc1 for different geometrical situation When you specify charge number of the projectile particle with izst in source section the motion of the particle with the number in the magnetic field is described Using izst Pa Ts can simulate the motion of the particle with charge states The charge number defined with izst doesn t change while the particle moves It should be noted that particles produced from nuclear reactions are not affected by the value of izst the charge of the produced particle is given as its atomic number 415 Magnetic Field section 105 4 15 2 Neutron The definition of the magnetic field for neutron is almost the same as for charged particles Here we describe the detail of the magnetic field for neutron Magnetic Field reg typ gap mgf trcl polar time 1 68 0 00000 35000 09 3 non non 2 61 0 00000 35000 0 1 1 non 3 106 5 00000 7130 0 9 0 non 4 104 0 00000 3 5 9 non 5 0 5 102 0 00000 0 20 9 non non 6 101 3 00000 71
141. de dede dede de ee dee dee de e de de de de de dede dede de ee eee dee ede e de de dede de dede de dede kk kkk kek eee 6 7 parameter mdas 120000000 8 parameter kvlmax 3000 9 parameter kvmmax 1000000 18 parameter itlmax 68 11 parameter inevt 78 12 parameter isrc 50 13 parameter latmax 25000000 14 15 common mdasa das mdas 16 common mdasb mmmax 17 18 19 20 mdas total memory 8 byte 21 mmmax maximum number of total array 2d 225 2 s 23 kvlmax maximum number of regions cell and material 24 kvmmax maximum number of id for regions cel and material 25 2d 26 itlmax number of maximum tally entry 275 inevt number of collision type for summary 28 isrc number of multi source 29 latmax maximum number of lattice in a cell 1 i 30 E UJ 12 3 INPUT FILE 3 Input File PuiTs input consists of some sections as listed in Table B I and 3 2 Each sections begins from a Section Name You can put maximum 4 blanks between the line head and the declaration of Section Name otherwise more than 4 blanks Section Name is not recognized as a beginning of a section and the following part is regarded as items of the previous section 3 1 Sections Table 3 1 and 3 2 shows the various sections used in P Ts Table 3 1 Sections 1
142. de dede eee ede de e de dede dede dede dede de dede eee ee dede de dede de dede dede dede 51 implicit real 8 a h o z 53 parameter pi 3 141592653589793d0 43 Source section 54 55 56 57 58 59 68 61 62 63 64 65 66 67 68 69 78 71 72 73 74 75 76 77 78 79 88 81 82 83 84 85 86 87 88 89 98 91 92 93 94 0000000 data ifirst 9 save ifirst character filenm 50 if ifirst eq 0 then filenm input dat inquire file filenm exist exex if exex eqv false then write file does not exist gt filenm call parastop 887 end if open 71 file file i status old close 71 ifirst 1 end if example for 3 GeV proton with z direction x 0 0 y 0 0 z 0 0 0 0 0 1 3000 0 wt 1 0 time 0 9 name 1 kf 2212 nci 0 nc2 0 nc3 0 sx 0 d0 sy 0 d0 sz 0 d0 return end 59 60 4 SECTIONS FORMAT 4 3 15 Definition for energy distribution In the energy distributed source type s type 4 5 6 8 10 14 and 16 or s type 17 100 with e type parameter energy distribution parameters are required as shown below For d t and nucleus this energy is expressed in units of MeV nucleon For e type 1 4 11 14 the source intensity in each energy bin should be given in the energy integrated value For e type 21 24 31 34 you should give the source intensity in each energy bin
143. ded into two particles One has a weight by penetration probability x its weight this particle pass through to the next region The other has a weight of 1 penetration probability x its weight and it is forced to collide with a target in the region The collide position is decided by cross sections and random number Regions and factors for the forced collisions can be defined in this section Non defined regions are set factor zero Maximum 6 forced collisions sections are allowed to be defined in a input file Forced Collisions part proton neutron reg fcl 1 1 000000 11 0 500000 2 5 89 0 200000 C 11 12 15 0 300000 6 lt 10 1 O lt u 3 0 500000 You set particle as part in the first line The default is part all part is the same format as in tally definition If you want to replace the order of region number reg and fcl you can set as fcl reg You can use the skip operator non Even if you use GG you should write the symbol not ce11 but reg here You can use the format 2 5 8 9 and you can use the lattice and universe style as C 6 lt 10 1 8 0 lt u 3 But you need to close a value by C ifitis not a single numeric value By using this format you can set different forced collision factor for each lattice If the same cell is re defined the value which is defined at first is used The forced collision factor fcl means 0 no forced collision gt 1
144. deposition energies are double counted 1 calculating by ionization loss electron and positron transports are required ctmin i omissible D 9999 minimum value for i th counter ctmax i omissible D 9999 maximum value for i th counter trcl omissible coordinate transformation number or definition for r z or xyz mesh gslat 1 default 0 1 show lattice boundary in gshow 0 no epsout electron When you set unit 6 you can obtain results in the unit of Gy source When you set mesh reg you should define volumes of each cells in volume section or by setting volume parameter of the t heat section Because absorbed dose is intensive variable PuiTS does not output sum over in output files for unit 0 It should be noted that when a region includes more than two materials dose in the region does not equal to average value of the region For example when two material with masses amp Mo and absorb energies E amp E respectively PHiTS gives Da a in this tally though its average dose is ee 144 6 TALLY INPUT FORMAT 6 4 T Deposit section This tally is very similar to t heat and scores dose and deposit energy distributions The difference from t heat is that this tally only counts an energy loss of charged particles and nuclei Thus you must use the event generator mode e mode 1 if you would like to transport low energy neutrons In this tally you can
145. distribution MeV D 0 generation option for 0 p i 1 for all i is assumed without the following data for 1 p 1 must be given from the next line by the format as p i i 1 ne 63 64 4 SECTIONS FORMAT Table 4 44 parameters for source energy distribution 5 parameter explanation e type 5 15 f x Differential spectrum dy dE i is given by f x For 15 case energy is given by wave length A Any analytical function of x FoRTRAN style X denotes energy MeV u One can use intrinsic functions and constants C e g f x exp cl x 2 nm number of energy group If it is given by positive number linear interpolation is assumed in a bin If negative logarithmic interpolation is assumed in a bin Integrated number of source particles generated in each cell is proportional to f x 2 minimum cut off for energy distribution MeV maximum cut off for energy distribution MeV e type 6 16 You can specify the same energy distribution as is the case of e type 5 15 Unlike e type 5 15 the number of source particle generated in each bin is the same for all energy bin but integrated values of the weight of source particles are adjusted to be proportional to f x You can also change the number of source particles generated in each bin by specifing p i f x For 16 case energy is given by wave length A Any analytical functio
146. due to the competition of accessing the shared memories This disadvantage becomes very important for calculations frequently updating memories such as those using the t sed tally 11 1 Distributed memory parallel computing 11 1 1 How to execute The PxiTs calculation using the distributed memory parallel computing with MPI protocol can be executed by the following command mpirun np 8 phits lin exe where phits_lin exe indicates the Pui Ts executable file name The number of PE Processing Element should be set after np You can send this command using the parallel computing submission protocol such as qsub In this case the name of the PuiTS input file should be written in a text file named phits in whose 1st line is file input file name where input file name is the name of the 75 input file This rule is only effective for the distributed memory parallel computing You can also write file phits in at the Ist line and add the contents of input file after the 2nd line of phits in Please see Sec in more detail 11 1 2 Adjustment of maxcas and maxbch In the distributed memory parallel computing jobs are distributed to each CPU core in unit of batch Hence the number of batch maxbch should be a multiple of PE 1 one of PEs is used for control If not PaiTs automatically changes maxbch to be a multiple of PE 1 and adjusts the number of history per batch maxcas to make the total h
147. e reg name size 1 cover 1 2 body 9 5 3 cell 2 2 4 cell 3 2 5 8 tube 3 If you want to replace the order of region number reg region name name and font size size set as reg size name You can use the skip operator non At least one of name and size must be defined If nothing is defined it is assumed to be default You can use the format 4 7 4 7 9 10 format can not be used If you need to use blanks in the name definition the name must be closed by as the example Therefore you cannot use and in the name definition If you want to use and you should write V C and D respectively The maximum number of characters of a name that you can define is 30 You can specify a font size as a relative value to the default size 4 19 Mat Name Color section 109 4 19 Mat Name Color section Material names size and colors for graphical output by gshow and 3dshow tallies are defined in this section By default the name is set as material number and the color is set automatically Mat Name Color mat name size color 0 void 1 lightgray 1 air 9 5 yellowgreen 2 mat 2 2 orangeyellow 3 mat 3 2 0 067 0 600 1 00 4 7 Fe 3 mossgreen If you want to replace the order of material number mat name size and color set as mat color size name You can use the skip operator non You must define at least one parameter in name and
148. e na Number of angular group Data must be given from the next line by the format as 1 1 1 1 1 a type 4 14 You can specify the same angular distribution as is case of a type 1 11 Unlike a type 1 11 the distribution is described by giving data set of angle bins a i and weights of the source particle w i by hand The number of source particles generated in each bin is the same for all angle bin but integrated values of the weight of source particles are adjusted to be proportional to w i You can also change the number of source particles generated in each bin by specifing q i For 4 case angle is given by cosine for 14 case given by degree na Number of angular group Data must be given from the next line by the format as aCi wCi i 1 na 1 In default q type 0 equal number of particle is generated in each cell The integrated number of source particles generated in each bin is proportional to q i q type 9 1 D 0 generation option for 0 q i 1 for all i is assumed without the following data for 1 qG must be given from the next line by the format as q i i 1 na 66 4 SECTIONS FORMAT Table 4 46 parameters for source angular distribution 2 parameter explanation a type 5 15 Angular distribution dg d 2 i is given by g x For 5 case angle is given by cosine for 15
149. e by utilizing the t cross tally Multiplying the flux by a cross section in the unit of cm of the detector you can estimate the number of counts in the response 138 6 TALLY INPUT FORMAT Table 6 3 t cross parameter 1 name value explanation mesh reg r z xyz geometry mesh you need geometry mesh subsection below this option part all default maximum 6 particles in a t cross particle name e type 1 2 3 4 5 energy mesh You need energy mesh subsection below this option a type 1 2 1 2 angle mesh 1 2 cos 1 2 degree The option is required You need angle mesh subsection below this option for a curr and oa curr t type 1 2 3 4 5 time mesh omissible You need time mesh subsection below this option unit 1 2 3 4 5 6 1 1 em source 2 1 cm MeV source 3 1 cm Lethargy source 4 1 cm sr source 5 1 cm MeV sr source 6 1 cm Lethargy sr source 11 12 13 14 15 16 11 1 cm nsec source 12 1 cm MeV nsec source 13 1 cm Lethargy nsec source 14 1 cm sr nsec source 15 1 cm MeV sr nsec source 16 1 em Lethargy sr nsec source axis eng reg y Z x axis value of output data cos the t angle cos the and time t mesh Xy 2 dimensional There may be cases where results of tally are not correct when a surface of mesh in r z or xyz agrees with that of the defined cell You can obtain current for specified ang
150. e input echo volmat omissible D 9 The option corrects a volume value for each mesh when material is defined by xyz mesh 0 means no correction Value of volmat means the number of scans for one side of xyz mesh epsout 8 default 1 If epsout is set to 1 results are plotted into eps files This eps file is named by replacing the extension into ctmin i omissible D 9999 minimum value for i th counter ctmax i omissible D 9999 maximum value for i th counter trcl omissible coordinate transformation number or definition for r z or xyz mesh gslat 1 default 0 1 show lattice boundary in gshow 0 no 611 T Time section 6 11 Using this tally we can get information on the number of particles of energy cut off escape and decay in the time mesh nsec We can also obtain energy spectra of these particles Especially this is the only tally to give energy spectra of the particles which can not be transported in since they are assumed as cut off particles T Tim e section in the code Table 6 29 t time parameter 1 name value explanation mesh reg r z Xyz geometry mesh you need geometry mesh subsection below this option part all default maximum 6 particles in a t time particle name material omissible You can specify materials for scoring all all default same as no definition next line number of materia
151. e maximum number of element can be used in one material is limited to 50 If this value is too small or too large due to memory problem change MXMED parameter in src include egs5_h f and re compile PHITS When you use EGSS the default values of the minimum and maximum energies for electron positron and photon transports are changed to emin 12 13 0 1 emin 14 0 001 and dmax 12 14 1000 0 You can also change these values by explicitly setting these parameters Note that the default values of several EGS5 parameters are different from those employed in the original EGS5 code t track and t cross tallies with setting axis eng may give unnatural energy distribution This is due to transport algorithm of EGS5 and is not error In this case set large mesh size for the energy From ver 2 76 photo nuclear reaction can be considered in using EGS5 Therefore an input file with negs 1 and ipnint 1 gives a different result from that calculated by the previous version of PHITS 10 Hirayama et al SLAC R 730 2005 and KEK Report 2005 8 2005 42 Parameters section Table 4 21 parameter 20 parameter value explanation incohr D 1 Option for incoherent scattering function 0 Do not use incoherent scattering function for Compton scattering 1 Use incoherent scattering function for Compton scattering ibound automatically becomes 1 iprofr D 1 Option for Doppler broadening of Compton s
152. e number of source particles generated in each bin by specifing p i For 34 case energy is given by wave length A Number of energy group If it is given by positive number source particles are generated so that the energy differential fluxes in the unit of 1 MeV become constant in each bin On the other hand if ne is negative the fluxes in the unit of 1 Lethargy become constant in each bin Data must be given from the next line by the format as CeCi wCi i 1 ne 1 In default p type 0 equal number of particle is generated in each cell The integrated number of source particles generated in each bin is proportional to p i p type 0 1 D 0 generation option for 0 1 1 for all i is assumed without the following data for 1 p 1 must be given from the next line by the format as p i i 1 ne 61 62 4 SECTIONS FORMAT Table 4 42 parameters for source energy distribution 3 parameter explanation e type 8 18 You can specify any energy distribution by giving data set of energy points e i and probabilities of the particle generation w i by hand The number of the particle generation at the point is proportional to w i and the specified energy distribution is statistically described For 18 case energy is given by wave length ne Number of energy points Data must be given from the next line by the format as eG wG i 1 ne
153. e parameter can be omissible Table 4 31 parameters for sphere and spherical shell source s type 9 10 sphere and spherical shell source x0 D 0 0 x coordinate of sphere center cm D 0 0 y coordinate of sphere center cm z D 0 0 z coordinate of sphere center cm rl inside radius cm If r1 0 sphere source r2 outside radius cm dir direction dir 1 0 outgoing from the center with normal line direction dir 1 0 inverse direction with dir 1 0 dir all isotropic dir all inverse direction against dir 1 0 and with cosine distribution This is used for volume and area calculation with cos bias Dir iso uniform distribution on a circle of radius r2 on a spherical shell of radius r1 with the direction toward the center of the sphere In the case of r1 r2 the result is almost the same as dir all but an effect of the weight on it is not included Therefore using the condition you can obtain the variance of deposition energies on the t deposit tally with output deposit projectile energy s type 9 MeV When you use the source type s type 9 for volume and area calculation you should set as dir all r1 r2 And dir iso also gives the same result Figure 4 3 Schematic image of the source in the case of dir iso 43 Source section 53 4 3 10 s type 11 This is a uniform distribution source in a phase space which is vertical with beam direction P
154. e threshold energy for each region in the delta ray section you can explicitly transport rays above the threshold energy 1 2 Development members Koji Niita Research Organization for Information Science amp Technology RIST Norihiro Matsuda Shintaro Hashimoto Yosuke Iwamoto Tatsuhiko Sato Takuya Furuta Tatsuhiko Ogawa Shinichiro Abe Hiroshi Nakashima Tokio Fukahori Keisuke Okumura and Tetsuya Kai Japan Atomic Energy Agency JAEA Hiroshi Iwase High Energy Accelerator Research Organization KEK 6 1 INTRODUCTION Satoshi Chiba Tokyo Institute of Technology TITech Lembit Sihver Chalmers University Sweden The following members also contributed to the development of PuiTS Hiroshi Takada Shin ichro Meigo Makoto Teshigawara Fujio Maekawa Masahide Harada Yujiro Ikeda and Yukio Sakamoto Shusaku Noda Japan Atomic Energy Agency JAEA Takashi Nakamura Tohoku University Davide Mancusi Chalmers University Sweden 1 3 Reference of PHITS Please refer the following document in context of using any version of PHITS e T Sato K Niita N Matsuda S Hashimoto Y Iwamoto S Noda T Ogawa H Iwase H Nakashima T Fukahori Okumura T Kai S Chiba T Furuta and L Sihver Particle and Heavy Ion Transport Code System PHITS Version 2 52 J Nucl Sci Technol 50 9 913 923 2013 This is an open access article and you can download it from http dx doi org 10 1080 00223131 2
155. e with given value or takes larger value with small excess as possible It is noted that you can use only 1 2 1 2 mesh types in a type definition Each mesh type format is shown in followings 5 6 2 e type 1 When you use e type 1 set number of group then numerical data as e type 1 ne number of group data 1 data 2 data 3 data 4 data 5 data 6 data 7 data 8 data ne4 I You can use multi lines without any symbols for line connection 5 6 Mesh definition 123 5 6 3 e type 2 3 When you use e type 2 3 set number of group minimum value and maximum value as e type 2 3 ne number of group emin minimum value emax maximum value 5 6 4 e type 4 When you use e type 4 set mesh width minimum value and maximum value as e type 4 edel width of mesh emin minimum value emax maximum value 5 6 5 e type 5 When you use e type 5 set mesh width minimum value and maximum value as e type 5 edel log width of mesh emin minimum value emax maximum value In the case mesh width is for log scale i e edel log Mj 124 5 COMMON PARAMETERS FOR TALLIES 5 7 Other tally definitions 5 7 1 Particle definition You can define particles as proton neutron pion 3112 208Pb or part proton part neutron part part 3112 part 2
156. ecay of the particle as a process in this category The total reaction cross section or the life time of the particle is an essential quantity in the determination of the mean free path of the transport particle According to the mean free path PuiTs chooses the next collision point using the Monte Carlo method To generate the secondary particles of the collision we need the information on the final states of the collision For neutron induced reactions in low energy region PHITS employs the cross sections from Evaluated Nuclear Data libraries For high energy neutrons and other particles we have incorporated two models JAM and JOMD to simulate the particle induced reactions up to 200 GeV and the nucleus nucleus collisions respectively Recently PuiTs introduces an event generator for particle transport parts in the low energy region Thus PuiTs was completely rewritten for the introduction of the event generator for neutron induced reactions in energy region less than 20 MeV Furthermore several new tallis were incorporated for estimation of the relative biological effects This report includes descriptions on new features and functions introduced into the code For examples GG geometry parallelization DPA tally neutron photon and electron transportation and detailed descriptions how to setup the geometry as well In order to keep comprehensive descriptions as the manual of PuiTS this report includes description on some parts of the NMTC JA
157. ed as the universe 1 Figure 4 19 shows the result of this example One can see that some prisms near edges of the 1st cell which is defined as a 12 cm cube are only partly used Directions of the lattice coordinate shown in the right panel depend on the order of the surface number written in the cell definition When you specify any cell using mesh reg in tally sections you can use the lattice and universe styles as 201 lt 101 2 0 0 lt 1 where the lattice coordinate is represented by s t u See Sec 5 1 2 for this format as well You can see lattice coordinates by the t gshow tally with output 7 or 8 10 3 2 water x cm 5 10 10 5 0 5 10 z cm Figure 4 19 Result of the cell section example 7 in 3D left and 2D right images 45 Cell section 85 4 5 5 Repeated structures You can use some simple procedures in to make repeated structures where the same or similar units are put repeatedly Using a lattice parameter explained in Sec is one of them and another is the LIKE BUT cell parameter format LIKE n BUT cell parameter Using this format you can make a little different cell from original one Only elements corresponding to cell parameters written after BUT are different from the n cell Cell parameters that can be used in this format are shown in Table 4 50 In the following example two cell parameters TRCL and MAT are used List 4 15
158. ee dom D 0 0 solid angle degree 1 cos bias distribution projectile energy s type 18 MeV u 43 Source section 55 4 3 13 Reading dump file In this source type the data of the dump file is read in as source Parameters for the type 17 are shown below The order of parameters is free If a parameter has a default value D the parameter can be omissible The dump file is rewinded and re used from the first data again if all of source in the dump file is read before the calculation finishes Table 4 36 parameters for dump file source s type 17 reading dump file file dump filename with full pathname dump number of dump data if it is negative data is written by Ascii next line identification of dump data omissible If below parameters are specified these values have priority over the dump data If the dump data does not include the following data one should specify the parameters minimum x coordinate cm 1 maximum x coordinate cm minimum y coordinate cm 1 maximum y coordinate cm 20 minimum z coordinate cm 21 maximum z coordinate cm SX D 0 x component of spin sy D 0 y component of spin SZ D 0 z component of spin dir direction cosine from z axis If you set all isotropic If you set data a type subsection is necessary phi Dznone random azimuthal angle degree dom D 0 0 solid angle degree
159. efinition t product Produced particle tally definition t dpa DPA tally definition t let LET tally definition t sed SED tally definition t time Time tally definition t star Star density tally definition t dchain Dchain tally definition t userdefined User defined tally definition t gshow Region surface display definition for graphical plot t rshow Physical quantity region display definition for graphical plot t 3dshow 3D graphical geometry plot definition Common parameters used in these tallies are described below 5 1 Geometrical mesh In the tallies shown by Table 5 1 GG region mesh reg r z scoring mesh r z and xyz scoring mesh xyz can be used for geometrical mesh of tallying area You can choose one mesh from mesh reg r z xyz 5 11 Region mesh The region mesh defined by the region number or the cell number can be written by mesh reg reg 12345 19 11 50 each region number or cell number is separated by blank If you want to combine some regions use The following format can be used for defining sequential region numbers 118 5 COMMON PARAMETERS FOR TALLIES mesh reg reg 1 5 10 11 C6 lt 10 1 9 0 lt u 3 In the format n1 n2 nl is smaller than n2 you can specify regions from n1 to n2 You can t specify like C nl n2 StylesC andC all canbeused but can
160. electron and p i 5 0 is positron 197 10 Region error check When you make a complex geometry it is difficult to set up the geometry without any mistakes such as double defined and undefined regions Thus a function for automatically detecting double defined or undefined regions was implemented after version 2 67 This geometry check function works when you specify a tally for generating the two dimensional view of your geometry namely t gshow t rshow and other tallies with setting axis Xy yz or xz and gshow icnt1 8 or rshow icnt1 19 options A parameter ginfo assigned to each tally controls this geometry check function ginfo 9 for no geometry check ginfo 1 for checking geometry and drawing its two dimensional view with error information see Fig 10 1 and ginfo 2 for checking geometry drawing its two dimensional view and outputting a geometry error file that specifies the xyz coordinates of the error location The default value of ginfo for tallies depicting the two dimensional geometry is 2 Figure 10 1 shows an example of the two dimensional view with geometry errors Double defined regions are painted in black and undefined regions are in purple When undefined region is detected its surrounding regions may disappear from the figure no 2 2 2204E 16 20 Water pj 0 EN Copper undefined position E Wy 10 20 10 0 10 20 30 z cm Figure 10 1
161. er Strategic Programs for R amp D of RIKEN and RIKEN Special Postdoctoral Researchers SPDR Program For this improvement we used K computer and RIKEN Integrated Cluster of Clusters RICC The cross section data for photo nuclear reaction was revised based on JENDL Photonuclear Data File 2004 JENDL PD 2004 It should be noted that the current version of PaiTs can handle only giant resonances among the photo nuclear reaction mechanisms Therefore the accuracy for calculating higher energy photo nuclear reactions above 20 MeV is not good The Statistical Multi fragmentation Model SMM was implemented in the statistical decay of highly excited residual nuclei Owing to this implementation the accuracy of calculating the production cross sections of light and medium heavy fragments in heavy ion collisions was improved Intra Nuclear Cascade of Li ge INCL was implemented and employed as the default model for simulating nuclear reactions induced by neutrons protons pions deuterons tritons 3He and a particles at intermediate energies This improvement was supported by Dr Joseph Cugnon of University of Li ge and Dr Davide Mancusi Dr Alain Boudard Dr Jean Christophe David and Dr Sylvie Leray of CEA Saclay under collaboration between CEA Saclay and JAEA KUROTAMA model which gives reaction cross sections of nucleon nucleus and nucleus nucleus was im plemented This improvement was supported by Dr Akihisa Kohama of RIKEN Dr Kei
162. erical shell source is shown below List 7 1 Source example for volume and area calculation 1 Source 2 s type 9 3 proj proton 4 500 0 5 0 0 6 y8 0 0 7 20 30 0 8 rl 18 9 r2 18 10 dir all 11 totfact 18 2 pi In this example a sphere with the center 0 0 30 and radius 18 cm is defined Decide the center and radius in which an interest region or crossing surface is included in the sphere You can set any projectiles and energies List 7 2 Tally example for volume calculation 1 T Track 2 mesh reg 3 reg 12345 4 e type 2 5 emin 0 B emax 1000 0 E ne 1 8 axis reg 9 unit 4 10 file volume dat A tally example for volume calculation is shown above As the example define an interest region set 1 to a group energy region including the source energy set the unit 4 In the case the volume input is set 1 automatically because of unit 4 so you do not need the volume section here You can obtain a volume value by this tally and you can used it as input data for volume definition in your actual calculation Furthermore you can calculate the mass volumexdensity in the region if you use multiplier in t track Actually you add the following lines to the above t track section multiplier all part all emax 1 0e10 mat msetl all 1 0 120 Here multiplier 120 is a function to multiply the track length by the mater
163. error 8 termination by weight cut off 9 termination by time cut off 10 geometry boundary crossing 11 termination by energy cut off 12 termination by escape or leakage 13 nx reaction 14 nnmx reaction 15 sequential transport only for tally 2 npe me These are the number of used PEs Processor Elements and ID number of each processor respectively in the distributed memory parallel computing 3 ipomp npomp These are ID number of each core and the total number of used cores respectively in the shared memory parallel computing 176 4 iusrtally 6 TALLY INPUT FORMAT This is a parameter to control whether subroutine usrtally is used or not If t userdefined is defined in an input file this parameter is set to be 1 5 iudtf 50 These are device numbers of output files defined with file in t userdefined its device number is iudtf 1 151 6 udtpara 0 9 These correspond to parameters defined with udtparai i udtpara0 7 NOCAS NOBCH RCASC RSOUIN For example if there is the earliest file defined 0 9 For example udtpara 0 equals to NOCAS current history number in this batch NOBCH current batch number RCASC real number of NOCAS maxcas NOBCH 1 RSOUIN sum of the weight of source particle 8 NO IDMN ITYP KTYP JTYP MTYP RTYP OLDWT NO cascade id in this history IDMN material id ITYP particle type KTYP particle kf code JTYP charge number of the parti
164. es in the energy region emin energy dmax If you set emin gt dmax any libraries are not used The maximum energies for proton neutron photon and electron are 3 GeV 3 GeV 100 GeV and 10 GeV respectively in this version We create the range table of charge particles in esmin lt energy esmax If you want to use much larger energy you should set esmax 42 Parameters section 23 Table 4 4 parameter 4 parameter value explanation ejamnu D 20 switching energy of nucleon nucleus reaction calculation from Bertini or QMD to JAM model MeV ejampi D 20 switching energy of pion nucleus reaction calculation from Bertini to JAM model MeV eisobar D 0 0 maximum energy MeV of isobar calculation when isobar is defined isobar 1 eqmdnu D 20 switching energy of nucleon nucleus reaction calculation from Bertini to QMD model MeV eqmdmin D 10 0 minimum energy of QMD calculation MeV nucleon ejamqmd D 3500 0 switching energy from JOMD to JAMQMD MeV nucleon inclg D 1 Control parameter for use of INCL 0 Not use of INCL 1 Use of INCL in a proton neutron pion d t He induced reaction 2 Use of INCL in a proton neutron or pion induced reaction einclmin D 1 0 Minimum energy of INCL calculation MeV u einclmax D 3000 0 Maximum energy of INCL calculation MeV u incelf D 0 Control parameter for use of INC ELF 0 Not use of INC ELF 1 Use
165. es transparent and you can see inside of the body In the last example add reg 3 lt 6 0 0 8 matinbox 1 6 Regions defined by reg 3 lt 6 8 0 become transparent and material number 6 becomes visible You can display any complex structures as you like combining with these options 190 7 VOLUME AND AREA CALCULATION BY TALLY FUNCTION 7 Volume and Area calculation by tally function Sometimes you need to obtain values of region volumes and areas of crossing surface for tally definitions You can obtain these values by using the tally itself by Monte Carlo method In order to calculate volume and area by Monte Carlo method you have to calculate the flux pass through the region or the crossing surface by making use of the spatially uniform trajectories You can set such source by setting s type 9 with 1 2 and dir all in source section You have to set the radius r1 of the sphere to include the region or surface that you want to calculate its volume or area In addition set an area of the source to totfact When you obtain the volume you should set t track tally with mesh reg and unit 4 When you obtain the area you should set t cross tally with mesh reg unit 1 and output flux Using the above setting you can perform Monte Carlo integration by executing PHITS with icntl 5 Please see a lecture note phits lecO3 en ppt in the folder phits lecture lec03 in more detail An example using the sph
166. esults of the t track tally When you use this set you have to define multiplier subsections in the t track section For example you can utilize this function for dose estimation using any dose conversion factor Inone multiplier section you can define only one multiplier set The maximum number of the multiplier section defined in an input file is 100 Format of this section is as follows Multiplier number 201 interpolation log ne 10 20 0 2 678 30 0 7 020 50 0 18 50 100 9 24 26 200 0 16 13 500 0 10 51 1000 0 10 55 2000 0 10 98 5000 0 12 10 10000 00 12 45 The ID number of the set is determined by number which must be between 299 and 200 and is used in the t track section You can choose which log log or lin lin as the interpolation method of the given data table by setting interpolation log or lin respectively The number of the energy point is given by ne and data sets for the point and the factor are defined respectively below ne Note that the data of the energy point should be in ascending order When you use the multiplier set defined in this section you have to use multiplier option of the t track section The basic format is given as k where C is a normalization factor and k is the ID number of the set It is noted that k should be negative Format of the multiplier subsection is given as follows multiplier number of material part neutron emax 1
167. etration through matter such as neutrino PuiTS calculation takes time too much If you define part all neutrino is included You must give attention about it Some rules can be used to define an importance of a cell in a repeated structures and lattices For example cells 5 6 and 7 on a bottom level are included by cells 11 12 and 13 on upper level we can define the importance as Importance gt or 1 2 1 3 1 4 11 2 5 4 6 8 Above two definitions give same results but in the latter case the importance for cells 5 6 and 7 are displayed as 1 0 at the importance summary 98 4 SECTIONS FORMAT 4 9 Weight Window section The weight window function can be defined in this section Maximum 6 weight window sections are allowed to be defined in a input file Weight Window part proton neutron eng 5 tim 5 6 00e 7 3 98e 1 1 00e 0 7 00e 0 5 00e 4 reg wwl ww2 ww3 1 0 010000 0 100000 0 001000 11 0 005000 0 050000 0 000300 2 5 89 0 001000 0 010000 0 000100 11 12 15 0 000500 0 005000 0 000030 6 lt 10 1 0 lt 3 0 000010 0 001000 0 000010 ww4 ww5 0 010000 0 100000 0 005000 0 050000 0 001000 0 010000 0 000500 0 005000 0 000010 0 001000 Particle is defined in the first line as part part all means all particles The format to describe particles part is the same format as in tally definition However it can distinguish ityp only each nuc
168. eutron goes into the magnetic field with the spin direction irrespective of the direction of the magnetic field nor polarization 43 Source section 49 4 3 3 Cylinder distribution source Parameters for cylinder source are shown below The order of parameters is free If a parameter has a default value D the parameter can be omissible Table 4 25 parameters for cylinder source s type 1 4 cylinder or circle source x0 D 0 0 x coordinate of center position of cylinder source cm D 0 0 y coordinate of center position of cylinder source cm 20 minimum z of cylinder source cm 21 maximum z of cylinder source cm when z1 z0 circle plane source ro radius of cylinder source when 0 0 0 pencil source cm rl D 0 0 inner radius for inner void of cylinder dir direction cosine of projectile against z axis If you set a11 it is isotropic If you set data a type subsection is necessary phi Dznone random azimuthal angle degree dom D 0 0 solid angle degree 1 cos bias distribution e8 projectile energy s type 1 MeV 4 3 4 Rectangular solid distribution source Parameters for rectangular solid source are shown below The order of parameters is free If a parameter has a default value D the parameter can be omissible Table 4 26 parameters for rectangular solid source s type 2 5 rectangular solid and rectangle source x9 minimum x coordin
169. f energy emin transpt DPA value when charged particles are transported library DPA value from neutron library all add d t and nucleus contributions as PKA with simple factor omissible D 1 0 normalization factor title omissible title angel omissible angel parameters 2d type 1 2 3 4 5 6 7 options for 2 dimensional plot omissible x txt omissible x axis title y txt omissible y axis title z txt omissible Z axis title gshow 9 default 1 2 3 4 When mesh xyz axis xy yz xz region border 1 material name 2 region name 3 and LAT number 4 are plotted by the option rshow 6 default 1 2 3 When mesh reg axis xy yz xz region border 1 material name 2 and region name 3 are plotted by the option You need xyz mesh section below this option ginfo 0 default No geometry check in the case of gshow or rshow gt 0 1 Check geometry and draw its two dimensional view with error information 2 Check geometry draw its two dimensional view and outputting a geometry error file err resol 1 default The option multiplies region line resolution by resol times with gshow or rshow option width 6 5 default The option defines the line thickness for gshow or rshow option volume omissible The option defines volume for each region for reg mesh You need volume definitions below this option Default values are given in input echo in the case of no definition reg vol
170. f momentum of the particle 8 E T X Y Z These mean E energy of the particle at x y z MeV T time of the particle at x y z nsec X Y Z position coordinate of the preceding event point cm 9 EC TC XC YC ZC These mean EC energy of the particle at xc yc zc MeV TC of the particle at xc yc zc nsec XC YC ZC position coordinate of the particle cm 10 SPX SPY SPZ These mean SPX SPY SPZ unit vector of spin direction of the particle 42 11 NZST This is charge state of the particle 12 NCLSTS 4 SECTIONS FORMAT This variable is written only for NCOL 13 14 collision case and means the number of produced particle and nucleus The next data are written for NCLSTS gt 0 case MATHZ MATHN JCOLL KCOLL These mean MATHZ Z number of the mother nucleus MATHN N number of the mother nucleus JCOLL reaction type idl KCOLL reaction type id2 JCOLL and KCOLL indicate the following meaning a Q o nothing happen Hydrogen collisions Particle Decays Elastic collisions High Energy Nuclear collisions Heavy Ion reactions Neutron reactions by data Photon reactions by data Electron reactions by data Proton reactions by data Neutron event mode delta ray production at j KCOLL normal high energy fission high energy absorption low energy n elastic low energy n non elastic low energy n fission low ener
171. file name e g phits264_win exe please don t delete the original one because it will be required when is updated 10 2 INSTALLATION COMPILATION AND EXECUTION OF PHITS 2 6 Compilation of ANGEL AnGzL is a computer program for making graphs in the EPS Enhanced PostScript format using simple input files Namely converts a file written by AvGgL computer language which consists the minimum order to make a figure from numerical data to that by PostScript one which is a page description language created by Adobe Systems AnGgL is included in the sources in other words AwGzL is installed automatically in the PuiTs code But you will need a stand alone ANGgL for off line plotting You can compile the stand alone AwGzgL easily using the make ang file which is included in the source files After modify the make ang execute make f make ang to compile the stand alone ANGzL Please see ANGgL manual in more detail 27 Executable file PuiTs code can be executed on the UNIX system by the following command List 3 1 command line to execute phits100 input dat gt output dat where phits100 is the PuiTs executable file input dat is the input file of the Pa7Ts calculation and output dat is the output file for summary and error messages You can use the same way on the Windows system unless a parameter infl is used When you use other files for the input data
172. fill each unit with any universe which is itself filled with biological matter such as compounds of carbon and water In an example below a 10 cm cube consisting of 2cm cubes voxels of 5 x 5 x 5 125 is described List 4 18 cell section example 11 1 Material 2 mat 1 1H 2 160 1 3 mat 2 Fe 1 4 cell 5 1 0 11 12 13 14 15 16 FILL 1 6 191 20 LAT 1 U 1 7 FILL 2 2 2 2 2 2 8 24 2222 22222 22322 22222 222722 9 222 23322 23432 23322 22222 10 22222 23332 34443 23332 22222 11 22222 22332 23432 22332 22222 12 24 22 2 22222 22322 22222 22222 13 201 0 90 U 2 14 301 2 18 8 90 U 3 15 401 1 1 90 U 4 16 2 1 1 17 Surface 18 11 PX 5 19 12 PX 5 20 13 PY 5 21 14 PY 5 22 15 PZ 5 23 16 PZ 5 24 20 BOX 1 1 1 200 020 8602 25 98 BOX 10 10 10 2000 0200 9 0 20 As a unit of voxel a 2 cm cube is defined in the 24th line Furthermore the 1st cell that is inside of a 10 cm cube has a repeated structure through definition in the 5th line The region of the lattice coordinate space is determined in the 7th line The order of voxel in the 8th 12th lines is as follows 2 2 2 71 2 2 2 2 2 represented by the lattice coordinate 2 in the 8th 12th lines means the universe 2 which is void and 3 and 4 namely the universe 3 and 4 correspond to iron and water respectively Figure 4 23 represents the result of this example that is a distorted
173. fined in a PHITS input file These limitations will be removed in the forthcoming version sumtally subsection should be defined between the lines of sumtally start and sumtally end written in the tally section that outputs one of the summing up tallies The parameters used in sumtally subsection are summarized in Table Table 5 5 Parameters used in sumtally subsection name value description isumtally 1 default 2 Summing up procedure 1 Integration of tally results considering history number of each simulation 2 Sum of tally results weighted by user defined ratios nfile Number Number of summing up files next line filename value Summing up file name weighted value Sum of the weighted values is automatically normalized to sumfactor for isumtally 2 sfile filename Output file name sumfactor Omissible D 1 0 Normalization factor For example if you have two tally results result 1 out and result 2 out that were obtained from maxcas 100 and maxbch 10 and 20 respectively you would like to obtain their summing up results considering their histories you have to write List 5 3 example 1 for isumtally 1 sumtally start isumtally 1 D 1 sumtally option 1 integration 2 weighted sum nfile 2 number of tally files result 1 out 1 0 result 2 out 1 0 sfile result s out file name of output by sumtally option sumfactor 1 0 D 1 0 normali
174. format of ANGEL Thread parallelization is available even using EGS5 i e negs 1 Some bugs related to EGS5 were fixed This improvement was performed by Mr Masaaki Adachi of Research Organization for Information Science amp Technology RIST and was supported by Center for Computational Science amp e Systems Japan Atomic Energy Agency JAEA A new function to combine two or more tally results named sum tally was implemented At this moment this function works only for the results obtained from t track and t deposit See Sec 5 8 in more detail This function was developed by Mr Takamitsu Miura of RIST and was supported by Center for Computational Science amp e Systems JAEA The Kurotama model was revised to be capable of calculating the cross sections over 5 GeV n See this article Min more detail The gamma de excitation data contained in trxcrd dat was incorporated in the source files of PHITS Con sequently ile 14 parameter is not necessary to be specified in PHITS input file even setting e mode gt 1 or igamma gt 1 Some bugs related to JAM and JAMQMD etc were revised From ver 2 73 we fixed a bug producing abnormal nuclei such as di neutron in calculation of nuclear reaction models For Windows an installed executable file of the OpenMP version is available only on 64 bit You can execute PuiTs in single processing on both the 32 bit and 64 bit systems but you cannot do it using OpenMP on 32 bit
175. from Kerma factors with nuclear data For e mode 1 the heat from neutrons is zero but the heat is calculated from energy loss of all charged particles and nuclei The heat from photons is usually obtained also from Kerma factors with nuclear data For electron 1 with electron transport we do not use the Kerma factors of photon but obtain the heat from the energy loss of electrons 141 Table 6 5 t heat parameter 1 number of materials name value explanation mesh reg r z Xyz geometry mesh you need geometry mesh subsection below this option axis reg X y Z r xaxis value of output data Xy YZ XZ TZ 2 dimensional file file name Define file names as same number of axis resfile omissible D file Define a file name of the past tally in the restart calculation Even if several axis parameters were defined you should specify only one resfile material omissible You can specify materials for scoring all all default same as no definition When you set number of materials define these material numbers in the next line You can set number of materials by negative In the case specified materials are not included for scoring next line 258 material numbers output heat total Total deposit energy simple total Total deposit energy ncut gcut pcut Deposit energies of neutrons photons and protons below cut off energy when you set incut 0 igcut gt 0 ipcut 6
176. generally outputted in the column which is placed in the rightmost column of the tally results In the case of 2D plot such as tallies with axis xy or rz errors are output in another file named err where indicates the file name specified in the tally For example when file tally out the name of the error file is tally_err out This error file has the same format of the conventional tally output file Hence you can obtain a graph for the error in 2D plot through a conversion process by ANGzL Note that the true value is not always within the error because calculates the standard deviation or the standard error Furthermore PuiTS does not estimate systematic errors due to the nuclear reaction model When istdev lt 9 the restart calculation mode is activated but if there is no past tally result a new calculation is started with istdev abs istdev namely the batch and history variance modes are selected for istdev 1 and 2 respectively In the case of the restart calculation the variance mode is automatically determined from the past PHiTs calculation You have to set the same tally parameters as written in the past tally results but you can add new tallies in the restart calculation The procedure for the restart calculation is given below 1 Check whether the file specified by resfile in each tally section exists or not The default file name of resfile is that given by file parameter
177. gy n absorption amp b ICLUSTS JCLUSTS QCLUSTS JCOUNT These variables have a array and denote the information on the produced particle and nucleus do i 1 NCLSTS write io ICLUSTS i write io JCLUSTS j i j 0 7 write io QCLUSTS j i j 0 12 write io C JCOUNT j i j 1 3 end do These mean 42 Parameters section ICLUSTS kind of particle 0 nucleus 1 proton 2 neutron 3 pion 4 photon 5 kaon 6 muon 7 others JCLUSTS 1 0 angular momentum proton number 2 neutron number 3 4 status of the particle 0 real lt 0 dead 5 charge number 6 baryon number 7 kfcode QCLUSTS i 1 0 impact parameter 2 py GeV c 3 pz GeV c moro mu Jp m GeV 5 rest mass GeV 6 excitation energy MeV 7 kinetic energy MeV 8 weight 9 time nsec 10 x coordinate cm l y coordinate cm 12 z coordinate cm 44 4 SECTIONS FORMAT 4 2 21 Event Generator Mode For Event Generator mode one should define dmax 2 appropriately since we need the information from the data base as mentioned above In the special statistical decay model we use the detail information on the level structure near the ground state for particle and photon emission For this we need igamma 1 3 We have developed the special statistical decay model based on GEM Then one should need to specify nevap 3 In
178. hared memory parallel computing using OpenMP architecture You can perform the parallel PHiTS calculation using both methods In addition the hybrid of them can be also utilized To execute distributed memory parallel computing you have to install MPI protocol in your computer On the other hand there is no required software for the shared memory parallel computing You have to make each executable file according to the type of the parallel computing See Sec 2 4 in detail In the distributed memory parallel computing jobs are distributed to each CPU core in unit of batch When all jobs assigned to each core are finished the main core gathers their results In this mode all cores individually use the memory equivalent to that used in single processing Thus the total RAM memory in the computer system must be larger than that used for single processing multiplied by the core number Therefore this parallel computing type is not suitable for the calculation requiring a large memory such as that using voxel phantom In the shared memory parallel computing jobs are distributed to each CPU core in the unit of history Then all cores share a large part of memories used in PuiTS except for those defined as thread private variable Therefore the memory required in this parallel computing is almost the same as that in single processing A disadvantage of this parallel computing in comparison to memory distributed one is the slower computational time
179. he detector room we have prepared the following duct source options to reduce the variance of the calculations The beam current transported through the beam line decreases proportional to the inverse square of the distance from the moderator This means that the current crossing the wall of the beam line which is called as wall current at 100 m point is six order of magnitude smaller than that at 1 m point from the source if we assume isotropic distribution of the source direction To reduce this variance we have introduced a special options of the source function in which the wall current of the simulation particles is equalized at any point of the beam line by changing the importance weight of the particles to simulate a real situation of the current inside the beam line We set the duct source options for s type 1 4 2 5 circle and rectangle source by dom 10 The parameters for the duct source options are summarized in Table 4 47 Table 4 47 parameters for duct source options parameter explanation dom 10 specify the duct source dlo starting z position of the beam line from z0 cm dli starting z position of the duct source from 70 cm dl2 ending z position of the duct source from 70 cm dpf portion of pass through particles at 412 drd radius of circle beam line for s type 1 4 cm dxw x size of rectangle beam line for s type 2 5 cm dyw y size of rectangle beam line for s type 2 5 c
180. heck source particles can be tallied by t product zu execute t gshow tally graphical output 8 geometry output of xyz mesh tally with gshow option graphical output 9 execute t rshow tally graphical output 10 geometry output of reg mesh tally with rshow option graphical output 11 execute t 3dshow tally graphical output 12 re calculate from dumpall file dumpall file is specified by file 15 The function of nuclear reaction calculation specified as icntl 1 is under development By setting icnt1 12 175 re calculates whole transport by reading the information from dumpall file which is created by dumpall 1 option The re calculation can describe whole transport events which were calculated before One needs the same input file as used in the previous calculation maxcas and maxbch cannot be changed but are read from the file It is very powerful when you want to calculate different tallies which are not used in the previous calculation However please be careful that the calculation with dumpall 1 may create huge dumpall file This option is only available for GG geometry 20 4 SECTIONS FORMAT 4 2 30 Number of history and Bank Table 4 2 parameter 2 parameter value explanation irskip D20 random number control irskip gt 0 begin calculation after skipping histories by number of irskip for debug irskip 6 begin calculation after skipping random numbers by number of irskip
181. hits c exe phits in output dat See Manual D 7 Executable file section in more detail Q2 4 An error occurred when try to execute 175 on Linux or Unix console but I can execute it on Windows using the same input file A2 4 Many reasons are considered to cause the error but the most probable one is the difference of return code used in Linux or Unix and Windows If you prepare your input file in your Windows computer and transfer to your Linux or Unix system using FTP software you have to check the status of transfer mode i e you have to select ASCII mode in your FTP software Q2 5 Can PuiTS5 be executed on Cygwin A2 5 Yes you can You can find the Cygwin option in makefile of PHiTs 12 3 Questions related to Tally Q3 1 What is the difference between t heat and t deposit tallies A3 1 The values calculated by T Heat includes the deposition energy estimated using the Kerma approxi mation as well as the energy of cutoff neutrons and photons On the other hand the value calculated by T Deposit includes only the deposition energy from charged particles due to their ionization energy loss Thus if you do not employ Event Generator mode in your simulation you have to select T Heat tally T Deposit is useful for calculating deposition energy weighted by user defined function such as Q L relationship for calculating dose equivalent See Manual 6 4 T Deposit section in more detail Q3
182. ial density See 6 T t track section for detail 191 List 7 3 Tally example for area calculation 1 T Cross 2 mesh reg 3i reg 3 4 r in r out area 5 12 C12 1 0000E 00 6 C23 2 3 1 0000E 00 Le C34 3 4 1 0000 00 8 e type 2 9 Q 10 emax 1000 0 11 1 12 axis reg 13 unit 1 14 file area dat A tally example for area calculation is shown above As the example define an interest surface set 1 to a group energy region including the source energy set the unit 1 You can obtain a area value by this tally and you can used it as input data for area definition in your actual calculation 192 8 PROCESSING DUMP FILE 8 Processing dump file You can write down the information on transport particles on dump file by t cross t time t product tallies If you set the dump file as a source you can calculate the sequential transport Furthermore you can get the information which cannot be obtained by the tally functions in PuiTS by processing the dump file To process the dump file however you need to make program to process the dump file In the following we show a program to process the dump file as an example of such program The following program is a simple program which converts the ascii dump file to binary dump file and vice versa The following simple program could help you to make a program to process the dump file The source program dump a f i
183. ic energy of particle MeV 9 wt weight of particle d 18 time initial time of particle ns 11 i name usually 1 for Coulmb spread 12 kf kf code of the particle 13 nci initial value of counter 1 x 14 nc2 initial value of counter 2 15 nc3 initial value of counter 3 E 16 SX Sy SZ Spin components 17 duncnzzlccoecLoco dccolaucllodcdlloz2lloeclcocconllcooeccn2cnatu2lsdcdoosocillzaoc 18 kf code table 19 kf code ityp description 5 20 2212 1 proton d 21 2112 2 neutron 22 211 3 pion i 23 k 111 4 pion 0 24 211 5 pion 25 13 6 muon 26 13 7 muon 2 225 321 8 kaon B 28 311 9 kaon 8 29 321 10 kaon 30 kf code of the other transport particles id 31 12 nu e 32 14 nu mu 33 gt 221 34 331 eta 35 311 kObar 36 2112 nbar t 37 2212 pbar ade 3122 Lanbda 39 3222 Sigma i V E 3212 Sigma T 41 3112 Sigma bi a2 3322 43 3312 1 44 3334 Omega 45 el eee see eee ie seh cee tose ecules 46 E available function for random number T 47 unirn dummy uniform random number from 9 to 1 48 gaurn dummy gaussian random number 49 for exp x 2 2 sig 2 sig 1 0 50 de ve ve de vede de dee ee ede de de de de dede de dede de
184. idual particles 6 5 T Deposit2 section 147 6 5 T Deposit2 section This tally scores deposit energy distribution in two regions and plot the correlation between two deposit ener gies By this one can simulate for an example dE E counters and plot the correlations in 2 dimensional graph In this tally as in the t deposit tally you can multiply any factor as a function of LET dE dx in a certain material to the dose or deposit energy This function is realized by user defined subroutine usrdfnl f and usrdn2 f As examples the default program of usrdfn1 f returns the dose equivalent calculated from deposit energy multiplied with the Q L relationship defined in the ICRP60 while that of usrdfn2 f simply does the energy loss without multiplying any factor You can change and add any factor in this routine In addition using the time mesh with timer section you can simulate a TOF time of flight detector and plot 2 dimensional graph of the correlation between the deposit energy and the TOF Table 6 11 t deposit2 parameters 1 name value explanation mesh reg geometry mesh only reg reg rl r2 Two region numbers should be written part all default maximum 6 particles in a t deposit2 particle name letmat1 omissible material id for LET dE dx of region rl If omitted real material is assumed letmat2 omissible material id for LET d E dx of region r2 If omitted
185. igin crosses screen surface vertically and passes through the view point w mnw Dz100 number of mesh for horizontal direction w mnh Dz100 number of mesh for vertical direction w ang D 0 0 angle of frame degree heaven D y topside direction set x x y y Z Or Z mirror D 0 1 mirror transformation in horizontal direction 184 6 TALLY INPUT FORMAT Polar Eye Point Picture Flame e the e phi e dst Light source Polar 1 u I the l phi l dst Coordinates w mnw X w mnh Pixel 100 x 100 default Origin x0 y0 z0 XY Z coordinates Figure 6 7 3dshow tally origin x0 y0 z0 eye point e the e phi e dst light source 1 the l phi l dst and picture flame w wdt w hgt w dst 617 T 3Dshow section Table 6 39 t 3dshow parameter 2 185 number of materials name value explanation line 9 default 1 When output 1 3 0 material boundary surface boundary 1 material boundary surface boundary region boundary r out D 50000 radius of outer void including view point and light source cm shadow D 0 shadow level 0 no shadow 2 is recommended bright D 0 8 brightness limit 1 max 0 no brightness dark D 0 2 darkness limit 1 no darkness 0 max box D 0 number of penetration box maximum 5 box 10 numbers box definition see below matinbox omissible materials in the box for display all all
186. ils are described in each tally explanation 5 7 8 info definition This option defines whether detailed information is output or not Set 0 or 1 as 5 7 9 title definition This option is for title as title title of the tally It is omissible and in this case default is used 5 7 10 ANGEL parameter definition In order to add ANGgL parameters in tally output define as 5 7 Other tally definitions 127 angel xmin 1 0 ymin 1 3e 8 Defined parameter is converted to the ANGgL format as p xmin 1 0 ymin 1 3e 8 See ANGgL manual for details 5 7 11 2d type definition When you define 2 dimensional output as axis xy you must set this 2d type option as These 2d types give the format of data arrange e 2d type 1 2 3 6 7 Data are written by below format the example is written by Fortran style Cdata ix iy ix 1 nx iy ny 1 1 10 data are written in a line Also a header for the ANGzgL input is inserted The AnGgL header is inserted by 2d type 1 for contour plot 2d type 2 for cluster plot 2d type 3 for color plot 2d type 6 for cluster and contour plot 2d type 7 for color and contour plot e 2d type 4 Data are written by below format do 1 1 do ix 1 nx C x ix data ix iy end do end do 3 data of x ix y iy and data ix iy are written in a line e 2d type 5
187. in the unit of cm of the detector you can estimate the number of counts in the response 134 6 TALLY INPUT FORMAT Table 6 1 t track parameter 1 name value explanation mesh reg r z Xyz geometry mesh you need geometry mesh subsection below this option part all default maximum 6 particles in a t track particle name material omissible You can specify materials for scoring all all default same as no definition number of materials When you set number of materials define these material numbers in the next line You can set number of materials by negative In the case specified materials are not included for scoring next line 258 material numbers e type 1 2 3 4 5 energy mesh You need energy mesh subsection below this option t type 1 2 3 4 5 time mesh omissible You need time mesh subsection below this option unit 1 2 3 4 1 1 cm source 2 1 cm MeV source 3 1 cm Lethargy source 4 cm source 11 12 13 14 11 1 cm nsec source 12 1 cm MeV nsec source 13 1 cm Lethargy nsec source 14 cm nsec source axis eng reg x y Z r xaxis value of output data Xy YZ XZ TZ 2 dimensional t time axis file file name Define file names as same number of axis resfile omissible D file Define a file name of the past tally in the restart calculation Even if several axis parameters were defined you should specify only
188. ion Foricntl 10 PuiTs makes a two dimensional plot for the tallies with reg mesh xy yz zx axis and rshow 1 2 3 In the figure different colors are used for different materials You should check whether regions are correct and a xyz mesh resolution is good or not before long time calculation 5 7 Other tally definitions 129 5 7 14 x txt y txt z txt definition If you want to change x y and z axis titles in the output figure use these option These title can not be defined in the ANGzL parameter X txt x axis title y txt y axis title z txt z axis title 5 7 15 volmat definition The volmat parameter corrects a volume where xyz mesh crosses region boundaries This option is effective in the case that mesh is xyz and the material parameter is defined This corrected volume is calculated by the Monte Carlo method for specified material volmat denotes the number of scanning parallel to x y and z axis respectively for the Monte Carlo calculation So If you set too large volmat the calculation takes long time You need to take care of it If volmat is given by negative value all xyz mesh is scanned If positive value the scanning is not performed when 8 apexes of the mesh are included in the same material 5 7 16 definition If you set epsout 1 output file is treated by AnGgL automatically and an eps file is created This eps file name is named by replacing the extension into eps With
189. ion KEK Tokyo Institute of Technology TITech Chalmers University Sweden Editor of this user s manual from ver 2 30
190. is tally section in this tally section In order to tally the in 66 T Yield section 66 T Yield section 149 T Yield gives information on produced nuclei informations Products by neutrons in the energy below dmax 2 are not scored but scored with e mode 1 number of materials Table 6 13 t yield parameter 1 name value explanation mesh reg r z Xyz geometry mesh you need geometry mesh subsection below this option special D 0 omissible When special 6 nuclear reactions are repeated more than once in order to increase statistics part all default maximum 6 particles in a t yield particle name projectile particle of the reaction material omissible You can specify materials for scoring all all default same as no definition When you set number of materials define these material numbers in the next line You can set number of materials by negative In the case specified materials are not included for scoring number of mother nuclei next line 258 material numbers mother omissible You can specify mother nuclei all all default same with no definition When you set number of mother nuclei define their mothers in the next line You can set number of mothers by negative In this case specified mothers are not included for scoring next line number of nuclei 208Pb Pb next line 208Pb Pb Nucleus if you specify with mass Without mass
191. is used The volume is utilized in the tally sections If you do not set volume it has 1 0 cm volume Volume reg vol 1 1 000000 11 5 000000 2 5 89 2 000000 11 12 15 3 000000 16 6 000000 You can use format 2 5 8 9 foragroup In this case you need to close a value by C if it is not a single numeric value You can not use the lattice and universe style as 6 lt 10 1 9 0 lt u 3 If you want to set cell volume in detail use the volume definition in the tally section If you want to change the order of region number reg and volume vol you can set as vol reg You can use the skip operator non Even if you use GG you should write the symbol not 11 but reg here 100 4 SECTIONS FORMAT 411 Temperature section Free Gas Thermal Temperature MeV for GG cell can be defined in this section This section corresponds to TMP card but you can not set time definition This value can be set in the ce11 section when you use GG If the temperature is double defined temperatures defined in this temperature sections are used If you do not set this the default value is 2 53 x 10 8 Temperature reg tmp 1 1 0 1 e 8 11 5 0 1 8 2 5 89 2 0 1 e 8 C 11 12 15 3 0 1 e 8 16 6 0 1 e 8 You can use the format 2 5 8 9 In this case you need to close a value by C if itis nota single numeric value You can not use the lattice and unive
192. istory number equivalent to that you set in the input file In this case some comments are outputted at the end of the input echo In the case of the restart mode istdev 8 adjustment of maxcas is not performed since it should be set to the same as written in the past tally results 11 1 3 Treatment of abnormal end When PuiTs stops by abnormal end in a PE the PE is removed from operation Finally a total result by remained PE is given as a final result In this case you should pay attention for the ncut file The ncut is incomplete 11 2 Shared memory parallel computing 199 11 1 4 ncut gcut pcut and dumpall file definition in the PHITS For the parallel calculation ncut gcut and pcut can be defined in an input file as normally as file 12 temp ncut dat In 1 PE calculation specified ncut dat is written normally but in multi PE calculation ncut dat is written separately in each node as wk j9999 temp ncut dat where j9999 is your user name which is read in automatically from the environmental variable LOGNAME By default your user name is put in the LOGNAME in the UNIX system Before parallel calculation make j9999 directory under the wk directory for each node If you want to make ncut file in a directory not named by your user name change environmental variable LOGNAME before parallel calculation In the case confirm there exists the directory you specified under the wk inpara igpara and ippara are prepared
193. ith Z axis z D 0 D SO sphere origin is center y g Rz0 R S multi purpose x Xy y y z z R 0 XyzR SX center on X axis y 02 0 XR SY center on Y axis 2 02 0 0 R SZ center on Z axis xy 2 0 zR C X cylinder parallel with X axis 902 2 2 R 0 yzR C Y parallel with Y axis 2 2 2 2 0 XZR C Z parallel with Z axis x 2 2 0 XyR CX on X axis y 2 R 0 R CY on Y axis 2 02 0 R CZ on Z axis 0 0 R K X cone parallel with X axis 2 2 tx X 0 1 K Y parallel with Y axis v x Xx z zp t y y 20 1 K Z parallel with Z axis X4x xy y yyy tz 220 XyzP 1 KX on X axis vy 2 1 x 0 KP 1 KY on Y axis Vx 2 ty j 0 y 1 KZ on Z axis yX y 2 0 1 1 is only needed for 1 sheet code SQ ellipse parallel with A x X BO Y C z zy ABCDE hyperboloid X Y 2D x 2E y y 2F z Z FGXY Z paraboloid or Z axis 0 GQ cylinder non parallel with Cz Dxy Eyz ABCDE code X Y and Gx Jz K 0 FGHJK ellipse Z axis hyperboloid paraboloid TX ellipse torus parallel with x xy B XyzABC torus X Y or y 3 z 2 AYJC 120 TY Z axis P4 P4 XyzABC x 3 2 AP JC 120 TZ z zy XyzABC 7 0 39 A C 1 0 P plane defined by Xp yp Zio X2 Y2 22 coordinates X3 Z3 The cone defined by x y or z has
194. kf code particle name ityp symbol kf code particle name 1 proton 2212 proton 11 12 Ve Ve 2 neutron 2112 neutron 11 14 Vu 3 pion 211 11 2212 4 0 111 11 2112 n 5 pion 211 11 311 6 muon 13 Hu 11 4 221 17 7 muon 13 Hu 11 331 7 8 kaon 321 Kt 11 _ 3122 A9 AO 9 kaonO 311 K 11 _ 3222 yt DF 10 kaon 321 K T B 1 3212 50 11 other below other particle 11 _ 3112 YE 12 electron 11 E 11 3322 zo 50 13 positron 11 e T _ 3312 11 4 334 oO 15 deuteron 1000002 deuteron 16 triton 1000003 triton 17 3he 2000003 He 18 alpha 2000004 a 19 nucleus 7 1000000 nucleus 20 all all particles 3 6 Particle identification Table 3 5 Decay channel and life time blanking fraction life time sec mJ gt y y 100 0 pw v 100 2 6029 8 cy 7 100 2 6029 8 e tow tow 100 2 19703e 6 gt V Yu 100 2 19703 6 gt m mr 68 6196 8 922e 11 gt 7 31 39 gt other o gu wv 63 5196 1 2371e 8 o m m other K o v 63 5196 1 2371e 8 gt m m other y gt y 38 9 0 gt m X 31 9 gt m m m 23 7 gt m mJ y other Jy gt m m m 44 196 0 2 m m 9 20 596 gt m mJ y 30 196 gt y other AX gt 64 1 2 631 10 n other gt
195. le z txt omissible Z axis title gshow 8 default 1 2 3 4 When meshzxyz axis xy yz xz region border 1 material name 2 region name 3 and LAT number 4 are plotted by the option rshow default 1 2 3 When mesh reg axis xy yZ XZ region border 1 material name 2 and region name 3 are plotted by the option You need xyz mesh section below this option ginfo 0 default No geometry check in the case of gshow or rshow gt 0 1 Check geometry and draw its two dimensional view with error information 2 Check geometry draw its two dimensional view and outputting a geometry error file err resol 1 default The option multiplies region line resolution by resol times with gshow or rshow option width 8 5 default The option defines the line thickness for gshow or rshow option volume omissible The option defines volume for each region for reg mesh You need volume definitions below this option Default values are given in input echo in the case of no definition reg vol volume definition 5 1 2 iechrl 72 default Number of maximum column for volume input echo volmat omissible D 9 The option corrects a volume value for each mesh when material is defined by xyz mesh 0 means no correction Value of volmat means the number of scans for one side of xyz mesh epsout default 1 If epsout is set to 1 results are plotted into eps files This eps file name is named by replacing the extension
196. le filename with full pathname The format of decay turtle is double precision and ascii and each record is as xq yp wt0 pz0 Table 4 34 decay turtle data variable explanation Xp yp incoming position of beam particle cm Xq yq angle against vertical face with beam direction mrad momentum of beam particle GeV c wt weight of beam particle pz polarizing of beam particle be not in use 54 4 SECTIONS FORMAT 4 3 12 Cone shape Parameters for cone shape source are shown below The order of parameters is free If a parameter has a default value D the parameter can be omissible Table 4 35 parameters for cone shape s type 18 19 Cone shape x9 D 0 0 x coordinate offset of top of cone cm D 0 0 y coordinate offset of top of cone cm z D 0 0 z coordinate offset of top of cone cm 1 x component of vector from top to bottom cm yl y component of vector from top to bottom cm 21 z component of vector from top to bottom cm ro D 0 0 distance between top and upper end of source locations on lateral surface cm 1 distance between top and lower end of source locations on lateral surface cm r2 angle between generatrix and lateral surface degree dir direction cosine from z axis If you set all isotropic If you set data a type subsection is necessary phi Dznone random azimuthal angle degr
197. les using the angle mesh shown in Fig In the cases of unit 4 5 6 14 15 or 16 the output is given as a quantity per unit steradian sr calculated by using the mesh size of the angle bin defined in the angle mesh subsection Figure 6 3 Schematic image of the tally using the angle mesh Lethargy in unit 3 6 13 or 16 is a natural logarithmic unit of energy and defined by In Eye E using a reference energy and a particle s energy E If you set these units you can obtain results per Lethargy which are calculated by Lethargy widths In Ehign Ejow at each energy bins given in the energy mesh subsection Here Ehign and are maximum and minimum values of the energy bins respectively 62 T Cross section Table 6 4 t cross parameter 2 139 name value explanation file file name Define file names as same number of axis resfile omissible D file Define a file name of the past tally in the restart calculation Even if several axis parameters were defined you should specify only one resfile factor omissible D 1 0 normalization factor title omissible title angel omissible angel parameters 2d type 1 2 3 4 5 6 7 options for 2 dimensional plot omissible output flux flux by surface crossing current current by surface crossing f curr forward current by surface crossing b curr backward current by surface crossing o curr omni
198. leus is not specified Next you define the energy mesh or time mesh First you define the number of mesh by eng or tim and in next line the values of each mesh Minimum value of weight window for each mesh should be defined in the followings Each minimum values are like ww1 ww2 ww3 where wwi is a window minimum value for a mesh lt E lt ej eg and fo is assumed If there exists no eng tim definitions energy time mesh are not prepared In this case you should set only wwl Region number ref must be written at the first column As above example you can make another table for wwi definitions From second table the region definition can be skipped as the example You can use the skip operator non in this section Even if you use GG you should write the symbol not cell but reg in the section You can use the format 2 5 8 9 and you can use the lattice and universe style as 6 lt 10 1 9 0 u 3 But you need to close a value by C ifitis not a single numeric value If you set large weight window to particles which has strong penetration through matter such as neutrino PHITs calculation takes time too much If you define part all neutrino is included You must give attention about it 410 Volume section 99 4310 Volume section Volume for GG cell cm can be defined in this section If the volume is double defined the value defined in this volume section
199. lin Table 6 37 t rshow parameter name value explanation mesh XYZ geometry mesh only xyz mesh you need geometry mesh subsection below this option axis Xy YZ XZ 2 dimensional file file name Define file names as same number of axis output 1 region boundary 2 region boundary material name 3 region boundary region name 4 region boundary LAT number resol 1 default The resolution in displaying region lines is multiplied by this value width 0 5 default The thickness of displayed region lines title omissible title angel omissible angel parameters X txt omissible X axis title y txt omissible y axis title z txt omissible Z axis title reg region definition value reg val value definition with same format as volume definition see section 5 1 2 iechrl 72 default Number of maximum column for volume input echo epsout 0 default 1 If epsout is set to 1 results are plotted into eps files This eps file is named by replacing the extension into trcl omissible coordinate transformation number or definition for r z or xyz mesh gslat 1 default 0 1 show lattice boundary in gshow 0 no ginfo 2 default Region error check 0 No geometry check 1 Check geometry and draw its two dimensional view with error information 2 Check geometry draw its two dimensional view and outputting a geometry error file err
200. lize 175 outputs when I use the isotropic source s type 9 or 10 dir all A4 1 If there is nothing inside the sphere of the isotropic source the fluence inside the sphere is normalized to 1 Inir source where r is the radius of the sphere Thus if you would like to convert the tally output source to the unit fluence you have to multiply the result with It should be noted that the weight control method is employed in generating the isotropic source and thus the event by event information cannot be derived from the simulation using the isotropic source If you would like to obtain event by event information for isotropic irradiation you have to set dir iso in the source section You have to update 175 if you want to use this function 12 4 Questions related to source generation 203 Q4 2 Source particle does not created in the cell where it should be A4 2 If you set the source generating surface or point exactly on the surface of a certain cell PuiTs sometimes miss identify the cell where it should be In this case please move the source surface a little bit different from the cell surface Q4 3 Is it possible to directly specify the source spectrum using energy differential flux A4 3 Version 2 60 or later you can define the spectrum using e type 21 24 31 34 See 4 3 15 Definition for energy distribution section in detail 204 13 CONCLUDING REMARKS 13 Concluding remarks We have developed multi pu
201. ls When you set number of materials define these material numbers in the next line You can set number of materials by negative In the case specified materials are not included for scoring material numbers omissible t type 1 2 3 4 5 time mesh You need time mesh subsection below this option e type 1 2 3 4 5 energy mesh You need energy mesh subsection below this option unit 1 2 3 4 1 1 source 2 1 nsec source 3 1 nsec cm source 4 1 nsec cm MeV source axis eng reg 2 axis value of output data Xy yZ XZ IZ 2 dimensional file file name Define file names as same number of axis resfile omissible D file Define a file name of the past tally in the restart calculation Even if several axis parameters were defined you should specify only one resfile output all energy cut off escape and decay particles cutoff energy cut off particles escape escape particles decay decay particles factor omissible D 1 0 normalization factor title omissible title angel omissible angel parameters 2d type 1 2 3 4 5 6 7 options for 2 dimensional plot 166 6 TALLY INPUT FORMAT Table 6 30 t time parameter 2 name value explanation x txt omissible x axis title y txt omissible y axis title z txt omissible Z axis title gshow 8 default 1 2 3 4 When meshzxyz axis xy yz xz region border
202. ltiplies region line resolution by resol times with gshow or rshow option width 0 5 default The option defines the line thickness for gshow or rshow option 69 T LET section Table 6 25 t let parameter 3 name value explanation volume omissible The option defines volume for each region for reg mesh You need volume definitions below this option Default values are given in input echo in the case of no definition reg vol volume definition See 5 1 2 iechrl 72 default Number of maximum column for volume input echo volmat omissible D 9 The option corrects a volume value for each mesh when material is defined by xyz mesh 0 means no correction Value of volmat means the number of scans for one side of xyz mesh epsout 0 default 1 If epsout is set to 1 results are plotted into eps files This eps file is named by replacing the extension into eps ctmin i omissible D 9999 minimum value for i th counter ctmax i omissible D 9999 maximum value for i th counter trcl omissible coordinate transformation number or definition for r z or xyz mesh gslat 1 default 0 1 show lattice boundary in gshow 0 no 161 162 6 TALLY INPUT FORMAT 610 T S ED section Calculation of the probability density of deposition energies in microscopic sites called as lineal energy y or specific energy z is of great importance in estimation of rela
203. ltiplies region line resolution by resol times with gshow or rshow option width 8 5 default The option defines the line thickness for gshow or rshow option 63 T Heat section 143 Generally speaking heat is an energy of ionization of charged particles However in the transport simulation cutoff energy of the particle is set and the transport is stopped below the energy Then there exist some components of heat i e recoil stopped particle and others in the output of the heat tally These components may change as the parameters of the transport are changed Table 6 7 t heat parameter 3 name value explanation volume omissible The option defines volume for each region for reg mesh You need volume definitions below this option Default values are given in input echo in the case of no definition reg vol volume definition 5 1 2 iechrl 72 default Number of maximum column for volume input echo volmat omissible D 9 The option corrects a volume value for each mesh when material is defined by xyz mesh 0 means no correction Value of volmat means the number of scans for one side of xyz mesh default 1 If epsout is set to 1 results are plotted into eps files This eps file is named by replacing the extension into eps 8 default 1 electron contribution options 0 using photon KERMA factors electron and positron should NOT be transported otherwise their
204. ly the batch variance mode since it is impossible to calculate the tallied quantities history by history using the shared memory parallel computing The standard deviations calculated by the batch variance mode vary with the combination of maxcas and maxbch even for the same total history number In principle larger maxbch gives more reliable statistical uncertainties in the batch variance mode but it may take longer computational time We recommend setting maxbch to more than 10 to obtain reliable results On the other hand in the history variance mode the standard deviation depends only on the total history number and they are independent of the combination of maxcas and maxbch Therefore the history variance mode istdev 2 15 recommended to be selected except for the memory shared parallel computing However the computational time occasionally becomes extremely long in the history variance mode especially in the case of tallies using a lot of memories e g xyz mesh tally with very fine structure In the tallies for calculating the variance of deposition energies by each history such as t deposit tally with output deposit and t deposit2 the standard errors instead of the standard deviations are outputted as the relative errors The relative standard errors can be estimated by 1 VK where K is the number of history contributing to the result of the tally This calculation procedure is independent of the istdev parameter Relative errors are
205. m We assume circle or rectangle beam line for s type 1 4 or s type 2 5 respectively 21 z8 and dir 1 also assumed the latter means the direction of the beam line If you want to change the direction of the beam line you should use the transformation trcl number of transformation The source particles are generated within the circle or rectangle region at z0 defined by r8 or x0 x1 y0 y1 for s type 1 4or s type 2 5 respectively The direction of the particle is determined by the wall position where it reaches within d11 and 412 so as to equalize the wall current at any point within this region changing the importance of the particle Overall normalization factor is defined as a number of the source particles which pass the entrance of beam line at d10 originated within the same region at the source position z0 as that at d10 We normally set the number to be unit for one history if all duct wall position from 110 to 412 can see the source region at 20 If the source region at zQ is larger than the area of the beam line at d16 the source particle from the outer region at z8 is not counted as the normalization number at d10 This means that the extra region at 20 increases the current in the beam line without changing the normalization factor In the above argument we assume isotropic angular distribution of the source particles within the small solid angle which covers the whole beam lin 70 410 dil 412 Figure
206. magnetic field The ratio of the number of parallel and anti parallel spin to the magnetic field is determined by the polarization defined by the polar column non in polar column means 0 polarization The polarization is defined as pa fer p o here and _ are the number of the parallel and anti parallel particles 106 4 SECTIONS FORMAT 4 16 Electro Magnetic Field section You can set uniform electric and magnetic fields in any region Defining parameters in this section and setting ielctf 1 in parameters section can simulate a motion of a charged particle in the fields You can set the electric and magnetic fields together It is noted that you cannot use a quadrupole magnet which can be defined in Magnetic Field section Cell number reg strength of the electric and magnetic fields elf and mgf respectively direction of the two fields trcle and trclm should be defined Units of elf mgf are kV cm and kGauss respectively You should set the coordinate transformation number trcl which are defined in transform section to trcle and trclm When trcle is 0 the direction of the electric field is positive direction of x axis When trclm is 0 the direction of the magnetic field is positive direction of y axis trcle and trclm are not omissible If you set elf or mgf to 0 or you don t need change the direction of the field you should set trcle and trclm to 0 Set the parameters as follows Electr
207. malization factor title omissible title angel omissible angel parameters 2d type 1 2 3 4 5 6 7 options for 2 dimensional plot omissible x txt omissible X axis title y txt omissible y axis title z txt omissible Z axis title gshow 0 default 1 2 3 4 When meshzxyz axis xy YZ XZ region border 1 material name 2 region name 3 and LAT number 4 are plotted by the option rshow 0 default 1 2 3 When mesh reg axis xy YZ XZ region border 1 material name 2 and region name 3 are plotted by the option You need xyz mesh section below this option ginfo 0 default No geometry check in the case of gshow or rshow gt 0 1 Check geometry and draw its two dimensional view with error information 2 Check geometry draw its two dimensional view and outputting a geometry error file err resol 1 default The option multiplies region line resolution by resol times with gshow or rshow option width 0 5 default The option defines the line thickness for gshow or rshow option volume omissible The option defines volume for each region for reg mesh You need volume definitions below this option Default values are given in input echo in the case of no definition reg vol volume definition 5 1 2 iechrl 72 default Number of maximum column for volume input echo 67 T Product section Table 6 19 t product parameter 4 name value explana
208. mat 6 1 T Track section 6 2 b Cross section lt seu ace e aod GR Sok FORE XS REOR UR UU e FS RUE S tos Rue ded eo ae qm Ede la dee auteni iat gestare pe Beck arn CMM ac te Made werk Bde su eget bebe es ep wees os T PLU atte west Gym aes a Ge peg pL eG a teak Sed as a Ga nied dead beet Ane cae aes edad aes eesti es cen yl se Sate Restate er ere sD ee errr OESE ene eee 6 17 1 boxdefimtion llle 6 17 2 3dshow 7 Volume and Area calculation by tally function Processing dump file Output cutoff data format E 0 Region error check xj 11 Additional explanation for the parallel computing 11 1 Distributed memory parallel computing 11 1 2 Adjustment of maxcas and maxbch 11 1 3 Treatment of 11 1 4 ncut gcut pcut and dumpall file definition in the PHITS 11 1 5 Read in file definition in the PHITS 11 2 Shared memory parallel computing 12 FAQ 12 1 Questions related to parameter setting 12 2 Questions related to error occurred in compiling or exec
209. me calculation 5 7 13 rshow definition You can use rshow definition in all tallies except for t cross and t gshow tallies This option is avail able with region mesh xy yz zx axis This option makes a two dimensional plot in which each region is colored with the amount of its region s output value And region boundaries material name or region name numbers are also displayed The xyz mesh definition is required after this rshow definition rshow 6 means norshow option 1 means rshow with region boundary 2 means rshow with region boundary and material name 3 means rshow with region boundary and region name numbers If rshow 0 xyz mesh definition is not required comment out it When you increase the resolution of the plot by resol parameter the indication of region name material name and lattice number on the graph are sometimes disturbed In this case you should increase the mesh points instead of resol If you use the rshow option with reg mesh there is no output for the values of each region In this case you can not re plot the figure because of no original data When this rshow option is used usually axis is set as xy yz and zx But you should use in addition axis reg in order to save results into another file for re plotting You can re plot figures from saved data and t rshow tally function You can execute this option without transport calculation by using icntl 10 in the parameters sect
210. me to be zero 1 stopped 1 or nothing 0 Timer reg in out coll ref 1 9 1 9 9 11 1 8 0 0 If you want to replace the order of region number reg in out coll and ref set as reg coll in out ref You can use the skip operator non At least one must be defined in the out coll ref If nothing is defined it is assumed no action You can use the format 2 5 8 9 and you can use the lattice and universe style as C 6 10 1 9 0 u 3 But you need to close a value by C if itis not a single numeric value 4 24 delta ray section 115 4 24 delta ray section In this section you can set parameters used in the function to generate knocked out electrons so called rays which are produced along the trajectory of a charged particle in materials as secondary particles In the PuiTs calculation an energy transfer to the material is estimated by Linear Energy Transfer LET dE dx and is assumed to be deposited only on the particle trajectory However it is well known that owing to a high energy ray the energy deposition is spread far away from the orbit of the primary particle You can take the effect of rays into account using this function The production cross sections of rays from those particles in liquid water were calculated using the model proposed by Butts and Katz considering the relativistic collision dynamics You can set a threshold energy Ey MeV for each
211. means that transposition vector is in sub coordinate system defined in main coordinate system means that transposition vector is in main coordinate system defined in sub coordinate system Default values are shown below TRn 00 10001000 1 4 7 0 Mathematical definition of the transform The mathematical definition in terms of transposition vector and rotation matrix is the following In the case of M 1 In the case of M 1 Bi B4 Bj x X y Ba Bs Be O2 z B Bg 2 B3 X B4 Bs Bo y Bs Bs O2 Bg Bo 2 96 4 SECTIONS FORMAT Here B cos x x B cos x y cos x z B4 cos y x Bs cos y y Bg cos y z B cos Z x Bg cos z y By cos z z In the case of M 1 the object used this transform function is rotated and then translated On the other hand in the case of M 1 the rotation is performed after the translation The rotation is performed about the origin of the xyz coordinate system Note that the direction of the translation setting M 1 and 1 is opposite each other 4 7 5 Examples 1 List 4 21 transform section example 1 1 Transform 2 trl 0 0000000 00 0 0000000 00 1 4000000 03 3 1 3500000E 02 9 0000000 01 4 5000000 01 4 0 0000000 01 0 0000000 00 9 0000000 01 5 2 2500000 02 9 0000000 01 1 350000
212. model dfano 146 dipole electromagnet dir direction cosine distributed memory parallel computing 410 412 dmax i dnb dom DPA dpa 207 dpf drd DRES dresol duct source dump 3 5 45 55157 130 140 192 dumpall DWBA dxw dyw e dst e mode 1 2 7 44 141 149 152 156 e phi 183 e the 183 e type 3 55 57 6064 120 122 123 134 138 144 0 el t el type 147 12 e2 t e2 type 147 e21 124 EBITEM EEDL ego egl 63 eg2 eg3 EGSS eielfmax eielfmin einclmax einclmin eisobar ejamnu ejampi ejamqmd elastic 170 elastic scattering 25 35 electron elf ELIB ELL emax emcnf emcpf emin i emumax emumin energy cut off 165 energy mesh energy straggling 27 eng 38 98 124 125 134 138 152 165 168 eng t engl 208 eng2 147 eps 10 129 135 140 143 146 148 151 155 158 epsout 129 135 140 143 146 148 151 155 158 eqmdnu 23 escape 165 ESTEP et0 63 et1 63 et2 63 evaporation model 25 event generator mode Excel 127 execution f curr 140 fac 158 factor 47 126 134 140 143 145 148 150 155 158 FAQ 201 fcl 103 file 21 125 134 140 141 145 150 155 175 179 182 file 20 2 FILL 77 78 82184
213. mple param cl 3 5 sin 55 pi 180 3 5 Using mathematical expressions 15 Table 3 3 Intrinsic Function Intrinsic Function FLOAT INT ABS EXP LOG LOG10 MAX MIN MOD NINT SIGN SQRT ACOS ASIN ATAN ATAN2 COS COSH SIN SINH TAN TANH As above example as a single numerical value is expected after param you can put blanks in the expressions However it is not allowed that multiple numerical values are aligned in some sections In such region you can close the expressions using like cl 2 pi 16 3 INPUT FILE 3 6 Particle identification Available particles in PxiTs are identified as in Table 3 4 These particles can be specified by the symbol or kf code The particles which is not specified the symbol in Table are specified by only kf code The other particles identified as type 11 can be defined by the kf code as shown in followings and these decay channels and life times are also shown in below By adopting the QMD code nucleus can be treated in 75 The writing form of nuclide is as 208Pb 56Fe The writing style Pb Fe etc means all isotopes This can not be used as projectile Nucleus can be described by kf Z 1000000 A for the kf code In the previous version of PHiTs the photon was called gamma but it is called photon in the newer version Table 3 4 List of the transport particles ityp symbol
214. multiply any factor as a function of LET dE dx in a certain material to the dose or deposit energy This function is realized by user defined subroutine usrdfn1 f and usrdn2 f As examples the default program of usrdfn1 f returns the dose equivalent calculated from deposit energy multiplied with the Q L relationship defined in the ICRP60 while that of usrdfn2 f simply does the energy loss without multiplying any factor You can change and add any factor in this routine In addition using the time mesh with timer section you can simulate a TOF time of flight detector and plot 2 dimensional graph of the correlation between the deposit energy and the TOF After version 2 70 the detector resolution can be considered in the calculation of event by event deposition energy distributions using output deposit Table 6 8 t deposit parameters 1 name value explanation mesh reg r z Xyz geometry mesh you need geometry mesh subsection below this option part all default maximum 6 particles in a t deposit particle name material omissible You can specify materials for scoring all all default same as no definition number of materials When you set number of materials define these material numbers in the next line You can set number of materials by negative In the case specified materials are not included for scoring next line 258 material numbers letmat omissible material id for LET dE dx If
215. n select the information that you need The current batch number appears on the console window in real time Some important error and warning messages such as input data file for cross section directory does not exist are also shown in the window Cone shape can be used for specifying the source locations by setting s type 18 19 Dumpall and dump function for t cross t time t product tallies can be used in the restart calculation For this revision the rule for specifying the file names was changed Results written in a configuration file cfg in the former version of PHITS before 2 66 are outputted in a file specified by Dump data are outputted in another file named _dmp We increased the total memory usage of PuiTs mdas given in the param inc file to 120 000 000 equiv alent to 1GB and the maximum number of lattice in a cell to 25 000 000 By this extention we can use a detailed voxel phantom such as ICRP phantom without recompiling the source code From ver 2 66 the following functions were implemented Algorithm for including discrete spectra calculated by DWBA Distorted Wave Born Approximation was implemented In several nuclear reactions induced by protons or deuterons discrete peaks are added to neutron and proton spectra obtained by nuclear reaction models Pion production processes in photo nuclear reactions were included by implementing A and N resonances Thus PHITS2 66 can treat
216. n boundary 128 179 181 region error region mesh 117 region name region number repeated structure INDEX resfile 125 134 140 14 1 145 147 150 155 156 16 1 residual nuclei 25 35 149 199 resol 129 135 140 143 145 148 15 1 155 158 16 1 resolution 128 restart calculation RHO 771 78 RHP rijk 10 5051 rseed 20 rshow 19 108 128 129 135 143 145 151 155 158 rx 53 ry rz 21 124 134 14 1 145 150 152 155 156 161 163 5 01 s type 45 71555 57 60 190 S a B Z5 scoring mesh SDM se type 163 se unit SED 162 sed 163 sfile 131 shared memory parallel computing 9 199 Shen 26 simple SMM 5 50 91 source 155 source check 19 special 149 specific energy 162 SPH spin 50 91 standard output 35 star density 168 statistical uncertainties straggling 37 sum tally sumfactor 131 surface surface definition 90 surface number surface sense surface symbol switching energy swtm D4 211 sx pI sx 715157 130 SY 1 sy 47 53H571 130 symbol 16 SZ 78H80 91 sz 47 55H57 130 t t el t e2 t eng t type 47 55 57 121 122 147 152 165 t0 tab target tc td tg list the the Moliere theory tim time mesh timeevo 172 title 126 134 140 143
217. n by e type 7 as e type 7 et 1 e 4 etl 1 e 6 et2 1 e 3 The second Gaussian distribution is also equivalent to the expression by e type 2 as e type 2 1 e 1 1 1 e 1 eg2 1 e 4 eg3 5 e 1 These energy distributions are shown below by using t product tally with output source and icntl 6 The result of each particle is shown in Fig 4 5 with different colors 107 1072 m T ks m 3 3 8 10 proton 4 s 1 photon 9 10 neutron E 2 Z 10 10510 10 10 10 10 10 10 10 10 Energy MeV 109 Figure 4 5 Multi source energy distribution 70 4 SECTIONS FORMAT The first source has an angular distribution defined by dir 0 which means 90 degrees direction with respect to z axis the second one has dir 1 180 degrees direction and the third one has an angular distribution defined by a type description in which we used an analytic function for an angular distribution The angular distribution of the third one is shown in Fig 4 6 by using t cross tally Md 0 0015 c M J J 2 0 0010 _ E 5 L G E J 2 L amp 0 0005 0 0000 0 0 0 2 0 4 0 6 0 8 1 0 cos 0 Figure 4 6 Multi source angular distribution 43 Source section 71 4 3 18 Duct source option For the simulation of neutrons through the long beam line from the moderator of spallation neutron source or the reactor to t
218. n direction of the particle 17 NZST This is charge state of the particle 18 NCLSTS This variable means the number of produced particle and nucleus a MATHZ MATHN JCOLL KCOLL MATHZ Z number of the mother nucleus MATHN N number of the mother nucleus JCOLL reaction type id1 KCOLL reaction type id2 JCOLL and KCOLL indicate the following meaning JCOLL 0 nothing happen 1 Hydrogen collisions 2 Particle Decays 3 Elastic collisions 4 High Energy Nuclear collisions 5 Heavy Ion reactions 6 Neutron reactions by data 7 Photon reactions by data 8 Electron reactions by data 9 Proton reactions by data 10 Neutron event mode 11 delta ray production KCOLL 0 normal 1 high energy fission 2 high energy absorption 3 low energy n elastic 4 low energy n non elastic 5 low energy n fission 6 low energy n absorption 178 b ICLUSTS JCLUSTS QCLUSTS JCOUNT These variables have a array and denote the information on the produced particle and nucleus ICLUSTS amp JCLUSTS i20 1 2 3 4 5 6 7 QCLUSTS i i 0 2 2 3 4 5 6 7 8 9 10 11 12 kind of particle nucleus proton neutron pion photon kaon muon others angular momentum proton number neutron number ityp status of the particle 0 real 0 dead charge number baryon number kf code impact parameter px GeV c py GeV c pz GeV c GeV rest mass
219. n of x FoRTRAN style X denotes energy MeV u One can use intrinsic functions and constants C e g f x exp cl x 2 number of energy group If it is given by positive number linear interpolation is assumed in a bin If negative logarithmic interpolation is assumed in a bin In default p type 0 equal number of particle is generated in each cell The integrated number of source particles generated in each bin is proportional to p i 1 eg2 minimum cut off for energy distribution MeV maximum cut off for energy distribution MeV p type 0 1 D 0 generation option for 0 p i 1 for all i is assumed without the following data for 1 p 1 must be given from the next line by the format as pCi i 1 nm 43 Source section 65 4 3 16 Definition for angular distribution If you set dir data angular distribution parameters are required as shown below If a parameter has a default value D the parameter can be omissible Table 4 45 parameters for source angular distribution 1 parameter explanation a type 1 11 You can specify any angular distribution by giving data set of angle bins a Ci and integrated values of the particle generation probability w i by hand The number of the particle generation in the bin is proportional to w i and the specified angular distribution is statistically described For 1 case angle is given by cosine for 11 case given by degre
220. nal to 1 L and 1 17 respectively The cross marker in the figure indicates the position of 4109 and show that the current at this point is unit The results of the duct source option agree very well with the analytical results T T 1 12 1118 o Current PHITS e Wall Current PHITS 107 Current n source 1000 2000 3000 4000 5000 z cm o Figure 4 8 duct source option example 1 In the next example we changed only the size of the source from the previous example 43 Source section 73 List 4 4 duct source option example 2 1 Source 2 3 set c1 200 d10 4 set c2 500 d11 5 set c3 5000 d12 6 set c4 10 0 x 2 7 set c5 10 0 2 8 set c10 5 0 9 set c20 5 0 dyw 10 set c30 0 001 dpf 11 12 s type 2 13 proj neutron 14 20 0 15 c4 2 16 x1 c4 2 17 c5 2 18 yl 5 2 19 20 0 0 20 21 0 0 21 dir 1 0 22 phi 0 0 23 24 dom 10 25 10 c1 26 911 c2 27 012 c3 28 dxw c10 29 dyw c20 30 dpf c30 at 20 at 20 Figure shows how the extra region of the source increases the current and the wall current By this function you can automatically treat the margin area of the moderator to the size of the cross section of beam line 10 rt 1 1 10 c iv o Current PHITS 107 o e Wall Current PHITS Current n source 1000
221. nd t type In the former version of PHITS before 2 66 the normal output was written on a configuration file cfg and the dumped data were written on This t product can tally the source particles By using this function you can modify the dump file You can read a dump file and write the information on a new dump file with some modification by setting the dump parameter and output source in this tally section and icntl 6 in the parameter section 156 68 T DPA section T DPA gives DPA Displacement Per Atom value This is the number of displaced atoms per a target atom and represents the radiation damage in materials irradiated by energetic particles The result by this tally includes the contribution of Coulomb scattering cross section for the charged particle transportation DPA by low energy neutron can be also obtained by using libraries In this case you must specify the library If you use 6 TALLY INPUT FORMAT e mode 1 you can get the DPA values without the DPA library Table 6 20 t dpa parameter 1 number of materials name value explanation mesh reg r z Xyz geometry mesh you need geometry mesh subsection below this option part all default maximum 6 particles in a t dpa particle name material omissible You can specify materials for scoring all all default same as no definition When you set number of materials define these material numbers in the next li
222. ne You can set number of materials by negative In the case specified materials are not included for scoring next line number of mother nuclei 208Pb Pb mother is not effective in library use next line 258 material numbers mother omissible You can specify mother nuclei all all default same with no definition When you set number of mother nuclei define their mothers in the next line You can set number of mothers by negative In this case specified mothers are not included for scoring Nucleus if you specify with mass Without mass all isotopes of Pb If you want to specify multiple mother groups use multiple t dpa tallies unit 1 2 1 DPA source 1 e 24 2 DPA source axis eng reg y 2 xaxis value of output data Xy yZ XZ IZ 2 dimensional file file name Define file names as same number of axis resfile omissible D file Define a file name of the past tally in the restart calculation Even if several axis parameters were defined you should specify only one resfile 68 T DPA section Table 6 21 t dpa parameter 2 name value explanation output dpa total total DPA value cutoff1 DPA value when energies of charged particles produced by reactions are below cutoff energy emin cutoff2 DPA value when energies of charged particles transported in materials are below cutof
223. ne for the library number id corresponding to the nuclide and use its data library You can specify library number id on each material number not on each nuclide by NLIB PLIB ELIB HLIB parameters in Table 4 48 Note that the specification with the above extension have higher priority than that with these parameters Information on used data library in a PHITS calculation is written in the summary output file file 6 D phits out when kmout 1 is set in parameters section 44 Material section 75 If you want to use carbon you should use 6000 6012 or 12C Because doubles as a comment mark 4 4 3 Density definition Two units are available for density definition if density takes positive value it means particle density as 107 atoms cm else if negative value mass density g cm These densities can be re defined in the ce11 section So if you have density definition in the ce11 section you don t need to set density alternatively you can set composition ratio here 4 4 4 Material parameters For the region in which you use nuclear data you can set material parameters for each material as the style keyword value Anywhere you can write this parameters in the material subsection Parameters are shown below Table 4 48 material parameter parameter value explanation GAS D 0 density effect correction to electron stopping power 0 appropriate for material in the condensed solid or liquid
224. not be used You can use the lattice and universe style as 6 lt 10 1 8 0 lt u 3 By using above format you can tally from each lattice individually And if you set region as reg all all regions become tallying region However cells which do not belong to bottom level are not included 5 1 2 Definition of the region and volume for repeated structures and lat tices When you define regions including repeated structures and lattices you must close your definition by C A level structure is indicated by In the case an intermediate level has the lattice structure you can specify lattices using represented by the lattice coordinate 5 t after the cell number as 160 1 2 3 6 1 1 In this example lattices which from 1 to 2 in s direction 3 to 6 in direction and 1 in direction are defined Or you can specify individually as 160 1 3 4 2 3 4 3 3 4 The style C in one level can be used to combine some regions See next example List 5 1 mesh reg example 1 mesh reg reg all 201 205 161 lt 168 1 2 3 6 1 1 201 202 283 204 161 162 163 C C 90 100 120 lt 61 62 63 D Uu This region mesh definition is echoed as List 5 2 mesh reg example 2 1 mesh reg mesh type is region wise 2 reg Call 201 205 C 161 lt 160 1 2 3 6 1 11 CC 3 201 204 lt 161 163 C C 98 100 120 lt 61
225. ns are still in inapplicable to the shared memory parallel computing 1 2 Runtime execution of ANGzL from PuiTS by setting epsout 1 Only for Intel Fortran compiled PxiTs on Windows In order to avoid the Ist problem the executable file for memory shared parallel computing contained in the current PuiTs package was compiled by replacing a angel f by a angel winopenmp f which outputs the file names specified by tallies with epsout 1 into angel temporary inp Then phits bat automatically executes stand alone version of ANGzL angel bat employing angel temporary inp as the input file If segmentation errors occur in executing memory shared parallel computing PxiTs on Linux it may due to the overuse of the stack memory In that case you have to increase the stack size using the command below export OMP_STACKSIZE 1G This command sets the stack size to IGB In principle the results obtained from single processing and shared memory parallel computing should be the same Thus if you found inconsistencies between the results obtained by the two modes please let us know It may be a bug in the programming 201 12 FAQ 12 1 Questions related to parameter setting 01 1 How can we precisely simulate motion of low energy neutrons How can we use nuclear data library in PuiTs 1 1 In general nuclear reaction models such as Intra Nuclear Cascade INC or Quantum molecular dynamics QMD cannot
226. number is m RHO This is used with LIKE BUT RHO x format You can define the same cell except that its density is x 4 5 2 Description of cell definition Cells are defined by treating regions divided by surfaces defined in the surface section When you describe the definition you need a concept surface sense to make a distinction between two regions divided by the surface corresponding to an equation f x 2 0 and Boolean operators Li blank AND OR and NOT to treat some regions The surface sense defines one region including a point xo zo which gives f xo yo zo gt 0 as pos itive sense and the other region as negative sense Then you write only the surface number in the 11 definition space when you want to use a region of positive sense and write it with minus symbol when a region of negative sense An example for this sense is shown below List 4 8 cell section example 1 1 Cell 2 1 10 3 2 1 10 4 Surface 5 10 SZ 3 5 The 10th surface represents a sphere with a radius of 5cm Because the inside of this sphere is negative sense the Ist cell is defined by 10 The outer region is explicitly defined as the 2nd cell This example gives the virtual space as shown in Fig 4 10 10 TT TTTTTTTTTTTTTTTTT L 4 3 b 5 0r 1 4 void x f V J ar UN 10 10 5 0 5 10 z cm Figure 4 10 Resul
227. o Magnetic Field reg elf mgf trcle trcim 1 100 1 1 2 2 100 1 1 2 If you set itstep 1 in parameters section you can depict clearly the track of the particle using t track tally When you specify charge number of the projectile particle with izst in Source section the motion of the particle with the number in the electro magnetic field is described Using izst PuiTS can simulate the motion of the particle with charge states The charge number defined with izst doesn t change while the particle moves It should be noted that particles produced from nuclear reactions are not affected by the value of izst the charge of the produced particle is given as its atomic number 417 Counter section 107 4 17 Counter section The counter function can be defined in this section Three counters can be used in tally sections The counter counts when 1 a particle comes into specified region 2 a particle goes out specified region 3 a particle takes scattering in specified region and 4 a particle reflects back on a certain boundary of the region You can set one progress value of the counter from 9999 to 9999 or zero set 10000 Counter values are attached to particles Secondary particles produced in the collisions have the same counter value of parent Capacity of the counter is from 9999 to 9999 Counter changes only this range You can set the counter for each particle by using part definition and you can exclude s
228. o directly define differential energy spectrum in MeV as well as discrete energy spectrum Several algorithms were optimized to reduce the computational time especially for xyz mesh tally with istdev 2 Furthermore use of memory for tally and AwGgL was improved These improvement were performed by Mr Daichi Obinata of Fujitsu Systems East Limited and were supported by Center for Computational Science amp e Systems Japan Atomic Energy Agency JAEA Minor revision and bug fix Number of cells acceptable in t dchain was increased The references of PuiTS and INCL were changed 7 digit cell ID became acceptable Maximum dmax for electron and positron was changed from 1 GeV to 10 GeV Restart calculation became available even when PuiTs did not stop properly Lattice cell became acceptable in t dchain Avoid the termination of PuiTs when some strange error occurs in JAM New multiplier function k 120 was added to weight the density Minor bug fix in SMM user defined tally range calculation transform electron lost particle random number generation for MPI delta ray production Nuclear data for some nuclei was revised by following the revision of JENDL 4 0 Bugin reading proton data library was fixed From ver 2 52 the following functions are implemented e Electron positron and photon transport algorithms were revised In the new version effective stopping powers of ele
229. of INC ELF in a proton or neutron induced reaction eielfmin D 1 0 Minimum energy of INC ELF calculation MeV 1 fmax D 3500 0 Maximum energy of INC ELF calculation MeV irqmd D 0 Control parameter for use of JQMD or R JQMD 0 Use of JQMD in nuclear reactions 1 Use of R JOMD in nuclear reactions Below egmdmin we do not consider the nuclear reactions of d t o and nucleus Since the applicability of is restricted in low energy region and the range of nucleus is very short in the normal material one do not need consider the low energy reactions of nucleus for usual case High energy heavy ion collisions are treated by JAMQMD above 3 5GeV u in default This switching energy can be changed by ejamqmd Even for nucleon induced collisions you can calculate the collisions by JAMQMD by changing eqmdnu e jamnu and e jamqmd INCL Intra Nuclear Cascade of Li ge is a nuclear reaction model for nucleons proton and neutron pions and light ions d t He or induced reactions From version 2 50 INCL is used by default for these reactions if you don t explicitly specify the nuclear reaction model In the case of using results obtained by INCL in your publication please refer a document shown below INC ELF Intra Nuclear Cascade with Emission of Light Fragment is a nuclear reaction model for nucleons induced reactions In the case of using results obtained by INC ELF in your publication please refer a document shown belo
230. of all sources generated in an event are the same This mode is useful for simulating a nuclear reaction occurred at arbitrary locations 3 Correlated multi source In this case the locations of all sources generated in an event are the same and the directions of second source is opposite to the first one This mode is useful for simulating a particle decayed into 2 particles at arbitrary locations You have to specify the multiplicity of each source in an integer value as its source parameter and sum of the multiplicities as the totfact parameter For example if you would like to simulate X 1 p2n reaction as an event you have to set source 1 and 2 for proton and neutron sources respectively and totfact 3 43 Source section 4 3 2 Common parameters 47 Common parameters for each source type are shown below The order of the parameters in the source section is free If a parameter has a default value D the parameter can be omissible The energy of d t and nucleus is specified by MeV nucleon Table 4 24 common source parameters parameter explanation proj projectile see Tabld3 4 for specification t type 0 1 2 D 0 time distribution 0 no time distribution t 0 0 1 rectangle distribution 2 Gaussian distribution tO D 0 0 center of time when t type 1 ns tw FWHM of time distribution ns tn number of time distribution td inte
231. of their cross section data such as n p and n contained in evaluated nuclear data library You can use this new event generator mode by setting e mode 2 in parameters section JOMD was improved to consider the relativistic effect The algorithm for stabilizing the initial state of nucleus was also implemented The improved JOMD named R JQMD can be activated by setting irqmd lin parameters section This improvement was performed under collaboration with Dr D Mancusi at CEA Saclay Detector resolution can be considered in the event by event deposition energy calculation using t deposit with output deposit Lu 2H Sihver et al Nucl Instr amp Meth B 334 34 39 2014 Hirayama et al SLAC R 730 2005 and KEK Report 2005 8 2005 1 1 Recent Improvements 3 From ver 2 67 the following functions were implemented A geometry check function was implemented This function works when you specify a tally for generating the two dimensional view of your geometry When double defined or undefined regions are detected their regions are painted on the two dimensional view See Sec 0 detail An extension of the event generator mode ver 2 was implemented Owing to this implementation the accuracy of event by event analysis for the reactions induced by neutrons below 20 MeV was improved See Sec 4 2 2 in detail New parameter infout was added to control output information in file 6 D phits out You ca
232. ome particles from the counter actions by part definition Counter counter 1 part neutron proton reg in out coll ref 1 1 10000 0 0 11 1 10000 0 0 counter 2 part proton deuteron triton 3he alpha nucleus reg in out coll 2 5 89 1 9 1 counter 3 part 208Pb reg coll C 11 12 15 5 6 lt 10 1 0 lt 3 100 If you want to change the order of region number reg in out coll and ref set as reg coll in out ref You can use the skip operator non At least one must be defined in the in out coll ref If nothing is defined it is assumed no counter Numeric gives one progress value of the counter 10000 means zero set The initial counter value of source particle is zero You can use the format 2 5 8 9 and you can use the lattice and universe style as C 6 lt 10 1 9 0 lt u 3 But you need to close a value by C if itis not a single numeric value In the definition of part you can specify particles up to 20 particles For nucleus you can use the expres sion like 208Pb and Pb The later case Pb denotes all isotopes of Pb 108 4 SECTIONS FORMAT 4 18 Reg Name section Region names and their font sizes for graphic output by t gshow t rshow and t 3dshow are defined in this section When you set the gshow or rshow option in the other tallies this definition is applied By default a region name is set to its region number Reg Nam
233. one resfile multiplier number of material multiplier for each material omissible You need multiplier subsection below this option factor omissible D 1 0 normalization factor title omissible title angel omissible angel parameters 2d type 1 2 3 4 5 6 7 options for 2 dimensional plot omissible Lethargy in unit 3 or 13 is a natural logarithmic unit of energy and defined by In Eye E using reference energy Eyer and a particle s energy If you set these units you can obtain results per Lethargy which are calculated by Lethargy widths In Enigh Etow at each energy bins given in the energy mesh subsection Here Fhigh and Elow are maximum and minimum values of the energy bins respectively If you set unit 1 2 3 11 12 or 13 you obtain the mean particle fluence in the specified region which is calculated from the sum of the track lengths per source divided by the volume of the region Noted that for reg mesh you have to set the volume in the Volume section If you do not you obtain the particle fluence for volume 1 the sum of the track lengths per source For r z and xyz mesh the volume is automatically calculated If you set unit 4 or 14 you obtain the sum of the track length per source 6 1 T Track section Table 6 2 t track parameter 2 name value explanation x txt omissible x axis title y txt omissible y axis tit
234. otal cores in the case of using the hyper threading technology since the parallel computing using this technology does not work in calculation You can change the environment variable by the following way set OMP NUM THREADS 4 for Windows export OMP NUM THREADS 4 for Mac and Linux In order to execute memory shared parallel computing PHiTs using sendto command you have to specify the number of cores that you want to use in the 3rd line of phits bin phits bat When you use 4 cores you have to write as follows set PHITS PARALLEL 4 200 11 ADDITIONAL EXPLANATION FOR THE PARALLEL COMPUTING It should be noted that in the parallel computing of hybrid type you have to set individually the environment variable on all nodes From version 2 73 an installed executable file of the OpenMP version is available only on the 64 bit Windows system An error due to a heap memory shortage sometimes occurred on Windows OS when the executable file of the OpenMP version for 32 bit is used with many cores However you can avoid the error by the executable file for 64 bit 11 2 2 Important notices for shared memory parallel computing If you use only 1 core for the memory shared parallel computing 175 it takes approximately twice as much time as that in the single processing Therefore it is meaningless to select the memory shared parallel computing in the case that your computer has only 1 or 2 cores The following functio
235. p 51 57 7 99e 11 gt n tom other 0 AP y 100 0 XY n Xo 100 1 479 10 E gt A 100 2 90e 10 E gt A r 100 1 639 10 Q gt A K 67 896 8 22e 11 gt x 23 6 gt E 7 other 18 4 SECTIONS FORMAT 4 Sections format 41 Title section In the section you can define a title of your calculation Any numbers of title lines are allowed Blank lines are skipped in this section Title This is a test calculation of PHITS Any number of title lines are allowed 42 Parameters section 19 42 Parameters section The various parameters of PuiTs can be defined in this section The format is as below Parameters paral number file name para2 number file name You can change the order of parameters Each parameter has the default value So undefined parameters use the default values Parameters and default values are shown in followings D means the default value 4 2 1 Calculation mode Table 4 1 parameter 1 parameter value explanation icntl D 0 basic control option 0 normal PHiTs calculation 1 nuclear reaction calculation under development 2 output a CGVIEW input file 3 output only input echo for checking memory usage and library and file links 4 output a MARS PF input file 5 no reaction no ionization all regions are made be void for geometry check and volume and area calculations 6 source c
236. phical geometry output by 3 dimensional view You can execute this tally with icntl 11 option in the parameters section without transport calculations Table 6 38 t 3dshow parameter 1 name value explanation output 9 draft 1 only region boundary 2 without region boundary 3 default region boundary color material omissible You can specify materials for display all all default same as no definition number of materials When you set number of materials define these material numbers in the next line You can set number of materials by negative In the case specified materials are not included for display next line 258 material numbers x8 D 0 0 Coordinates of original point for view point D 0 0 and light source Center of screen is defined 20 D 0 0 by this point and view point e the D 80 view point angle 6 degree with z axis e phi D 140 azimuthal angle for view point degree with x axis e dst D w dst 10 distance between view point and the origin cm l the D e the light source angle degree with z axis l phi D e phi azimuthal angle for light source degree with x axis l dst D e dst distance between light source and the origin cm w wdt D 100 width of screen frame cm w hgt D 100 height of screen frame cm w dst D 200 screen frame distance from the origin cm A straight line drawn between the center of screen frame and the or
237. piler options written in makefile are just examples and you may have to change them to be suitable for your computer environment If you use option j in the make command you will get many errors because the order of compiling files should not be changed in the make of Pu Ts j option changes the order In that case you have to type make j again or do not use j option then you will succeed in making the Pu Ts executable If you want to use gfortran for Winpows you can download the latest version of the installer from Bundle Installer on the web site below e TDM GCC http tdm gcc tdragon net download Note 1 Select Create in the first setup page Note 2 Change Select the type of install to Recommended Packages in the page of New Installation Choose Components When you installed this package you can use mingw32 make command as make command In order to make PuiTs applicable to the memory shared computing the source code of PuiTs was dramatically revised from version 2 50 The status of most variables used PuiTs was changed from static to dynamic Consequently PuiTs 2 50 or later cannot be compiled by old Fortran compilers such as 77 and 277 Therefore FoRTRAN compilers recommended by PuiTs office are Intel Fortran Compiler 11 1 or later and gfortran 4 71 or later 2 5 Compilation using Microsoft Visual Studio with Intel For
238. r value explanation inucr D 1 nuclear reaction options 1 double differential cross section calculation 2 total elastic non elastic cross section output 3 non elastic cross section calculation 4 angular distribution of elastic scattering 5 cross section output 6 cross section calculation idam i integer user defined integer variable rdam i real 8 user defined real variable i 1 1098 These values can be used in the Pz Ts code by common userp idam 100 rdam 100 Nuclear reaction calculation mode by icntl 1 is under developing at present 36 4 SECTIONS FORMAT 4 2 17 Physical parameters for low energy neutron The following parameters correspond to PHYS Energy Physics Cutoff Card for neutron less than 20 MeV Table 4 18 parameter 17 parameter value explanation emcnf D 0 0 threshold energy for neutron capture MeV implicit capture is considered above this energy analog capture is considered below this energy iunr D 0 fixed 0 at present dnb D 1 number of delayed neutron by fission 1 natural sampling no delayed neutron number of neutrons V 42 Parameters section 37 4 2 18 Physical parameters for photon and electron transport based on the original model Table 4 19 parameter 18 parameter value explanation emcpf D 18080 maximum energy for the det
239. r143 Rb085 RbO86 RbO87 Rh103 Rh105 Rud96 Ru098 Rud99 100 101 Ru182 Ru183 Rul04 Ru105 Rul06 Sb121 Sb123 Sb124 Sb125 Sb126 Se074 Se076 Se8077 5 078 Se079 5 080 5 082 51084 Sr8086 Sr087 5 088 5 089 5 090 Tc699 Te128 Te122 123 124 125 126 Tel27m 128 129 Te130 132 124 126 128 129 Xe130 131 132 Xe133 134 135 Y 089 Y 090 Y 091 Yb168 Yb170 Yb171 Yb172 Yb173 Yb174 Yb176 7 093 Zr095 1 INTRODUCTION From ver 2 60 the following functions are implemented Algorithm for de excitation of nucleus after the evaporation process was improved by implementing EBITEM ENSDF Based Isomeric Transition and isomEr production Model Prompt gamma spectrum can be pre cisely estimated including discrete peaks The isomer production rates can be properly estimated Quasi deuteron disintegration which is the dominant photo nuclear mechanism between 25 to 140 MeV was implemented in JOMD Thus PHITS2 60 can treat the photo nuclear reaction up to 140 MeV The evaporation process after the giant resonance of Li C N was improved by considering the isospin of excited nucleus Thus the alpha emission is suppressed and neutron and proton emission is enhanced from the giant resonance of these nuclei Particle transport simulation in the combination field of electro magnetic fields became available See section in detail New energy mesh functions were implemented in source section in order t
240. rce 6 Dose MeV source 7 8 9 10 11 12 7 Track 1 cm ke V um source 8 Dose MeV cm keV um source 9 Track 1 cm In keV um source 10 Dose MeV cm In keV um source 11 Track 1 cm source 12 Dose MeV cm source axis let reg x y Z r xaxis value of output data Xy YZ XZ IZ 2 dimensional file file name Define file names as same number of axis resfile omissible D file Define a file name of the past tally in the restart calculation Even if several axis parameters were defined you should specify only one resfile factor omissible D 1 0 normalization factor title omissible title angel omissible angel parameters 2d type 1 2 3 4 5 6 7 options for 2 dimensional plot omissible X txt omissible X axis title y txt omissible y axis title z txt omissible 7 axis title gshow 0 default 1 2 3 4 When meshzxyz axiS xy YZ XZ region border 1 material name 2 region name 3 and LAT number 4 are plotted by the option rshow 0 default 1 2 3 When mesh reg axis xy yz xz region border 1 material name 2 and region name 3 are plotted by the option You need xyz mesh section below this option ginfo 0 default No geometry check in the case of gshow or rshow gt 0 1 Check geometry and draw its two dimensional view with error information 2 Check geometry draw its two dimensional view and outputting a geometry error file err resol 1 default The option mu
241. rder 1 material name 2 region name 3 and LAT number 4 are plotted by the option rshow default 1 2 3 When mesh reg axis Xxy yz Xz region border 1 material name 2 and region name 3 are plotted by the option You need xyz mesh section below this option ginfo 0 default No geometry check in the case of gshow or rshow gt 0 1 Check geometry and draw its two dimensional view with error information 2 Check geometry draw its two dimensional view and outputting a geometry error file err resol 1 default The option multiplies region line resolution by resol times with gshow or rshow option width 8 5 default The option defines the line thickness for gshow or rshow option volume omissible The option defines volume for each region for reg mesh You need volume definitions below this option Default values are given in input echo in the case of no definition reg vol volume definition 5 1 2 iechrl 72 default Number of maximum column for volume input echo volmat omissible D 9 The option corrects a volume value for each mesh when material is defined by xyz mesh 0 means no correction Value of volmat means the number of scans for one side of xyz mesh epsout 8 default 1 If epsout is set to 1 results are plotted into eps files This eps file is named by replacing the extension into eps 169 170 6 TALLY INPUT FORMAT Table 6 33 t star parameter 3
242. rection as you want 48 Importance section 97 48 Importance section The importance for GG cell can be defined in this section If the importance is not defined it is set as 1 0 Maximum 6 importance sections are allowed to be defined in a input file Importance part proton neutron reg imp 1 1 000000 11 5 000000 2 5 89 2 000000 11 12 15 3 000000 C 6 lt 10 1 9 8 u 3 6 000000 Particle is defined as part at the first line If the part is not defined default value is defined as part all The format to describe particles is the same as in tally definition However it can distinguish ityp only each nucleus is not specified If you want to change the order of region number reg and imp set as imp You can use the skip operator non Even if you use the GG you should write not cell but reg here You can use the format like 2 5 8 9 and you can use the lattice and universe style as C 6 lt 10 1 9 0 lt u 3 But you need to close a value by C if itis not a single numeric value The importance of bottom level is a product by each importance at each level In 175 importance of a specific cell at bottom level can be defined by above format By using the format we can define different importance into each lattice If the importance is double defined the first defined importance is valid If you set large importance to particles which have strong pen
243. restart calculation Even if several axis parameters were defined you should specify only one resfile 148 a specific particle which goes into the tally region by using part energy loss for each projectile particle going into the tally region you should define the counter with part 6 TALLY INPUT FORMAT Table 6 12 t deposit2 parameter 2 name value explanation factor omissible D 1 0 normalization factor title omissible title angel omissible angel parameters 2d type 1 2 3 4 5 6 7 options for 2 dimensional plot omissible x txt omissible x axis title y txt omissible y axis title z txt omissible 7 axis title volume omissible The option defines volume for each region for reg mesh You need volume definitions below this option Default values are given in input echo in the case of no definition reg vol volume definition 5 1 2 iechrl 72 default Number of maximum column for volume input echo epsout default 1 If epsout is set to 1 results are plotted into eps files This eps file is named by replacing the extension into ctmin i omissible D 9999 minimum value for i th counter ctmax 1 omissible D 9999 maximum value for i th counter This tally only scores the energy loss of charged particles So you cannot get the sum of the energy loss for counter section and ctmin ctmax in th
244. ribution MeV egl FWHM of Gaussian distribution MeV eg2 minimum cut off for Gaussian distribution MeV eg3 maximum cut off for Gaussian distribution MeV e type 3 Differential spectrum 1 is given by Maxwellian distribution 5 nm 0 200 number of energy group If it is given by positive number linear interpolation is assumed in a bin If negative logarithmic interpolation is assumed in a bin etd temperature parameter T MeV etl minimum cut off for Maxwellian distribution MeV et2 maximum cut off for Maxwellian distribution MeV e type 7 You can specify the same energy distribution as is the case of e type 3 Unlike e type 3 the number of source particles generated in each bin is the same for all energy bin but integrated values of the weight of source particles are adjusted to be proportional to f x x exp x T You can also change the number of source particles generated in each bin by specifing p i nm D 200 Number of energy group If it is given by positive number linear interpolation is assumed in a bin If negative logarithmic interpolation is assumed in a bin In default p type 0 equal number of particle is generated in each cell The integrated number of source particles generated in each bin is proportional to p i etd temperature parameter T MeV etl minimum cut off for Maxwellian distribution MeV et2 maximum cut off for Maxwellian
245. rite the next 4 lines where text about the executable file for the OpenMP version is written as follows specify the number of cores for the parallel computing by OMP NUM THREADS If you would like to use OpenMP version please use the following commands phitsexe Users phits office phits bin phits273 mac openmp exe Please input your machine thread number when you use OpenMP version export OMP NUM THREADS 4 8 Save Contents document wflow Other usage When you use PuiTS with Terminal app you have to type as follows echo export PATH PATH TO PHITS phits bin PATH gt gt bash profile source bash profile where PATH TO PHITS should be changed your installation folder e g Users noda Then you can execute PuiTs with a command as below phits250 mac exe lt your input 2 4 Compilation using make command for Windows Mac and Linux 9 2 4 Compilation using make command for Windows Mac and Linux You can compile the 75 code using make command For this purpose the makefile file in src folder should be revised to be suitable for your own computer For example in the case of compilation using Intel Fortran Compiler on Linux you should set ENVFLAGS written in makefile to be If you want to execute PHiTs on a parallel computing using MPI and OpenMP you have to set MPIFLGS and OMPFLAGS respectively to be true Since com
246. rm number surface symbol and surface definition You can use mathematical expressions and user defined variables in the surface definition Surface definition by macro body can be used Surface number is limited from 1 to 999999 You can also use reflective and white boundary conditions by writing and respectively before the surface number For example 10 indicates that surface 10 is a reflective boundary Formats and examples are shown below Surface surface number transform number surface symbol surface definition Table 4 51 surface definition format item explanation surface number 999999 coordinate if no coordinate transform no input transform number else with coordinate transform use number n of TRn in transform section surface symbol surface symbol in surface card list or symbol of macro body surface definition 1 15 inputs depends on surfaces 4 6 2 Examples List 4 19 surface section example 1 1 surface 2 1 CZ 5 0 3 2 CZ 10 0 4 3 CZ 15 0 5 4 CZ 20 0 6 5 pz 0 0 7 6 pz 5 0 8 7 pz 10 0 9 8 pz 15 0 10 9 pz 55 0 11 10 68 8 46 Surface section Table 4 52 surface card 91 surface symbol type explanation equation input numeric value P plane multi purpose Ax By Cz D 0 ABCD PX vertical with X axis x Dz0 D PY vertical with Y axis y Dz0 D PZ vertical w
247. rpose particle and heavy ion transport Monte Carlo code system PHiTs to simulate the particle induced nuclear reactions up to 200GeV and the nucleus nucleus collisions The event generator mode which was recently incorporated in PHiTs can calculate as an example LET distributions of particles in matter or energy deposition distributions event by event and correlations between energy depositions in different regions on a u scale This mode opens a various possibility to calculate the effects of particle radiation on biological and non biological materials e g risk for single event upsets in electronic devices Newly introduced tally t sed makes possible to estimate RBE of charged particles by considering the pro ductions of rays and Auger electrons based on track structure simulation This method gives to users in various research fields a hint beyond hierarchy from microscopic to macroscopic structures Usually it is very difficult to connect simulation codes in the different structure levels because of huge CPU time However this method overcomes the difficulty by making functions fitting the results of a simulation code and incorporating another code PuiTs has been developed under the collaboration of JAEA RIST and KEK The code is to be further improved in future under collaboration of these institutes together with other universities institutes all over the world The following items are considered to be implemented in near future 1
248. rse style as 6 lt 10 1 9 0 lt u 3 If you want to change the order of region number reg and temperature tmp you can set as tmp reg You can use the skip operator non Even if you use GG you should write the symbol not ce11 but reg here 412 Brems Bias section 101 4 12 Brems Bias section Energy bias of the bremsstrahlung process can be defined for each material in this section This corresponds the BBREM card In the bremsstrahlung process many low energy photons are generated In case that you are interested in high energy photon you can define bias for each energy in order to improve statistics for interest energy region Brems Bias material allor number of materials ml m2 m3 num bias 1 45 1 9 46 2 0 47 3 0 48 4 0 49 5 0 First you define the material for bias setting If you set all the next line is not necessary else if you set numerical value material numbers for the value should be listed in the next line Biases should be defined for the group from 1 to 49 Large number corresponds high energy The bias is relative value If you want to replace the order of group number num and bias bias you can set as bias num You can use the skip operator non 102 4 SECTIONS FORMAT 4 13 Photon Weight section Photon production weight for GG cell can be defined in this section This corresponds the PWT card When the photon production weight W for cell i takes po
249. rval of time distribution ns tc D 10xtw cut off time when Gaussian distribution t type 2 ns SX D 0 x component of spin sy D 0 y component of spin SZ D 0 z component of spin reg D all The source region can be restricted within overlaps between regions defined by each s type and those specified by this parameter The format is as 1 5 18 34 You can use the lattice and universe frame as 6 lt 10 1 9 0 lt u 3 See the section about tally region specification for details ntmax D 1000 maximum re try number when reg is specified trcl D none transform number or definition of transform wgt Dz1 0 weight of source particle factor D 1 0 Normalization factor of source particle PuiTs multiplies all results of tally by factor When you use multi source you should use totfact instead of factor When you don t use multi source totfact factor is an actual normalization factor izst D charge of particle specified with proj Charge state of source particle This has an effect only on a motion in the magnetic and electric fields defined in magnetic field and electro magnetic field sections The charge number defined with izst doesn t change while the particle moves It should be noted that particles produced from nuclear reactions are not affected by the value of izst the charge of the produced particle is given as its atomic number 48 A projectile direction is specified
250. s eng reg X y Z x axis value of output data r t Xy YZ XZ TZ 2 dimensional t eng eng t file file name Define file names as same number of axis resfile omissible D file Define a file name of the past tally in the restart calculation Even if several axis parameters were defined you should specify only one resfile factor omissible D 1 0 normalization factor title omissible title angel omissible angel parameters 2d type 1 2 3 4 5 6 7 options for 2 dimensional plot omissible X txt omissible X axis title y txt omissible y axis title z txt omissible Z axis title gshow default 1 2 3 4 When mesh xyz axis xy yz xz region border 1 material name 2 region name 3 and LAT number 4 are plotted by the option rshow default 1 2 3 When mesh reg axis xy YZ XZ region border 1 material name 2 and region name 3 and LAT number 4 are plotted by the option You need xyz mesh section below this option ginfo 0 default No geometry check in the case of gshow or rshow gt 0 1 Check geometry and draw its two dimensional view with error information 2 Check geometry draw its two dimensional view and outputting a geometry error file err resol 1 default The option multiplies region line resolution by resol times with gshow or rshow option width 8 5 default The option defines the line thickness for g
251. s of the source particle w i by hand The number of source particles generated in each bin is the same for all energy bin but integrated values of the weight of source particles are adjusted to be proportional to w i You can also change the number of source particles generated in each bin by specifing p i For 14 case energy is given by wave length ne Number of energy group If it is given by positive number source particles are generated so that the energy differential fluxes in the unit of 1 MeV become constant in each bin On the other hand if ne is negative the fluxes in the unit of 1 Lethargy become constant in each bin Data must be given from the next line by the format as CeG w i i 1 ne 1 In default p type 0 equal number of particle is generated in each cell The integrated number of source particles generated in each bin is proportional to p i p type 90 1 D 0 generation option for 0 pCi 1 for all i is assumed without the following data for 1 p 1 must be given from the next line by the format as p i i 1 ne For neutron optics we prepare an alternative option to specify the energy as wave length If you specify e type 11 12 14 you can use wave length as an energy unit For the other case you can use the mathematical expressions as e0 8 180425e 8 13 2 which gives the energy of neutron with 13A wave length 43 Source section Table 4 41 parame
252. s attached in the holder src and the execute file dump a exe in Windows system is include in the holder bin List 8 1 source code of dump a f 1 dee dede de de de dede dede de dede dede ede de dee dede dede dede ede de ede dede ede dee e dee de dee e dede ede dee e dede ede dee dee deed x 2 gis This program exchanges the binary data and the ascii data 4 of dump file 5 i modified by K Niita on 2005 08 15 7 8 7 E gr 10 11 dee dede de de de dede dede de dee dede dede dede eode de dede dede ede de ee dede ede dee dede de dede dede ede dee dede dede dee dee ede dex 12 implicit real 8 a h o z 13 14 dimension isdmp 0 30 15 dimension jsdmp 0 30 16 data isdmp 31 0 17 data jsdmp 31 0 18 character chin 80 19 character chot 80 20 logical exex 21 character dmpc 30 4 22 data dmpc kf x y 25 u v w 23 amp er swt stm Seley 2 c3 24 amp Sx sy sz nQO nc nb no 25 amp i An inde uS e 15 26 amp E d ora d H 27 dimension dmpd 30 28 dimension dmpp 30 29 data dmpp 2112 0 0 0 0 0 0 0 0 0 0 1 0 30 amp 100 1 0 0 0 0 0 0 0 0 0 31 amp 0 0 0 0 0 0 0 0 1 0 1 0 1 0 32 amp 0 0 0 0 0 0 0 0 0 0 0 0 0 0 33 amp 0 0 0 0 0 0 34
253. s energy is less than 10 eV or sin is greater than 0 001 the latter is due to roughness of the surface 4 22 EHlastic Option section 113 4 22 Elastic Option section In this section you can set some parameters for user defined elastic option for low energy neutrons By this function you can change angle distributions of elastic collisions of data based neutron reactions We prepare two sample routines usrelst1 f and usrelst2 f You can choose one of these two by usrelst 1 2 in the parameter section You should define the regions to which this function is applied and 4 parameters as Elastic Option reg cl c2 c3 c4 1 5 1 3 3 9 4 2 1 1 1 1 0 7 3 3 1 0 3 0 8 If you want to replace the order of region number c1 c2 c3 c4 set as c3 c2 c1 c4 You use the skip operator non You can use the format 4 7 but the 4 7 9 10 format can not be used The sample routine of usrelst1 f is for Bragg scattering based on the data base and usrelst2 f for any type of angular distribution described by an analytic formula 114 4 SECTIONS FORMAT 423 Timer section The timer function can be defined in this section The timer controls the time of each particle when 1 a particle comes into specified region 2 a particle goes out specified region 3 a particle takes scattering in specified region and 4 a particle reflects back on a certain boundary of the region You can set the ti
254. s which are not used in the previous calculation However please be careful that the calculation with the dumpall option may create huge dumpall file This option is only available for GG geometry In the parallel computing files corresponding to each PE Processor Element are created for writing and reading dumped data If you set idpara 0 or 1 a file is made in the directory named by wk uname on each of the nodes If you set idpara 1 or 3 the each IP number is put at the end of the filename The each PE writes down its result on only the corresponding file and reads it from the same file in the re calculation 34 4 SECTIONS FORMAT 4 2 14 About geometrical errors Table 4 15 parameter 14 parameter value explanation nlost D 18 acceptable value against lost particle per 1 PE igerr D 0 number of recovery for region error igchk D 0 0 no region check check region setting flight mesh to deltb after region crossing deltb D 1 e 5 flight mesh cm after region crossing with igchk 1 It is also a distance from a region boundary where particle is created by the importance and the forced collision deltm D 20 12345 A maximum of flight mesh cm deltc D 2 012345 maximum of flight mesh cm for charged particles with nedisp 1 110 D28 1 A minimum of flight mesh cm with nspred 1 or imagnf 1 Note that when you want to describe a scattering process on thin films less than
255. seed and the next initial random seed 13 CPU summary Category I Total computation time and number of calling each calculation process Meaning of each item is as follows When icput 8 the information on the computation time except for total cpu time is not outputted and items of transport and set data are not outputted e total cpu time total computation time transport time for particle transport set data time for setting input parameters analysis number of data processing nevap number of evaporation dexgam number of de excitation nreac number of nuclear reaction e dklos number of particle decay hydro number of nucleon nucleon scattering n data number of using neutron data library h data number of using proton data library p data number of using photon data library e e data number of using electron data library p egs5 number of photon interaction with EGS5 e egs5 number of electron interaction with EGS5 photonucl number of photo nuclear reaction e muon number of muon induced nuclear reaction elast number of elastic scattering ncasc number of nuclear reaction model bertini number of using Bertini model e isobar number of using isobar model 30 4 SECTIONS FORMAT e JAM number of using JAM model e OMD number of using JOMD model e JAMQMD number of using JAMQMD model e INCL number of using INCL model e INCELF number of using INC ELF model When infout 8 inform
256. show or rshow option In this tally one can only score the energy loss of charged particles So you cannot get the sum of the energy loss for a specific particle which goes into the tally region by using part in this tally section In order to tally the energy loss for each projectile particle going into the tally region you should define the counter with part in counter section and ctmin ctmax in this tally section When you set unit 0 with output dose you can obtain results in the unit of Gy source When you set mesh reg you should define volumes of each cells in volume section or by setting volume parameter of the t heat section Because absorbed dose is intensive variable PuiTs does not output sum over in output files for unit 9 It should be noted that when a region includes more than two materials dose in the region does not equal to average value of the region For example when two material with masses amp Mo and absorb energies E ED s E E E amp respectively PuiTs gives M in this tally though its average dose is M M 146 6 TALLY INPUT FORMAT Table 6 10 t deposit parameter 3 name value explanation volume omissible The option defines volume for each region for reg mesh You need volume definitions below this option Default values are given in input echo in the case of no definition reg vol volume definition 5 1 2 iechrl 72 default
257. sitive value photon is generated if its weight is larger than W x I Unless the photon is treated by the Russian roulette method In this case and I are the importance of neutron for source and creation point cells respectively In the case the photon production weight W for cell i takes negative value photon is generated if its weight takes larger than W x W x I I Unless the photon is treated by the Russian roulette In this case W is a weight of neutron before nuclear reaction If W 0 one photon is generated by neutron reaction If W 1 0e6 photon creation is ignored in the cell By the default W 1 Photon Weight reg pwt 1 0 1 11 0 3 2 5 89 0 5 C 11 12 15 0 1 16 9 9 You can use the format 2 5 8 9 Inthis case you need to close a value by C ifitis not a single numeric value You can not use the lattice and universe style as 6 lt 10 1 8 0 lt u 3 If you want to change the order of region number reg and weight pwt you can set as pwt reg You can use the skip operator non Even if you use GG you should write the symbol not cell but reg 4 14 Forced Collisions section 103 4 14 Forced Collisions section The forced collisions are used for improving tally statistics or thin target analysis by enlarging the collision probabilities When specified particle comes into a region defined as the forced collision region the particle is divi
258. sout is set to 1 results are plotted into eps files This eps file is named by replacing the extension into ctmin i ctmax i omissible D 9999 omissible D 9999 minimum value for i th counter maximum value for i th counter trcl omissible coordinate transformation number or definition for r z or xyz mesh gslat 1 default 0 1 show lattice boundary in gshow 0 no 152 6 TALLY INPUT FORMAT 67 T Product section T Product tallies particles and nuclei produced by nuclear reaction decay and fission and also tallies source particles The differences from t yield are that you can get the energy distribution and time distribution of produced particles and nuclei This tally is not available for low energy neutron photon and electron For e mode 1 however particles and nuclei produced by reactions due to neutron with the library can be obtained Table 6 16 t product parameter 1 name value explanation mesh reg r z Xyz geometry mesh you need geometry mesh subsection below this option part all default maximum 6 particles in a t product particle name material omissible You can specify materials for scoring all all default same as no definition number of materials When you set number of materials define these material numbers in the next line You can set number of materials by negative In the case specified materi
259. stical Multi fragmentation Model SMM the accuracy of calculating the production cross sec tions of light and medium heavy fragments is improved in collisions of heavy ions such as Pb and Hg or for incident energies over 100 MeV u It should be noted that the computational time becomes long using this model See the document below for detail When igamma 3 you can obtain information on the isomer production using t yield with axis chart or dchain See the document for detail 5T Ogawa T Sato S Hashimoto and K Niita Nuclear Instruments and Methods in Physics Research A 723 2013 36 46 6 J P Bondorf A S Botvina A S Iljinov I N Mishustin and K Sneppen Physics Reports 257 1995 133 221 Tap Ogawa S Hashimoto T Sato and K Niita Nuclear Instruments and Methods in Physics Research B 325 2014 35 42 25 26 4 SECTIONS FORMAT 4 2 6 Model option 2 Table 4 7 parameter 7 parameter value explanation ieleh D 0 options for electron and positron transport 0 no slowing down no reaction in the energy region above dmax 12 1 make e dmax 12 and weight e dmax 12 in the energy region above dmax 12 ipnint D 0 Options for photo nuclear reaction 0 This reaction mechanism is not taken into account This reaction mechanism is taken into account Until ver 2 30 this parameter was ipngdr imucap D 0 Options for capture reaction of negative muon Char
260. surface 5 surface vertical with the end of A1 A2 A3 surface vertical with the origin of A1 2 h3 side face of cylinder surface vertical with the end of H surface vertical with the origin of RHP TRC side face of cone surface vertical with the end of surface vertical with the origin of H ELL This is defined as normal surface WED WN n PWN surface including top and bottom hypotenuses surface including and V3 surface including V and V surface including V V and the end of Y amp surface including V V and the origin of Vs 47 Transform section 95 47 Transform section 4 7 Formats You can define the coordinate transform in this section Only C and can be used as a comment mark File including and variable definition can be set in this section The coordinate transformation defined in this section can be used in source section surface section cell section r z xyz mesh of tally and the magnetic field Formats and examples are shown below Transform TRn O5 B B4 Bs Bo Bg Bo M Table 4 55 transform definition item explanation n transform number 1 9999 xT Rn means that B is not a cosine but an angle degree transposition vector B rotation matrix M
261. t be changed but are read from the file It is very powerful when you want to calculate different tallies which are not used in the previous calculation However please be careful that the calculation with the dumpall option may create huge dumpall file This option is only available for GG geometry The dumped data written in binary can be not used on the other computer The data sequence and meaning are given in the following 1 NCOL NCOL is an intrinsic variable in the program and denotes identification of process NCOL 1 start of calculation 2 end of calculation 3 end of a batch 4 source 5 detection of geometry error 6 recovery of geometry error 7 termination by geometry error 8 termination by weight cut off 9 termination by time cut off 10 geometry boundary crossing 11 termination by energy cut off 12 termination by escape or leakage 13 nx reaction 14 nnmx reaction 15 sequential transport only for tally When NCOL 1 2 3 the output is finished The followings are for NCOL24 2 NOCAS NOBCH RCASC RSOUIN These four data are written only for NCOL 4 and their meaning are NOCAS current history number in this batch NOBCH current batch number RCASC realnumber of NOCAS maxcas NOBCH 1 RSOUIN sum of the weight of source particle 3 NO MAT ITYP KTYP JTYP MTYP RTYP OLDWT These mean NO cascade id in this history MAT material id ITYP particle type KTYP particle kf code JTYP
262. t of the cell section example 1 45 Cell section 79 When you treat some regions to make the cell definition Boolean operators are used Symbols Li blank and denote intersection AND union OR and complement NOT respectively as the operators Parentheses C and can be used to combine some regions The second example in this section uses Li blank and List 4 9 cell section example 2 1 cell 2 1 11 12 13 14 15 16 3 2 1 1 4 Surface 5 11 PX 6 6 12 PX 6 7 13 PY 6 8 14 PY 6 9 15 PZ 6 10 16 PZ 6 In the cell definition in the 2nd line the three numbers without minus symbol correspond to regions of positive sense of the 11th 13th and 15th surfaces and those with minus correspond to regions of negative sense of the 12th 14th and 16th surfaces Then a region surrounded by the 6 surfaces is defined with Li blank as the Ist cell which is the inside of a 12cm cube The outside of the cube is defined by the complement operator as the outer region Figure 4 11 shows the result of this example 10 a 5 of 1 void x L 10 10 5 0 5 10 z cm Figure 4 11 Result of the cell section example 2 The next example uses and parentheses The sphere in the 1st example and the cube in the 2nd example are combined List 4 10 ce11 section example 3 1 cell 2 1
263. ters for source energy distribution 2 parameter explanation e type 21 31 You can specify any energy distribution by giving data set of energy bins e i and differential probabilities of the particle generation dy dE i by hand The integrated number of the particle generation in the bin is proportional to dy dE i e i 1 e i and the specified energy distribution is Statistically described For 31 case energy is given by wave length A ne Number of energy group If it is given by positive number source particles are generated so that the energy differential fluxes in the unit of 1 MeV become constant in each bin On the other hand if ne is negative the fluxes in the unit of 1 Lethargy become constant in each bin Data must be given from the next line by the format as e i dy dE i i 1 ne 1 The integrated number of the particle generation in the each energy bin is proportional to dy dE i e i 1 e i e type 24 34 You can specify the same energy distribution as is the case of e type 21 31 Unlike e type 21 31 the distribution is described by giving data set of energy bins e i and weights of the source particle w i by hand The number of source particles generated in each bin is the same for all energy bin but integrated values of the weight of source particles are adjusted to be proportional to w i eCi 1 e i You can also change th
264. the next line Nucleus if you specify with mass Without mass all isotopes of Pb e type 1 2 3 4 5 energy mesh You need energy mesh subsection below this option t type 1 2 3 4 5 time mesh omissible You need time mesh subsection below this option unit 1 2 1 1 cm3 source 2 1 cm MeV source axis eng reg y Z X axis value of output data Xy YZ XZ IZ 2 dimensional file file name Define file names as same number of axis 6 12 T Star section Table 6 32 t star parameter 2 name value explanation resfile omissible D file Define a file name of the past tally in the restart calculation Even if several axis parameters were defined you should specify only one resfile output all star density for all reactions decay star density for decay reaction elastic star density for elastic reaction nuclear star density for non elastic Hydrogen HI fission star density for fission absorption star density for absorption heavyion star density for Heavy Ion reaction factor omissible D 1 0 normalization factor title omissible title angel omissible angel parameters 2d type 1 2 3 4 5 6 7 options for 2 dimensional plot omissible x txt omissible x axis title y txt omissible y axis title z txt omissible Z axis title gshow 8 default 1 2 3 4 When mesh xyz axis xy yz xz region bo
265. the photo nuclear reaction up to 1 GeV Results in the unit of Gy can be also obtained in t heat tally We corrected a bug that NaN was detected in the case of void regions We fixed a bug occurred when you set nm to be negative in source section using e type 2 3 5 6 7 12 15 16 which specify the energy spectrum by functional shape Furthermore we also fixed the similar bug for nn in the cases of a type 5 6 15 16 which specify the angular distribution by the shape From ver 2 65 dose in the unit of Gy can be obtained in t deposit tally Furthermore a bug in converting mass density to particle density in material and cell sections was fixed This bug caused errors 0 696 at the most in calculated results when neutron rich nuclei were used From ver 2 64 bugs in photo nuclear reaction model and EBITEM and other minor bugs were fixed Fur thermore NaN was detected in T Heat calculations because of negative values in the probability table p table The Ace libraries were re produced by neglecting p tables for the following 130 nuclides 5075 Bal30 Bal32 134 Bal35 Bal36 Bal37 140 Br079 Br681 Cd106 Cd108 Cd118 Cd111 Cd112 Cd113 Cd114 Cd116 141 142 143 144 Cf250 Fe059 Ga069 Ga8071 174 Hf176 Hf177 Hf178 Hf179 Hf188 Hf181 Hf182 I 127 I 129 I 130 I 131 I 135 In113 In115 Kr078 Kr080 Kr082 Kr083 Kr084 Kr085 1 138 La139 La140 Mo092 Mo094 Mo095 Mo096 Mo097 Mo898 Mo099 Mo100 Nb094 Nb6995 1059 141 P
266. the view point and light source are set same position 186 6 TALLY INPUT FORMAT 6 17 1 box definition Maximum 5 penetration boxes can be defined Defined boxes become transparent To define the box you first set three points as bo xo yo Zo bi1 x1 y 1 21 and b2 X2 y2 Z2 We define the 4 th point b from bo by L cm on the vertical direction of the plane defined by these three points i e b bo direction In this box definition you can use the coordinate transformation as trcl transform number or trcl before the definition of the points This function may fail when a void region is included in the penetration box In this case please fill the void region with a material of very low density e g air The box definition is shown below Each relations are also shown in Fig 6 8 box 2 box 0 20 1 yl 71 x2 y2 22 L box trcl 2 x0 yO 20 1 yl 71 2 y2 22 L box trc1 000 0 90 98 90 60 158 90 30 68 1 0 0 0 0 0 0 5 0 0 0 0 0 0 0 0 0 5 0 5 0 4 l X3 2 Zo X5 Ya 22 Figure 6 8 Example of box definition 617 T 3Dshow section 187 6 17 2 3dshow example List 6 6 t 3dshow example 1 cell 2 1 9 1 fill 1 3 2 0 41 42 43 44 45 46 u 1 fill 5 4 22 6 41 42 43 44 45 46 u 1 trcl 8 8 28 fill 6 5 23 like 22 but trcl 8 8 40 fill 7 6 5 6 21 22 23 24 25 26 u 5 lat 1 fill 3 7
267. this option part all default maximum 6 particles in a t let particle name material omissible You can specify materials for scoring all all default same as no definition When you set number of materials define these material numbers in the next line You can set number of materials by negative In the case specified materials are not included for scoring material numbers letmat omissible material id for LET dE dx If omitted real material is assumed If you select the material that is not used in your geometry you have to define its material density in material section If you would like to calculate LET in water you have to define water with 1 g cm in material sectiont When you set letmat 0 PHITS automatically calculates dE dx for water with 1 g cm for electrons and positrons Please see particletherapy in the recommendation setting in more detail l type 1 2 3 4 5 LET mesh You need LET mesh subsection below this option It is noted that the LET spectrum may have unnatural peaks when you set a very fine mesh e g 20 meshes per one order of magnitude 160 6 TALLY INPUT FORMAT Table 6 24 t let parameter 2 name value explanation unit 1 2 3 4 5 6 1 Track cm keV um source 2 Dose MeV keV um source 3 Track cm In keV um source 4 Dose MeV In keV um source 5 Track cm sou
268. ticles see Table 3 4 x y z are coordinates cm u w denote the unit vectors of the direction of the particle e is the energy MeV or MeV nucleon for nucleus wt is the weight time is the initial time ns c1 c2 c3 are the values of counters and sx sy sz are the unit vectors of the direction of spin respectively name is a collision number of the particle nocas is a current history number of this batch nobch is a current batch number no is a cascade id in this history These are assumed as real 8 for the binary data 1 1 24 15 data format for the ascii data For an example one record has 9 data as kf e wt x y gt v w To read this data we write the parameters as dump 9 18923456 7 When you use this dump parameter axis and file are restricted to one axis and one file and unit is always 1 The dumped data are written on a file named where indicates the file name specified by filez The normal output of the tally is written on From this file you can get the information on the total normalization factor In the former version of PHITS before 2 66 the normal output was written on a configuration file cfg and the dumped data were written on In the parallel computing files to the number of PE 1 corresponding to each PE Processor Element are created for writing and reading dumped data If you set idpara 0 or 1 a file is made in the directory named b
269. tion t dchain automatically creates t track and t yield as well as the input file of DCHAIN SP The t track tally calculates the neutron energy spectra below 20 MeV with 1968 energy group structure The t yield tally calculates the nuclear production yields by protons heavy ions mesons and neutrons with energies above 20 MeV In the DCHAIN SP calculation the neutron energy spectra are multiplied with the activation cross section con tained in the DCHAIN SP data library Then the total activations are estimated by adding these results and those di rectly calculated by PuiTS using the t yield tally After that DCHAIN SP evaluates radioactivity nuclide de cay heat and gamma energy spectrum at irradiation and cooling time Please see the A phits recommendation Vdchain folder in more detail You have to refer the document4 below when you use the results obtained by this tally in your publications By setting e mode 1 in the parameters section you can also calculate the yields of radioactive nuclides produced by low energy neutron reaction below 20 MeV using PuiTs instead of the activation cross sections con tained in the DCHAIN SP data library However the accuracy of the event generator mode in terms of calculating the residual nuclide yields has not been verified in comparison to that of the DCHAIN SP data library Thus we recommend to set e modez0 default in the PuiTS calculation using t dchain Note that the activations
270. tion volmat omissible D 9 The option corrects a volume value for each mesh when material is defined by xyz mesh 0 means no correction Value of volmat means the number of scans for one side of xyz mesh epsout default 1 If epsout is set to 1 results are plotted into eps files This eps file is named by replacing the extension into ctmin i omissible D 9999 minimum value for i th counter ctmax i omissible 9999 maximum value for i th counter trcl omissible coordinate transformation number or definition for r z or xyz mesh dump number of data For mesh reg the information is dumped on the file If dump is negative data are written by ascii if positive by binary next line data sequence define the data sequence gslat 1 default 0 1 show lattice boundary in gshow 0 no 155 In the t product tally you can use the dump option If the dump option is set the meshes of e type and t type have only the meaning of the maximum and minimum values When you use this dump parameter axis and file are restricted to one axis and one file and unit is always 1 The dumped data are written on a file named dmp where indicates the file name specified by file The normal output of the tally is written on From this file you can get the information on the total normalization factor To do so you had better set one mesh for e type a type a
271. tion energy and fission component When axis is 2 dimensional all is the same as simple Only total recoil ionization low neutron electron and others are output part particle name When you set output all deposit energies for ionization omissible and stopped particle specified here are output It should be noted that the results are not plotted in eps file omissible ionization and stopped particle are used as output unit 0 1 2 0 Gy source 1 MeV cm source 2 MeV source factor omissible D 1 0 normalization factor title omissible title angel omissible angel parameters 2d type 1 2 3 4 5 6 7 options for 2 dimensional plot omissible x txt omissible X axis title y txt omissible y axis title z txt omissible Z axis title gshow 8 default 1 2 3 4 When mesh xyz axis xy yz xz region border 1 material name 2 region name 3 and LAT number 4 are plotted by the option rshow default 1 2 3 When mesh reg axis xy YZ XZ region border 1 material name 2 and region name 3 are plotted by the option You need xyz mesh section below this option ginfo 0 default No geometry check in the case of gshow or rshow gt 0 1 Check geometry and draw its two dimensional view with error information 2 Check geometry draw its two dimensional view and outputting a geometry error file err resol 1 default The option mu
272. tive biological effectiveness RBE of charged particles However such microscopic probability densities cannot be directly calculated by PuiTs simulation using t deposit or t heat tallies since PuiTS is designed to simulate particle motions in macroscopic scale and employs a continuous slowing down approximation CSDA for calculating the energy loss of charged particles We therefore introduced a special tally named t sed for calculating the microscopic probability densities using a mathematical function that can instantaneously calculate quantities around trajectories of charged particles The function was developed on the basis of track structure simulation considering productions of rays and Auger electrons Note that the name of SED derives from Specific Energy Distribution Details of the calculation procedure are given elsewhere 819 Using this tally we can get information on probability densities of y and z in water We can also calculate the probability densities in different materials although the accuracy has not been checked yet Similar to t let the dose is only counted in an energy loss of charged particles and nuclei and thus we must use the event generator mode e mode 1 if we would like to transport low energy neutrons The deposition energy in microscopic sites can be expressed by deposit energy in MeV lineal energy y in keV um or specific energy z in Gy The definitions of these quantities are given in ICR
273. tle omissible title angel omissible angel parameters 2d type 1 2 3 4 options for 2 dimensional plot z txt omissible omissible X txt omissible X axis title y txt omissible y axis title Z axis title 164 6 TALLY INPUT FORMAT Table 6 28 t sed parameters 3 name value explanation gshow 8 default 1 2 3 4 When mesh xyz axis xy yz xz region border 1 material name 2 region name 3 and LAT number 4 are plotted by the option rshow default 1 2 3 When mesh reg axis xy yZ XZ region border 1 material name 2 and region name 3 are plotted by the option You need xyz mesh section below this option ginfo 0 default No geometry check in the case of gshow or rshow gt 0 1 Check geometry and draw its two dimensional view with error information 2 Check geometry draw its two dimensional view and outputting a geometry error file err resol 1 default The option multiplies region line resolution by resol times with gshow or rshow option width 8 5 default The option defines the line thickness for gshow or rshow option volume omissible The option defines volume for each region for reg mesh You need volume definitions below this option Default values are given in input echo in the case of no definition reg vol volume definition 5 1 2 iechrl 72 default Number of maximum column for volum
274. tran for Win dows In phits bin folder a solution file bin sIn and a project file phits intel proj are included which are required for compiling PuHiTS using Microsoft Visual Studio coupled with Intel Fortran You can compile PxiTs using these files as follows 1 Double click the bin sIn file This file may be automatically updated when you use a new version of Visual Studio or Intel Fortran You cannot open these files if you use an older version of Visual Studio before 2005 and or Intel Fortran before 11 1 2 Build phits intel vfproj in the release mode 3 Make an input file for PuiTS in the bin folder 4 Execute the project in the release mode 5 Type file input file name in the console window 6 Check whether track all eps is created or not If you want to compile 175 in the memory shared parallel mode you have to change a angel f to a angel winopenmp f in Source files of phits intel vfproj and add Qopenmp in the additional option window see project property Fortran command line before building phits intel proj If you want to use your compiled 1 using the sendto command please rewrite the environmental variable PHITS EXE written in phits bat e g set PHITS_EXE C phits bin Release phits intel exe Although you can also use the sendto command renaming the compiled to the original
275. ulation process source geometry error random seed and CPU summary I Input echo III Information on memory usage and batch IV Information on transport particles V Detailed information variance reduction number of scattered particles for each region and that for each material VI PHITS developers The information is outputted in the following order 1 LOGO Category I Note that only information of developers is category VI Version of PHITS developers job title and starting time 42 Parameters section 29 2 Input echo Category II Echo of input file 3 Information on used memory Category IIT Amount of used memory for geometry material tally bank and others 4 Information on batch Category III Number of history by each batch and CPU time 5 Information on calculation process ncol Category I Number of geometry boundary crossing reactions termination by energy cut off etc 6 Information on variance reduction Category V Particle weights changed by importance weight window and forced collision options 7 Number of scattered particles for each region Category V 8 Number of scattered particles for each material Category V 9 Number of transport produced stop and leakage particles Category IV 10 Number of source particles and their weight Category I 11 Geometry error Category I Number of lost particles and their kind 12 Random seed Category I Initial random
276. ulomb diffusion by Lynch s formula based on the Moliere theory 10 with Coulomb diffusion by ATIMA ascatl D 13 6 S parameter Lynch s formula for nspred 2 ascat2 0 0 088 e parameter in Lynch s formula for nspred 2 nedisp D 0 energy straggling option for charged particle and nucleus 0 without energy straggling 1 with Landau Vavilov energy straggling 10 with energy straggling for ATIMA e mode D 0 option for event generator mode 0 Normal mode 1 Event generator mode Ver 1 2 Event generator mode Ver 2 Until ver 2 73 file 14 trxcrd dat is required for e mode 1 2 When you set idwba added to neutron and proton spectra obtained with other nuclear reaction model for the following reactions 7Li p n Be reactions for 30 400 MeV Be p reactions for 10 50 MeV 7L i d n Li d p Li reactions for 10 50 MeV 27 1 discrete spectra calculated by DWBA Distorted Wave Born Approximation are Be d n B and Be d p Be reactions for 5 25 MeV 12 13C d and 12 5 d p I C reactions for 10 50 MeV gravx gravy gravz represent directions of gravity The gravity force acts on neutrons below eV For an example for gravx 1 gravy 0 gravz 0 case the direction of the gravity is negative direction of x axis It should be noted that the default option for ndedx was ndedx 8 until PuiTS ver 2 00 The option for ATIMA is under development and it takes very long cpu
277. ut cutoff data format The information for neutron photon electron positron and proton below the cut off energy can be written in the output file file 12 file 13 and file 10 in order to continue these transport calculation by other Monte Carlo codes such as MCNP and EGS4 The data are written in binary The format is shown below rd rn C data i i 1 nint abs rd rd rn data i i 1 nint abs rd H m 5 rd rn x y Z C eG u i v i wG rd rn x y Z C eG u i v i wG H m 3 Next incut 1 with importance option rd gt 0 m rd rn x z C eG uG vG wG wtG rd rn x 2 C eG 1 v i w i 1 incut 2 and no importance option rd 0 l m 5 w rd rn x y 2 C eG u i v i 1 t i i rd rn x y z C eG u i v i wG t i i 1 n incut 2 with importance option rd gt 0 rd rn x y 2 C eG u i v i w i wtG t i rd rn x y 2 C eG u i v i wG wtG t i H H Hog PR where n nint rn x y Zis a coordinate cm e i is an energy MeV u i v i w i is an unit vector of momentum wt i is an weight and t i is time ns In the case igcut 3 the particle identifier p Ci is written instead of t 1 in the case of incut 2 pCi 3 0 15 photon p i 4 0 is
278. uting PHITS 12 3 Questions related to Tally 12 4 Questions related to source generation 1 oncluding remarks 190 192 196 197 198 198 198 198 198 199 199 199 199 200 201 201 201 202 202 204 206 1 Introduction Particle and heavy ion transport code is an essential implement in design and study of spacecrafts and accel erator facilities We have therefore developed the multi purpose Monte Carlo Particle and Heavy Ion Transport code System 175 based on the NMTC JAMBP The physical processes which we should deal with in a multipurpose simulation code can be divided into two categories transport process and collision process In the transport process PHITS can simulate a motion under external fields such as magnetic and gravity Without the external fields neutral particles move along a straight trajectory with constant energy up to the next collision point However charged particles and heavy ions interact many times with electrons in the material losing energy and changing direction PHITS treats ionization processes not as collision but as a transport process under an external field The average dE dx is given by the charge density of the material and the momentum of the particle taking into account the fluctuations of the energy loss and the angular deviation The second category of the physical processes is the collision with the nucleus in the material In addition to the collision we consider the d
279. vival weight value wsurvn wupn mxspln D 5 maximum number of split maximum multiple number of survival mxspln gt 1 mwhere D20 where the weight window takes place at nuclear reaction 0 both 1 at region crossing Cut off time should be specified as tmax i nsec for each particle After elapsing the cut off time the particle is killed It is not effective to results for high energy particle transport but it is useful for low energy particle transport calculation Weight of a particle is changed by the importance forced collisions implicit captures and weight window functions When the weight takes lower value than user defined weight cut off the particle is judged if it is killed or not by the Russian roulette method This function is not available for particles defined in the weight window In the Russian roulette method when the weight WGT is lower than the product of WC2 and ratio R of two importances between at source point and at current point WC2 x R i e when WGT WC2 x R the particle survives with a probability WGT WC1Xx R which is a function of own weight WGT Then the weight is changed as WGT WC1 XR Unless the particle is killed If the WC1 and WC2 are given as negative WC1 x SWTM and WC2 x S WT M are set as WC1 WC2 If there are any particles and regions which are not set importance these importances are set as 1 42 Parameters section 4 20 5 Model option 1 Table
280. volume definition 5 1 2 iechrl 72 default Number of maximum column for volume input echo volmat omissible D 9 The option corrects a volume value for each mesh when material is defined by xyz mesh 0 means no correction Value of volmat means the number of scans for one side of xyz mesh epsout 0 default 1 If epsout is set to 1 results are plotted into eps files This eps file is named by replacing the extension into library number of materials Define library for each material omissible Format is shown later 157 158 6 TALLY INPUT FORMAT Table 6 22 t dpa parameter 3 name value explanation ctmin i omissible D 9999 minimum value for i th counter ctmax i omissible D 9999 maximum value for i th counter trcl omissible coordinate transformation number or definition for r z or xyz mesh gslat 1 default 0 1 show lattice boundary in gshow 0 no Format of library specification library number of material part proton emax 3000 mat fac lib mt 1 1 0 41 445 2 1 0 42 445 3 1 0 43 445 library number of material part neutron emax 3000 mat fac lib mt 1 1 0 41 444 2 1 0 42 444 3 1 0 43 444 Define particles for library use by part Neutron and proton are available in this version The emax defines the maximum energy of data from libraries If you skip part definition neutron is
281. w JQMD and R JQMD are the nuclear reaction models In particular heavy ions induced reactions can be de scribed by these models In 75 Ver 2 7 and later users can use R JOMD in alternative to the conventional JQMD R JQMD describes reactions particularly peripheral collisions more reasonably than JQMD Users should be aware that R JQMD may take twice or more CPU time than JOMD 3 Boudard J Cugnon J C David S Leray and D Mancusi Phys Rev C87 014606 2013 Y Sawada Y Uozumi S Nogamine T Yamada Y Iwamoto T Sato and K Niita Nucl Instr amp Meth B 291 38 44 2012 24 4 SECTIONS FORMAT 1MeV emin 3 0GeV emin i dmax i einclmax Nucleon Library INCL inclg 1 JAM 1MeV 3 0GeV emin i einclmax INCL inclg 1 JAM 10MeV u 3 5GeV u eqmdmin ejamqmd Nucleus JAMQMD d t He INCL inclg 1 Kaon Hyperon JAM Figure 4 1 Map of Nuclear Reaction Models 4 2 4 Cut off time cut off weight and weight window Table 4 5 parameter 5 parameter value explanation tmax i D 1 e 9 cut off time for i th particle nsec i 1 20 1 particle id see Table 3 4 1 1 D 0 5 minimum weight for i th particle wc2 i D 2wc1 2 cutoff weight for i th particle swtm i D 1 0 minimum source weight for i th particle wupn D 5 maximum value of weight window minimum value in Weight Window section x wupn wupn gt 2 wsurvn 8 6 wupn sur
282. with radius 4cm is not included In the next source it is also a cylinder source from z lcm to z 2cm with 5cm radius without r1 This is a normal thin cylinder The last one is also a thin cylinder from z 29cm to z 30cm with 5cm radius The numbers defined after each source denote the relative weight of the multi source In this example the relative weight is determined by the relative volume ratio of each source This means that the source particles are generated uniformly in each source volume The coordinate distribution of the generated source particles is shown in Fig 4 4 using t product tally with output source and icntl 6 T T 6 L Eu j 7 gl 3 E 7 10 E 5 or J E x 1 3 2 a 2 4 6 1 1 a 0 10 20 30 z cm TTT T 717 1 TT 6r 7 6 z 15om 7 4r 4r 2r 2r d T we 2 5 op 5 oL 4 E gt L RI 5 E 2 L Ja 2 L JIE Lau dau pad 6 4 2 0 2 4 6 6 4 2 0 2 4 6 x cm x cm Figure 4 4 Multi source coordinate distribution 43 Source section 69 The source particles of the multi source are proton photon and neutron In each subsection the energy dis tribution of the source particle is defined as Maxwellian Gaussian and user defined analytical function by using the expression of those function with Fortran style The first Maxwellian distribution is just equivalent to the expressio
283. with this parameter the following text should be written in the first line of input dat List 3 2 the first line of the standard input file input dat This method can be used on the other systems including the UNIX See section 3 3 for the infl parameter If you run the PxiTs code by the parallel computing the method shown in List 3 1 can not be used even on the UNIX system Instead you can use the List 3 2 method on the parallel calculation In addition is forced to read the input file named phits inon the parallel computing 2 8 Terminating the PHITS code Once PuiTs is executed it creates the batch now file The batch now file contains an elapse information after every batch It also contains each PE status on the parallel calculation You can check if PE abort is occurred by the batch now The first line of the batch now is written as 1 1 continue 0 stop If you change the value 1 into 0 the calculation will be terminated and the summary and results are provided for the histories until terminated It is an useful function shown in below Associated with the batch now a new parameter was included by the parameter section You can specify it as itall 2 D 8 O no tally at batch 1 same 2 different If you set itall 1 PxiTs outputs the latest results tally output after every batch On the parallel calculation results are created by every batch x 1 In the case of itall
284. xample using quadratic prism LAT 1 is shown below List 4 13 ce11 section example 6 1 Material 2 mat 1 1H 2 160 1 3 cell 4 1 0 11 12 13 14 15 16 FILL 1 5 101 0 26 25 22 21 LAT 1 U 1 FILL 2 6 201 1 1 0 90 U 2 7 2 1 1 8 Surface 9 11 PX 6 10 12 PX 6 11 13 PY 6 12 14 PY 6 13 15 PZ 6 14 16 PZ 6 15 21 PX 2 16 22 PX 2 17 23 PY 2 18 24 PY 2 19 25 PZ 2 20 26 PZ 2 21 98 BOX 10 10 10 2000 0 200 9 9 20 In the 5th line a unit cell with LAT 1 is defined using 4 surface numbers Setting U 1 the universe 1 is defined by repeated structures of this unit which is filled with the universe 2 defined in the 6th line Because a cross section of the unit in the x z plane has a square 4 cm on a side the 1st cell defined in the 4th line as a 12 cm cube has 9 blocks as shown in Fig It is noted that the unit has an infinite length in the y direction in the universe 1 because of using only 4 surfaces If you want to define a prism having a finite length you have to add 24 23 to the cell definition in the 5th line 10 TT TTTTTTTTTTTTTTTTT 5 F 0r J r water x L s 10 De 10 5 0 5 10 z cm Figure 4 18 Result of the cell section example 6 in 3D left and 2D right images 84 4 SECTIONS FORMAT To distinguish cells in the repeated structure each cell is on the lattice coordinate 5 t as shown in the right panel of
285. y wk uname on each of the nodes If you set idpara 1 or 3 the each IP number is put at the end of the filename The each PE writes down its result on only the corresponding file and reads it from the same file in the re calculation 5 8 Function to sum up two or more tally results 131 5 8 Function to sum up two or more tally results After version 2 74 PHITS has a function to sum up two or more tally results There are two methods for sum up one is to integrate the tally results considering the history number of each simulation while the other is to add the tally results weighted by user defined ratios The former can be used for the parallel calculation on computers in which MPI protocol is not installed On the other hand the latter is suit for the simulation with different source terms whose intensities cannot be fixed before the simulation such as that for Intensity Modulated Radiation Therapy IMRT In order to use this function you have to satisfy the following conditions e icntl is set to 13 in parameters section e The parameters for each tally results such as mesh axis and part are identical to one another e sumtally subsection is defined in the tally section that outputs one of the summing up tallies sumtally subsection is ignored when icntl parameter is not set to 13 in parameters section At this moment sumtally works only for t track and t deposit tallies and only one sumtally subsection can be de
286. y definition 13 t yield Residual nuclei yield tally definition t product Produced particle tally definition t dpa DPA tally definition t let LET tally definition t sed SED tally definition t time Time tally definition t star Star density tally definition t dchain Dchain tally definition t userdefined User defined tally definition t gshow Region surface display definition for graphical plot t rshow Physical quantity region display definition for graphical plot t 3dshow 3D graphical geometry plot definition end End of input file It is noted that PHiTS does not read any input informations which are written below the end section 32 1 2 3 4 5 6 Reading control Uppercase lowercase blank Discrimination between lowercase and uppercase characters is not performed in the PuiTS input except for file names Blanks at line head and end are taken no account except for the declaration of the Section Name as described before Tab A tab is replaced into 8 blanks Line connecting The maximum number of characters that you can write in a line is 200 If you add V at line end the next line is considered to be a continuation line You can use multiple lines to write input data by the V connecting But you don t need to use the V connecting in the ce11 and surface sections In these area line is connected autom
287. you the number of data in a record You put positive number for both ascii and binary put the ID numbers of data in a record You put ID for the data See kind of dump data and ID in Tables 5 3 5 4 put the file name of output You put the file name of output If the file already exists the program asks you whether the file can be overwritten or not Next the program asks you how many records are processed put the number of records to read all lt 0 or positive integer If this number is larger than total record number the program turns back to the top of the data Finally the number of records actually processed is shown When you make a program based on this program you should change iuser to 1 at 35 line in above list Then the program does not write the converted data on file In this case the output is written by ascii In 150 169 lines there are variables kf x y 7 v w e wt t nl n2 n3 sx sy sz nO nc nb no Here kf means the kf code of the particles see Table 3 4 x y z are coordinate cm v w denote the unit vector of the direction of the particle e is the energy MeV or MeV nucleon for nucleus wt is the weight time is the initial time ns c1 c2 c3 are the values of counters and sx sy sz are the unit vector of the direction of spin respectively By using these variables you can make a program to obtain desired quantities 196 9 OUTPUT CUTOFF DATA FORMAT 9 Outp
288. zation factor sumtally end Using this sumtally subsection you can obtain the results for maxcas 100 and maxbch 30 Please be sure that the initial random seeds for calculating result 1 out and result 2 out should be different from each other otherwise you would get biased results for certain random numbers The most recommended method for changing the initial random seed is to use irskip parameter The weighted value for each tally outputs are 132 5 COMMON PARAMETERS FOR TALLIES generally set to 1 for isumtally 1 unless you would like to change the weight of source particles The output file obtained from this sumtally section result s out can be used for restart calculation by setting istdev lt 9 For isumtally 2 the weighted summation of the tally results X is calculated by the following equation N X F Y X 2 75 Q j l where F is the normalization factor defined by sumfactor N is the number of summing up files defined by nfile X is the j th tally results r is the weighted value of j th tally and r is the sum of rj i e r xj rj The uncertainty of the summation value ox can be calculated by 3 where cx is the standard deviation of j th tally results If you have two tally results result l out and result r out and you would like to sum up them weighted by factors of 2 0 and 3 0 respectively you have to write List 5 4 example 2 for isumtally 2

Ver. 2.76 User`s Manual

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