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1. 3 cylinder X B x x Home End R gt px d Delete px 4 cylinder X x x inserty 1 5 outside X EI sw Pg up Pg Dwn 3 ok 5 a px 715 11 px 15 6 cx 10 px 20 t gx 20 2 ox 15 10 px 25 14 px 25 Geometry Sphere Cylinder slab Box X base center 10 Y base center Z base center Length 20 Radius 5 Axis ParalleltoX T Detta vwiath Mat Density Name sel core CylinderGeom1 5 224 7 872 cylinderShield1 delta5 El 252 11 35 cylinderShield2 delta5 224 7 872 cylinderShield3 delta5 Figure 2 3 Cylindrical Shield Geometry 2 3 Slab Shields To create slab shields select the Slab tab in the Geometry window and specify the minimum and maximum X location for the slab All slabs are created along the X axis These values define the first slab To add slab shields select New in the first column of the shield list and enter the thickness for the slab shield Once a user enters a thickness Nuc Wiz automatically offers another line designated New Next click in the Mat column to set a material for this shield see Section 3 for more information on setting materials Other shields can be added by clicking on New in the first column for each additional shield and setting the thickness and material as was done for the first shield To create the geometry select Update at the top of the Geometry window and NucWiz c
2. Source Close Update Delete selected Point Sphere cylinder Box Name mte oen x y z Raus 1 SPHSrci 204 0 001225 10 New wet Enter Energy Spectrum Below spacestab delimited energy particles sec Histogram Bins gt Figure 2 5 Spherical Source Configuration Page 10 Phase Final Report Graphical User Interface for Simplified Neutron Transport Calculations Figure 2 6 shows a plot of the geometry and input file created for a cylindrical source configuration NucWiz created the SDEF in the input file to correspond to the cylindrical source f mcshield mcshield1 File Geometry Source Physics Tallies Input Run Edit View Window Help nag e amp t Formatting error in routine padstring incoming string length 2 c File Created by meshield exceeds max length1 d 3 1 2 cyLsre 1 Formatting error in routine padstring incoming string length 2 2 4 3 1 2 outsideworld exceeds max length1 DUI 3 4 S outsideworld Formatting error in routine padstring incoming string length 2 Wi mcshield1 Click in the Plot Window tousethesek Jc Num Name show Color soia Trans wire aoe zA sgh gens 1 CYLSrIc1 X x x up down P 2 ousie X x Alt Home Alt End 2 px 10 HomeX End 3 x 10 insert Delete ej je Pg upXPa Dwn Surfaces for cell ou
3. Overwrite outp metal runtpe etc files inp sphere geom Browse name Sphereout outp NEED runtpe metal Figure 10 2 Specifying the Input and Output File Names 40 The user must now select the location of the executable by clicking on the Command gt button and selecting the appropriate MCNP executable This executable can either be an MCNP5 executable or an MCNPX executable because the geometries being created are compatible with both versions of MCNP Execute MCNP Close Run WordPad Current Directory gt F SBIR_DOE_2008_phase1 manual C Program Files LANLIMCNPStbiniindows menpS exe Overwrite outp metal runtpe etc files inp sphere _geom Browse name Sphereout outp runtpe metal sid Figure 10 3 Selecting the Executable to Run In this example the MCNP5 executable was selected stored in the C Program Files LANL MCNPS bin Windows directory Once the command to be run and the input file have been indicated NucWiz can run the file 41 To run the file select Run in the Run window which will bring up a command prompt window to run the specified file using the executable defined in the Run window ri sphere geom mcshield Dc 8 c File Created by meshield FOUND stndrd n using DATAPATH ENVIRONMENT VARIABLE gt C Program Files LANL Vised stndrd n T 204 0 001225 1 3
4. A mcshield mcshield1 File Geometry Source Physics Tallies Input Run Edit Yiew Window Help iDea i sea exceeds max lengthi Formatting error in routine padstring incoming string length 2 exceeds max length Formatting error in routine padstring incoming string length 2 exceeds max lengthi WP mcshield1 bm Nene show coer sois ane vie ur 1 SPHSrc1 X H x x upy down a jc File Created by meshield 2 outside X x Alt Home Ait End i n 1 SPHSre 1 HEIKE xe 2 2 1 Soutsideworld MESURE a 2 Soutsideworld Input Edit e Surfaces for cell SPHSre 1 Z so 25 98076 sdef cel 1 rad dl sil L o 10 spl EL e Tally information created by NucWiz nps 100000 Source Point Sphere cylinder Box Name Mat Den x 1 SPHSre 1 204 0 001225 New wer Enter Energy Spectrum Below spacestab delimited energy particlesisec Histogram Bins hd Figure 5 5 Spherical Source Configuration 19 5 3 Cylinder Source To create a cylindrical source select the Cylinder tab in the Source window then click on New in the first column Specify the X Y and Z location for the center of the base of the cylinder the direction for the axis of the cylinder and the radius and length Select Update to create the source and update the input file Figure 5 6 shows an input file for a cylinder source with the center of the base at x 10 y 0 and z 0
5. OUND stndrd p using DATAPATH ENVIRONMENT VARIABLE Ci Program FILAM Wised stncrd p 2 7 872 2 1 S8phereshieldi deltas 11 35 3 2 S 8phereBhield2 delta 7 872 4 3 8phereShield3 deltas 5 4 Soutsideworld 5 Soutsideworld Surfaces for cell UphereGeoml sy 7 5 59 174 6000 60c 0 0006 carbon steel with ENDF VI 25055 60c 0 0035 26054 60c 0 056755 26056 60c 0 91493 26057 60c 0 021323 26058 60c 0 002893 82206 60c 0 242902 Slenad 82207 60c 0 223827 82208 600 0 53327 Sphere Cyinder siab Bax 9 14 PPA SSS or A SS Sor X center Y verter Rasus 10 Figure 2 2 Spherical Shield Geometry Page 7 Phase Final Report Graphical User Interface for Simplified Neutron Transport Calculations Figure 2 3 shows a cylindrical shield geometry with a central cylindrical volume and three cylindrical shields The input file is displayed along with the cylindrical geometry creation panel f meshield mcshield1 File Geometry Source Physics Tallies Input Run Edit View Window Help DSH 568a c File Created by mcshield X 3 1 8 CylinerGeoml 2 224 7 872 6 4 11 3 1 8 cylinderS8hieldl delta5 3 252 11 35 9 7 13 6 4 11 cylinderShield2 delta5 4 224 7 872 12 10 14 9 7 13 cylinderShield3 delt 5 6 FOUND stndrd n using DATAPATH ENVIRONMENT YARIABLE gt C Program Files LANL Vised stndrd n FOUND stndrd p using DATAPATH ENVIRO
6. Box Pa Name Surfacenumbers 0 0 0 0 0 0 0 2 n SurfTal 2 Box Object 1 Max Z i2 n SurfTal 12 5505 gt New Box Object2 gt Box Object 2 All 1 Box Object 2 Min X Box Object 2 Min Y Box Object 2 Min Z Box Object 2 Max X m h2 Box Object 2 Max Y mem El Additional Data Tally Box Object 2 Max 2 mremjhr w Figure 6 6 Selecting a Surface of a Box to Tally On Similarly if the object is a cylinder a list of cylinder surfaces to tally on is displayed as shown in Figure 6 7 Close Update Delete_Selected Click New to add a new tally Point Surface Sphere Cylinder Box Pa Name Surfacenumbers 0 0 0 0 0 O 2 n SurfTal 2 Cylinder Object 1 Bottom Cylinder Object 1 gt ITT me New EEVUNUETUENE Cylinder Object 2 All UU cylinder Object 2 Top Cylinder Object 2 Bottom Cylinder Object 2 Side Additional Data Tally 12 Conversion Factor None mremfhr Figure 6 7 Selecting a Surface of a Cylinder to Tally On 27 When the user selects Update Nuc Wiz creates the surface tallies with the correct surface numbers used in the tally description Figure 6 8 shows the input file with the surface numbers indicated on the surface tally lines Notice that only one surface is currently allowed per tally number Close Edit e Surfaces for cell outsideworld m2z04 7014 70 0 755636 Sair US 8 Atm at sea level 8016 70c 0 231475 18036 70c lt 3 98 0
7. C Program Files LANLlVisedlstndrd p File Not Found usr n File Not Found usr p VW mcshield1 Name Sphere Spheres RPPSre 1 outside Show Color Solid x x x x x x Trans Wire x Click in the Plot Window to use these oc upXdown Alt Home Alt End Home End Insert Delete Pg up Pg Dwn ic Surfaces for cell RPPSre 1 mode p sdef cel 3 x dl y dZ z d3 sil H L i spi D QL si2 H I 1 sp2 D ui si3 H zt i sp3 D 0 1 m204 7000 02p 0 755636 Sair US 8 Atm at sea level 8000 02p 0 231475 18000 02p 0 012889 228 1000 02p 0 005558 concrete ordinary with ENDF VI 8000 02p 0 4980765 11000 02p 0 017101 12000 02p 13000 02p 0 045746 14000 02p 0 3150923 16000 02p 19000 02p 0 019239 20000 02p 0 0829411 26000 02p s ica Tally information created by NucWiz fc5 PDetTal 5 f5 p 15 0 0 5 fci5 PDetTal 15 f15 p 0 15 0 5 Click New to add a new tally Point Surface Sphere Cylinder Box Pec Name x 5 P PDetTal S 15 5 15 p PDetTal 15 15 5 New Conversion Factor None v mremhr v Additional Data Tally 15 Figure 6 4 Point Detector Tallies Added to the Input File 25 6 2 Surface Tallies To add surface tallies to the input file select the Surface tab in the Tallies window click on New and enter the parameters Once a user enters the pa
8. Trans Wire Click in the Plot Window to use these key functions 2 2 Yaw Sphere X Oo x up down Move Toward SphereS X in Alt Home Alt End Pitch sourceb X LI Home End Roll 7 insert Delete Rotate Vert outside x Pq upXPg Dwn Rotate Horiz Update xYZ hd Materials 3 outsideworld Figure 2 14 Three Dimensional Geometry Window Note that all geometries appear as a sphere because NucWiz creates the outside world and this is always outside a sphere By default this outside world is set to a transparent sphere because typically this sphere is not of interest to the user Page 19 Phase 1 Final Report Graphical User Interface for Simplified Neutron Transport Calculations On the top of the plot window is a list of the bodies that have been created The numbers listed do not refer to cell numbers but to object numbers NucWiz gives a default name to each of the objects These names can be changed to something more meaningful to the user In this example the objects are listed in nonsequential order 1 2 4 3 but in the input file these objects are assigned cell numbers that are sequential 1 2 3 4 So it is important to not confuse the object number with the cell number With NucWiz cell numbers are only assigned on creation and until that time different elements are referred to with these object numbers WP sphere_geom mcshield mum Neme Stew car Sait mene wwe Cicki the Pot Wind
9. 005558 concrete ordinary with ENDF VI 8016 70c 0 498076 11023 70c 0 017101 12024 70c 0 001999 12025 70c 0 000264 12026 70c 0 000302 13027 70c 0 045746 14028 70c 0 289486 14029 70c 0 015181 14030 70c 0 010425 16032 70c 0 001216 16033 70c 1e 005 16034 70c 5 7e 005 16036 70c 0 19039 70c 0 01788 19040 70c Ze 006 19041 70c 0 001357 20040 70 0 08019 20042 70c 0 000562 20043 70c 0 00012 20044 70c 0 00188 20046 70c 4e 006 20048 70 0 000186 26054 70 0 000707 26056 70 0 01139 26057 70 0 000265 26058 70 3 6e 005 e Tally information created by NucWiz nos 100000 Source Box Close Additional User Data mps 100000 Problem Mode ivi gt neutron anit neutron gt electron positron Figure 4 1 Setting the Problem Mode 13 The user can also change the problem mode from N to P by only selecting the P check box in the Problem Mode panel In the example below the mode has been set to P and the user has selected Apply Notice there is now a mode p line in the data section and all the neutron cross sections have been replaced with photon cross sections 14 mcshield mcshield1 File Geometry Source Physics Talies Input Run Edit View Window Help E input insu vest cm FOUND stndrd n in CURRENT DIRECTORY c File Created by mcshield FOUND stndrd p using DATAPATH ENVIRONMENT VARIABLE gt C Program
10. Element Zaid Fraction Percent 1 Hydrogen 1001 70c Se 005 8 Oxygen 8016 70c 0 000717 11 Sodium 11023 70c 0 008735 12 Magnesium 12024 70c 0 00016 12 Magnesium 12025 70c 2 1e 005 12 Magnesium 12026 70c 2 4e 005 16 Sulfur 16032 70c 0 000151 16 Sulfur 16033 70c 1e 006 1 C dl i 1 02A4 We Te NNE lli Figure 2 12 Material Library Window 2 6 Running Files Created in NucWiz Once an input file has been created it can be run inside NucWiz The user selects the input file to run and the executable to use either MCNP5 or MCNPX and then selects the Run option Page 17 Phase 1 Final Report Graphical User Interface for Simplified Neutron Transport Calculations Figure 2 13 shows an example of running an input file created by NucWiz using the MCNP5 executable Complete details on running files created in NucWiz can be found in Appendix A Execute MCNP Close Run WordPad Current Directory gt F XSBIR DOE 2008 phase1ttest Command gt C Program Files ANLWMCNPSbintvindowsWmncnps exe Overwrite outp metal runtpe etc files AMI box shid EDEN command executed successfully mE Ld CProgram FilesiLANLMECNPSbiniAindowsmnenp5 exe inp box_s name jbox shld outp runtpe metal Figure 2 13 Running the NucWiz Input File 2 7 NucWiz Plot Options NucWiz implements DirectX for all geometry visualization DirectX comprises the graphics libraries developed by Microsoft for three dime
11. HomeXEnd c File Created by mc Insert Delete 1 204 0 00122 Pg upXPa Dwn 2 228 22 8 3 0 4 0 m204 7014 70c 0 755636 air US S Atm at sea level 8016 70c 0 231475 18036 70c 3 9e 005 18038 70c 8e 0t 18040 70c 0 012842 228 1001 70c 0 005558 concrete ordinary with ENDF VI 8016 70c 0 498076 11023 70c 0 017101 12024 70c 0 0019 12025 70c 0 000264 12026 70c 0 000302 13027 70c 0 0457 14028 70c 0 289486 14029 70c 0 015181 14030 70c 0 01047 16032 70c 0 001216 16033 70c 1e 005 16034 70c 5 7e OC 16036 70 D 19039 70c 0 01788 19040 70c Ze 0t 19041 70c 0 001357 20040 70 0 08019 20042 70c 0 0005t 20043 70c 0 00012 20044 70c 0 00188 20046 70 4e amp Dt 20048 70c 0 000186 26054 70 0 000707 26056 70 0 011 26057 70c 0 000265 26058 70 3 6e 005 c Tally information created by NucWiz nps 100000 Additional User Data nps 100000 Figure 3 4 Creating the Geometry and Updating the Input File At any time the user can cancel the creation process by closing the Geometry window without selecting Update thus clearing out all of the geometry information in the window and allowing the user to start over from the beginning To edit an existing geometry change either the dimensions or the materials to different values in the Geometry window and select Update 12 4 Setting the Problem Mode The user can set the mode for the problem by selecting Physics and then Mode fr
12. Input Run Edit View Window Help C E Coed se ea c File Created by mcshield 1 0 123 4 5 6 BoxGeoml 2 224 7 872 7 8 9 10 11 12 BoxShieldi delta5S FOUND stndrd n using DATAPATH ENVIRONMENT VARIABLE gt C Program Files LANL Visedlstndrd n FOUND stndrd p using DATAPATH ENVIRONMENT YARIABLE gt C Program Files LANL Visedistndrd p File Not Found usr n File Not Found usr p C1 2 3 4 5 6 3 252 11 35 13 14 15 16 17 18 BoxShield2 delta5 77 8 9 10 11 12 4 224 7 872 19 20 21 22 23 24 S BoxShield3 deltaS 713 14 15 16 17 18 E mcshield1 Num Name Show cor soia Trans Wire 5 0 25 19 20 21 22 23 24 outsideworld 6 0 25 S outsideworld 1 BoxGeo X x x up down 2 BoxShiel X x x Case Fs 10 1010 12102 22 v v sun 3 BoxShiel X x x _ HomeXEnd e 4 BoxShel X x x insert Delete c Surfaces for cell BoxGeoml 8 mise ly wj Pa upg Dwn i fe n 1 px 2 5 2 py 5 3 pz 7 5 4 px 2 5 5 py 5 8 pz 7 5 ni Geometry Sphere Cylinder slab Box X center Y center Zeenter Xlength 5 Yiength 10 Ziength 15 Deta width Mat Density Name core BoxGeomi 224 7 872 BoxShield1 delta5 252 4135 BoxShield2 dettaS 224 7872 BoxShield3 delta5 Figure 2 4 Rectangular Parallele
13. Sieverts To add surface tallies to the input file the user can select from a list of tally volumes and then specify the surface to tally on In Figure 2 8 the object is a box when the user clicks on the Surface numbers column NucWiz displays a list of objects When the user selects an object NucWiz displays a list of box surfaces to tally on The surface is not a number but a surface location on the object Close Update Delete Selected Click New to add a new tally Point Surface Sphere Cylinder Box Box Object 1 Max Z Box Object1 Ts gend Box Object 2 Al Box Object 2 Min X Box Object 2 Min Y Box Object 2 Min Z Box Object 2 Max X Box Object 2 Max Y Additional Data Tally 12 Conversio Bo Object 2 Max Z mremihr Figure 2 8 Creating a Surface Tally Page 13 Phase Final Report Graphical User Interface for Simplified Neutron Transport Calculations Figure 2 9 shows a plot of the geometry and input file created for a spherical tally configuration consisting of three volume tallies NucWiz created the geometry and tally definitions in the input file to correspond to these tallies The panel used to create these tallies is also shown A meshield mcshield1 E input Eile Geometry Source Physics Tallies Input Run Edit View Window Help C IDag ses c File Created by mcshield FOUND stndrd n using DATAPATH ENVIRONMENT VARIABLE gt C Program Files LANL Wised stndrd n 1 D 1 SPHTal 4
14. a radius of 10 cm and a length of 20 cm parallel to the X axis A mcshield mcshield1 File Geometry Source Physics Tallies Input Run Edit View Window Help Dea s e 6 t Formatting error in routine padstring incoming string length 2 c File Created by mcshield exceeds max length1 i 3 1 2 cyLsre 1 Formen er ree padstring incoming string length 2 2 4 3 1 2 Soutsideworld s 3 a 4 S outsideworld mcshield1 Surfaces for cell CyLSre 1 Click inthe Plot Windowtousethesek e show color soia Trans wire ene Yaw i AS Sg 1 cyYLSret X x x up down P 2 outside X x Alt Home At End 2 px 10 HomeX End d x 10 insert Delete e WU BE BEBO LER Pg upXPg Dwn c Surfaces for cell outsideworld 4 so 25 98076 sdef axs 1 0 O0 cel 1 ext d1 pos 10 rad d2 L 0 20 2i 0 L 0 10 Source Point Sphere Cylinder Box Name Mat Den Y Base Z Base Len_ Rad Axis Sel CYLSrc1 204 0 001225 10 20 10 Parallel to X New wer Enter Energy Spectrum Below spacefab delimited energy parlicles sec Histogram Bins 7 Figure 5 6 Cylindrical Source Configuration 20 5 4 Box Source To create a box rectangular parallelepiped source select the Box tab in the Source window then select New in the first column Specify the X Y and Z location for the center of each box and the le
15. sea level 0 001225 Sphere Cylinder Slab Box o 208 aluminum 2 699000 212 beryllium metal 1 850000 216 beryllium oxide BeO 3 025000 zem 220 boron natural 2 450000 X center Y center 224 carbon steel with ENDF VI 7 872000 228 concrete ordinary with ENDF VI 2 350000 Radius 5 232 concrete magnetite with ENDF VI 3 530000 236 graphite 1 700000 v Deta Width Met Density Name Sel lt aF 0 001225 E m Number User Materials Density JEJ Element Zaid Fraction Percent Figure 3 2 Adding Materials to the Geometry Shields To view materials and their compositions the user should select the Materials button in the main window The material name and density are shown in the upper portion of the Materials window and the composition of the material selected is shown in the lower portion of the window In the example in Figure 3 1 air has been added to the inner geometry region of the sphere Currently the user cannot create new materials but can only add materials that exist in the material library If new materials are needed it is recommended that the user create these materials using the MCNP Visual Editor and save these materials to the user library which can then be read by NucWiz If the Materials window does not show any materials then NucWiz cannot read the material files The material files are named stndrd n and stndrd p NucWiz can find the material files if they ar
16. stndrd p using DATAPATH ENVIRONMENT VARIABLE gt C Program Files LANL Vised stndrd p File Not Found usr n File Not Found usr p DAK A Click in the Plot Window to use these key functions X Yaw 1 sci x W x x up down 3 RPPTa4 X x x Alt Home Ait End 4 RPPTeH14 X x x piu Gr Clos Update D lete selected 5 RPT X x x Insert Delete ss Upd 5 RPPTala4 X r1 x x w owXPaDwm Point Sphere cylinder Box 1 SPHSre 1 5 New WGT Enter Energy Spectrum Below spaceftab delimited energy particlesisec l Histc Tallies Delete Selected lose Update Click New to add a new tally Point Surface Sphere Cylinder Box Additional Data Tally 34 Conversion Factor None Figure 6 7 Creating Box Cell Tallies 30 7 The Input File and Inserting Additional User Data The NucWiz input file can be displayed by selecting Input from the main menu The generated input file includes all elements that have been created Because NucWiz completely controls the creation of the input file the user is not allowed to modify the input file Instead the user must bring up the appropriate NucWiz window to modify the element and then select Update to change the input file NucWiz will not support all of the user data options To accommodate user data not supported by NucWiz the user can enter additional data information in the Additional User Data portion a
17. the example below a box source is created inside the existing sphere geometry which has a length of 2 in X Y and Z 15 Even though New is displayed in the second row only one source is allowed and clicking on the second row will not allow for the creation of a new source in this release Source Close Update Delete selected Point Sphere Cylinder Box Name Met Den Xcent Ycent Zcent Xien Yien Zien sel irt LU a HAE Pes SA MESA een a ICONE New wot Enter Energy Spectrum Below spacestab delimited energy _particles sec Histogram Bins Figure 5 2 Creating a Rectangular Source The material for the source can be specified by clicking in the Mat column in the core row which brings up the Materials window as discussed in Section 3 To create the source add its description to the input file and update the plot the user selects Update NucWiz inserts the source geometry and source description SDEF into the input file as shown below 16 14 mcshield mcshield1 Eile Geometry Source Physics Tallies Input Run Edit View Window Help Dea s eS t IFOUND stndrd n in CURRENT DIRECTORY FOUND stndrd p using DATAPATH ENVIRONMENT VARIABLE gt C Program Files LANL Vised stndrd p File Not Found usr n File Not Found usr p 4 9 2 Goutsideworld 5 9 Soutsideworld Wi mcshield1 Surfaces for cell SphereShieldl del
18. the name indicated in the Save As window and a NucWiz file is saved containing all the information NucWiz needs to recreate the input file To read a file back into NucWiz the user must read in the NucWiz file NucWiz does not recognize MCNP input files In this example the file is saved with a name of sphere geom 38 10 Running MCNP from Inside NucWiz To run the MCNP input file that has been saved select Run from the main menu which will bring up the window shown below The user can now specify the input file by selecting the Browse button next to the inp field and selecting the input file Execute MCNP Close Run WordPad Current Directory gt Command gt Overwrite outp metal runtpe etc files inp Browse names outp i runtpe n mtas Figure 10 1 Run Window 29 For the example below the sphere geom input file is selected from the file browser Notice that the directory for the input file is set in the Current Directory gt field at the top of the window The input file and directory can also be set by selecting the Current Directory gt button which will also bring up a file browser to select the input file If desired the user can now set the names of the output files to be generated In this case the name field has been set to Sphereout Execute MCNP Close Run WordPad Current Directory gt F SBIR_DOE_2008_phase1 manual Command gt
19. 000 sp2 D D at si3 H 1 000000 sp3 D i m2z04 7014 60c z 8016 60 Dz mz28 1001 60c gil 8016 60c U 13027 60 zs 19000 60 xls 26056 60 cd impire ids 1 dup Additional User Data c File Created by mcshield 1 438 4 5 5 6 7 B 8phereGeoml 2 1 8phereShieldi deltas 4 5 6 7 8 S sourceboxi 2 Soutsideworld Soutsideworld 1 000000 1 000000 1 000000 755636 Gair US S Atm at sea level 231475 18000 59c 0 012889 005558 conerete ordinary with ENDF VI 498076 11023 60c 0 017101 12000 60c D45746 14000 60c 0 315092 16000 60c 019239 20000 60c 0 082941 26054 60c 0 01139 26051 60c 0 000265 Z6058 60c O zi t zu 002565 001283 000707 6e 005 lt Figure 7 1 Appending Additional User Data to the Input File Note that the user can copy text out of a Word document and paste it in the Additional User Data portion of the Input window This portion of the window also allows the user to copy text from an existing MCNP input file and append it to the NucWiz input file 32 8 NucWiz Plot Options NucWiz implements DirectX for all geometry visualization DirectX comprises the graphics libraries developed by Microsoft for three dimensional geometry visualization NucWiz is designed using the DirectX 9 0c libraries allowing for backwards compatibility with the Windows XPO operating system Higher library versions only work with Windows Vista and Windows 7 To use NucWiz th
20. 05 18038 702 8e 006 18040 70c 0 012842 m228 1001 70 0 005558 concrete ordinary with ENDF VI 8016 70c 0 498076 11023 70c 0 017101 12024 70 Dgl1995 12025 70c 0 000264 12026 70c D 900302 13027 702 0 045746 14028 70c 0 289486 14029 70c 0 015181 14030 70 0 010425 16032 70c 0 001216 16033 70c 1e 005 16034 70c 5 7e 005 16036 70c 0 19039 70c 0 01788 19040 70 Ze 006 19041 70c 0 001357 20040 70c 0 08019 20042 70 0 000562 20043 70c 0 00012 20044 70c 0 00188 20046 70 4e 006 20048 70c 0 000186 26054 70 0 000707 26056 70 z 0 011398 26057 70c 0 000265 Z6058 70c 3 6e 005 e Tally information created by NucWiz fc5 PDetTal 5 f5 n 15 B 0 5 FiS PDetTal 15 fl5 n 0 dy 5 f2 n T Eca SurfTal 2 fAi2 m 2 Eez SurfTal 12 Additional User Data nps 100000 Figure 6 8 Surfaces Tallies Inserted in the Input File 28 6 3 Cell Tallies To add cell tallies select one of the cell tally tabs Sphere Cylinder or Box Figure 6 9 shows four sphere cell tallies arranged around a central spherical source When creating a sphere cell tally specify the X Y and Z location and radius of the cell NucWiz creates the sphere cell and inserts it in the geometry then creates a tally that specifies this cell Cell tallies cannot be specified on geometry cells only on the generated cells created specifically for the tally P mcshield mcshield1 Elle Geometry Source Physics Tallies Input Run Edit Vie
21. 1 Execute MCNP Close Run WordPad Current Directory F SBIR_DOE_2008_phase1 manual Command gt C Program FilesL ANLWCNPSbint lndowsmncnps exe Iv Overwrite outp metal runtpe etc files command executed successfully inp sphere geom Browse C Program Files L ANLYMCNPS bintindows mcnpS exe inp sphere Figure 11 1 Displaying the Output File iis 43
22. 4 5 6 7 FOUND stndrd DATAPATH ENVIRONMENT VARIABLE gt C Pr Files LANL Vised stndrd 5 7 e 3 stndrd p usina Proaram FileslLANL Wisedlstndrd p Sede pz esphere tieldiidelteS File Not Found FT File Not Found Akosi Aou s elo Ip x 4 5 6 7 8 ssourceboxt ERROR NULL eyga ld 07112 G a P 2 Soutsideworld outsideworld 8 8phereGeoml in this problem comment using random number generator 1 initial seed 19073486328125 imcn is done ctm C a dump i on file runtpe nps coll a xact is e cp 8 0 run terminated when 18880880 particle histories were done 1 000000 ctm 6 02 nrn 2 2 i s S BABAE dunp on file runtpe np 190084 coll 1 000000 si3 H 1 000000 1 000000 sp D 01 m204 7014 60c 0 755636 Gair US S Atm at sea level 8016 60c 0 231475 18000 59c 0 012889 m22R 1nnt Ane N ANSSSA ennerete nrdinarv with RNDF UTY Additional User Data impin 11110 print nps 100000 Exec m MCNP Current Directory gt FASBIR DOE 2008 phase1Wmanual Command gt C Program FilesiL ANLCNPSlbintWindows mncnp5 exe jv Overwrite outp metal runtpe etc files command executed successfully inp sphere geom C Program FilesiLANLIMCNPShbint indowstmcnpS exe inpesphert name outp runtpe metal Figure 10 4 Executing the Nuc Wiz Input File The user can also select the Overwrite check box in the Run window which te
23. APATH ENVIRONMENT VARIARE gt Cil Program FledLANLIVieedtn rd o le Not Found utr n le Not Found utr p Charr ame delete object Vet struet using ID An wild ID was passed to this routine Click in the Plot Window to use these hey functions XK Yow File Created by mcshield upXdmwn Move Toward 0 3 8PHTa1 4 AtMomekAREnd Pech 2 224 7 072 1 2 4 SalabGeomt ramen 0 4 3 1 2 outsidewo EPOD uA 4 71 2 outsidewor fg uoXFg Own Rotate Horiz 4 Soutsideworld r cell SPHTal 4 r cell outsideworld 20 17 5 61 16065 sdef cel 1 pos 0 0 0 m224 6000 60e 0 0006 carbon steel with ENDF VI 25055 60c 0 0035 26054 60e 0 056755 26956 60c 0 91493 26057 60c 0 021323 26058 60c 0 002893 Tally information created by NucWiz f4 n fc SPMTal 4 nps 100000 Additional User Data nps 100000 Figure 2 1 The NucWiz Main Window 2 2 Supported Shielding Configurations Because NucWiz is intended to be a simplified neutron transport calculation tool only a limited set of geometric configurations are available An initial geometric set of shields was developed consisting of slabs spheres boxes and cylinders For all of these geometries the graphical user interface GUI creates a large outside world sphere to contain the geometry The sphere is large enough to contain the source geometry and tally regions The initial set of geometries include the following 1 Noshield geo
24. FOUND stndrd p using DATAPATH ENVIRONMENT VARIABLE gt C Program FilesiLANLYisedlstndrd p 2 uU 2 SPHTal 14 Fie Not Found ux p 3 8 X a a EE 4 o 4 1 2 3 GSoutsideworld 5 0 4 Goutsideworld WP mcshield1 IMMER a TI EE E Click in the Plot Window to use thesekf c Surfaces for cell SPHTal 4 SPHTal4 Naan Mae EC dx cru c D I SPHTal14 At Home AIt End i E CNN S 2y SPHTal 24 Home End a4 aa AG MIC ail a es ae Oddo Insert Delete e e Surfaces for cell SPHTal 14 Pg up Pg Dwn e 2 sy 50 10 ie SASA e Surfaces for cell SPHTal 24 d eee Edo OU Mee scc 3 sz 50 10 EST SaaS a a SSS e Surfaces for cell outsideworld amc ee a aasan 4 s 25 25 25 90 93266 e Tally information created by NucWiz f4in i fc4 SPHTal 4 fl4 n 2 fcl4 SPHTal 14 f24 n 3 fc24 SPHTal 24 Tallies Click New to add a new tally Point Surface Sphere Cylinder Box SPHTal 4 14 n SPHTal 50 10 24 n SPHTal 50 10 New E i Additional Data Tally 24 Conversion Factor None E n Figure 2 9 Spherical Tallies Page 14 Phase Final Report Graphical User Interface for Simplified Neutron Transport Calculations Figure 2 10 shows a plot of the geometry and input file created for a cylindrical tally configuration consisting of three volume tallies NucWiz created the geometry and tally definitions in the input file to correspond to these tallies The panel used to create these tallies is a
25. Files LANLlVisedlsl aq 204 0 001225 1 SphereGeoml File Not Found usr n IFile Not Found usr p 2 228 22 35 2 1 SSphereShieldl deltas 3 3 2 outsideworld 4 3 S outsideworld E mcshield1 UM eee ese ee ees Num Name Show Color Solid Trans Wire e Surfaces for cell SphereGeoml 1 Sphere X x x upy do C ARS TSR Se ena ea en mre 2 SphereS X x x Alt Ho 1 so 5 3 code x B x O a a corneas ven UE 4 lc Surfaces for cell SphereShieldi deltaS ic Surfaces for cell outsideworld 3 sy 2 5 24 01171 mode p m204 7000 02p 0 755636 Gair US 8 Atm at sea level 8000 02p 0 231475 18000 02p 0 012889 m228 1000 02p 0 005558 concrete ordinary with ENDF VI 8000 02p 0 4980765 11000 02p 0 017101 12000 02p 0 002565 13000 02p 0 045746 14000 02p 0 3150923 16000 02p 0 001283 19000 02p 0 019239 20000 02p 0 0829411 26000 02p 0 012398 e Tally information created by NucWiz nps 100000 Source Box Apr Problem Mode I 1 N 222 5 neutronjanit neutron v 2 p gt photon 3 E gt electron positron Additional User Data nps 100000 Figure 4 2 Changing the Problem Mode Because the input file is completely regenerated each time a NucWiz component is changed the user can switch the problem mode at any time and NucWiz will insert the proper cross sections into the file 14 5 Creating the Source Once a geometry h
26. Fun tar n uang DATAPATH ENVIRONMENT VARIALLL gt C Program PesiLara isedisindrd n 1 n 1 8phereGeoml stnded p using DATAPATH ENVIRONMENT VARIAELE gt C Program Finn LAN Wised stncrd p 224 7 872 2 1 S8phereshieldi deltas fe 4 d Nek Found usr n istered 2 11 35 3 2 8phereBhield2 delta5 3 4 224 7 872 4 3 Sphere3hield3 delteas 5 0 5 4 Goutsideworld 6 P meshioldt o 5 Soutsideworld wee A Ckkinthe Piot Wexkyw to ute these key ee Vaw ri Move Toward ic Surfaces for cell UphereGeoml Rot Rotate Vert Rutste Horiz Bhield3 deleas 0 0006 carbon steel with ENDF VI 0 0025 26054 60c 0 056755 26056 60c 0 91493 0 021323 26058 60c 0 002893 0 53327 Sphere Cytinder slab Box X center Y center Ratus 10 Figure 2 2 Spherical shield geometry 2 2 Cylindrical Shields To create cylindrical shields select the Cylinder tab in the Geometry window and specify the X Y and Z location for the center of the base of the cylinder along with a length radius and direction for the axis of the cylinder These values define the interior volume of the cylinder To add cylindrical shields click on New in the first column of the shield list and enter the thickness for the cylindrical shield Once a user enters a thickness Nuc Wiz automatically offers another line designated New Next click in the Mat column to set a material for this shield see Section 3 for mor
27. Graphical User Interface for Simplified Neutron Transport Calculations Phase 1 Final Report Instrument No DE SC0002321 July 20 2009 through April 19 2010 Recipient Randolph Schwarz Visual Editor Consultants Principal Investigator Randolph Schwarz Teaming Members Randolph Schwarz of Visual Editor Consultants Leland L Carter of Carter Monte Carlo Analysis Inc Alysia Schwarz of Visual Editor Consultants Table of Contents LIST OBR FIGURES cccvccccssesesccccsceckccscacscccccsesacccasssaccoscessccscassaccocsesscccossscccuscassccccsssaccocsecsc ue 3 1 0 EXECUTIVE SUMMARY scccsssssssssssssssssssssssssssssssssssssssssssssccccscccscscccssscseees 4 2 0 SIGNIFICANT ACCOMPLISHMENTS ccccccscscscscssssssscssscscssscscscssscscssscccscseses 4 2 1 OVERVIEW OF THE NUCWIZ PROGRAM ssssssssssssssssosssosososososososososososososososososo 4 2 2 SUPPORTED SHIELDING CONFIGURATIONS ccccccccsscscccccscccecccccccccccscccscccccccceces 6 2 3 SUPPORTED SOURCE CONFIGURATIONS scscssssssssssssssssssssssssssssssssssssesssssseseses 9 2 4 SUPPORTED TALLY CONFIGURATIONS cccccsccccssccccccccccccccccccccccccccccccscccccceccooes 12 2 5 SUPPORTED DATA sccsseestesiccedeessnciscsticcesbesselessesstesssessscedessceducsiulescsboteeduecsuscecede 16 2 6 RUNNING FILES CREATED IN NUCWIZ ssccssssssssssssssssssssssssssessssssssssssssseseses 17 2 7 NUCWIZ PLOT OPTIONS cscccssssssssssssssssssessssssssssssssseseesssesssesssess
28. NMENT VARIABLE gt C Program Files LANL Vised stndrd p File Not Found usr n File Not Found usr p 15 12 10 14 outsideworld 15 S outsideworld mcshield1 Click in the Plot Window to use these ke e Num Name show coor soia _ Trans wre eet En 1 CylinerG X x x ubXdown Movs T Ic Surfaces for cell CylinerGeoml 2 cylinder X x x Alt Home Alt End i CM Gic DLE EI C E 3 cylinder X a x x orama j px E sert e px 4 cylinder X x jl 5 ndsde X piaia hotel ten 3 5 Geometry Close Update Sphere Cylinder slab Box X base center 10 Y base cete Z base center Length 20 Radius 5 Axis Parallel to X Deta Width Mat Density Name Sel core CylinderGeom1 5 224 7 872 cylinderShield1 deltaS 252 11 35 CylinderShield2 delta5 224 7 872 cylinderShield3 delta5 Figure 2 3 Cylindrical Shield Geometry Page 8 Phase Final Report Graphical User Interface for Simplified Neutron Transport Calculations Figure 2 4 shows a rectangular parallelepiped shield geometry with a central rectangular parallelepiped volume and three rectangular parallelepiped shields The input file is displayed along with the rectangular parallelepiped geometry creation panel P mcshield mcshield1 L Input Ele Geometry Source Physics Tallies
29. Richland Washington 3 Compendium of Material Composition Data for Radiation Transport Modeling PNNL 15870 April 2006 R G Williams III C J Gesh and R T Pagh Pacific Northwest National Laboratory Richland Washington Page 25 Phase 1 Final Report Graphical User Interface for Simplified Neutron Transport Calculations Appendix A NucWiz User s Manual Page 26 NucWiz User s Manual Nucwiz Version 2S May 2010 Randolph Schwarz of Visual Editor Consultants Leland L Carter of Carter Monte Carlo Analysis Inc Table of Contents l TTPO CLUE COM eis Sates Satta ood anak ected sana aerea dein efe na dM ado dodi e o E 3 2 Creating the Geometry sessionen oesi DE e Ee aAa ES A EEEE S TEE ar A E AEREN 4 2 1 Spherical Shielidsa dioe u a a e b UI e da ote itn ere oaee aiot 4 Dede GylmndrncalsShie lus o sudeste Na A E E Race ds E Rie EEE 5 2 3 SIDB SBICIOS tree piii mud Urso T a ieu a AE eee 6 24 J BOX Shields eost edocti gea RU RV AREA Suas cuta tuti nte pec tuf e duque 7 3 Adding Materials to the Geometry 5 eret et tenter In EON HIN SUR SN RN Essa RENI PRG V NR a eU He eene 8 4 Setting the Problem Mode oe soe dote dee etat aa i AE 13 5r Creatine the SOUT CC uod miedos edat ote Oulu ee ot ue PL E AL tL CHUA 15 5 1 Point cli c asiarren niian aia i a Leeder 18 5 2 Sphere SOULOS eC RE 19 5 3 Cylinder Souice caen E sea ba a ios do A ca ees sae See E ee 20 DA BOR SOURCE 2 62 24 eet em c t Ne il fe 21 6 Create Ta
30. T es eS A gu 5 2 py 20 3 pz is 4 px 5 5 py 10 6 pz as e c Surfaces for cell outsideworld sil H 45 5 spl D 01i si2 H 10 i0 sp2 D ot si3 H 15 15 D DE Point Sphere Cylinder Box Name was Den xcent Ycent zcen xen vien zin Set 1 RPPSrci 204 0 001225 10 20 30 New wer Enter Energy Spectrum Below spaceftab delimited energy particlesisec Histogram Bins z Figure 2 7 Rectangular Parallelepiped Source Configuration 2 4 Supported Tally Configurations In addition NucWiz contains a limited set of tally configurations Tallies that are supported include the following Point detector 2 Surface tally with optional surface splitting to provide a profile across the surface 3 Cell volume tally including a sphere tally cylindrical tally and rectangular parallelepiped tally Multiple tally regions are supported If a cell tally is specified the program creates the geometry for the tally Page 12 Phase 1 Final Report Graphical User Interface for Simplified Neutron Transport Calculations A number of tally response functions are supported Supported conversion factors are those specified by the National Council on Radiation Protection and Measurements the American National Standards Institute and the International Commission on Radiological Protection The standards can be converted to provide results in either Rem hr mrem hr or
31. as been defined the user can define the source The Source window can be displayed by selecting the Source option from the main menu or by right clicking in the plot window and selecting Source Either method brings up a tabbed window showing the possible source options as shown below In this case the Box tab has been selected Source Close Update Delete selected Point Sphere Cylinder Box Name mat Den Xcent_ Ycent Zcent xien Yien Zien _ Sel wet Enter Energy Spectrum Below spacestab delimited energy particles sec Histogram Bins hd Figure 5 1 Example Source Window Notice that even though there are additional rows for more than one source description only one source geometry is supported in this release of NucWiz When the source configuration is defined in this case by specifying the center and extent of the rectangular parallelepiped a new cell is created to contain the source description and the source is placed in this cell The user must take care to make sure the source description does not conflict with the geometry description NucWiz will check to see if the source geometry conflicts with the shield geometry If NucWiz detects a conflict an error message will be displayed and the source will not be generated The user will then need to modify the source description to eliminate the conflict with the existing geometry To enter source information click on New to add a new source In
32. ated into the NucWiz program The addition of tally splitting surfaces went beyond the current scope but does not detract from the capabilities of NucWiz because this is a specialized capability that allows a tally region to be divided into smaller segments Additionally biasing in the form of importances was beyond the scope of this initial work and will be pursued if future funding becomes available The input window has a user section that allows the user to specify importances but currently these are not automatically generated by NucWiz Page 23 Phase Final Report Graphical User Interface for Simplified Neutron Transport Calculations 4 0 Products Developed The primary product developed from this Phase 1 project is the initial release of the NucWiz program This initial release will be demonstrated in the Visual Editor workshops and may be distributed as a beta release through these workshops to get user input on its capabilities 5 0 Details of the NucWiz Software Program The NucWiz program was written in C using Microsoft Visual Studio 2008 The current version of Nuc Wiz is 2S released in May 2010 In this new approach to developing a GUI for creating MCNP input files the project team decided to use the DirectX libraries instead of the OpenGL libraries DirectX is recognized as the industry standard for gaming engines and gaming software By using DirectX advanced software and hardware support can be accessed to
33. calculations The input file is constrained to a number of simple geometry source and tally configurations The interface allows a user to specify a simple geometry configuration select from specific source geometries and then specify tally types and locations Once the user specifies these parameters NucWiz generates a complete MCNP input file that can be run from within NucWiz The output file can also be viewed directly from NucWiz NucWiz is designed to create simple geometries with simple sources and simple tallies The possible configurations are constrained to the types specified in Table 2 1 This simplification allows for 100 shield source tally combinations Only one source and one shield geometry is allowed per input file however multiple tallies and tally configurations are allowed Page 4 Phase 1 Final Report Graphical User Interface for Simplified Neutron Transport Calculations Table 2 1 Shield Source and Tally Configurations Supported by NucWiz Shield Geometry Tally Rectangular Parallelepiped Rectangular Parallelepiped Rectangular Parallelepiped Sphere Cylinder Cylinder Cylinder po Surface NucWiz creates an MCNP input file by allowing the user to make choices in three primary elements 1 Geometry where the surfaces cells and optionally materials are generated 2 Source where surfaces cell the source definition and optionally materials are generated 3 Tallies where the surfaces cell tally definit
34. ck in the Plot Window to use these key functions Num Nome Snow Cor _ soia Trans vwe ces m SphereGeom1 X up down Move Toward SphereShield1 detta5 X Alt Home Alt End Pitch sourcebox1 X Ll HomeX End Roll outsideworld Ll Insert Delete Rotate Vert Pg up Pg Dwn Rotate Horiz Update XYZ X Materials M Show Axis SphereGe SphereShi sourcebox1 outsideworld Figure 2 16 Wire Frame Geometry Display Page 21 Phase 1 Final Report Graphical User Interface for Simplified Neutron Transport Calculations The isometric view of the geometry can be changed to a cross sectional view by selecting the appropriate basis view in the pull down menu on the right under Update Shown below is an XY view of this geometry that can be displayed by selecting the XY option in the pull down menu WPsphere geom mcshield E DEI snow osor sota Trens wre prie Plot Window to En es key functions SphereGeoml X up down Move Toward SphereShield1 dettaS X x x Alt Home Alt End Pitch sourcebox1 x Home End Roll X Insert Delete Rotate Vert outsidewvorld Pg upY Pg Dwn Rotate Horiz Update e SphereShi sourcebox1 outsideworld Figure 2 17 Cross Sectional View of the Geometry Page 22 Phase 1 Final Report Graphical User Interface for Simplified Neutron Transport Calculations The user also has a number of options for moving the display in three dimensions The user can chang
35. column Specify the X Y and Z location of the point source then select Update to create the source and update the input file Figure 5 4 shows an input file with a point source at x 5 y 0 and z 0 A mcshield mcshield File Geometry Source Physics Tallies Input Run Edit View Window Help Oa as Sa e FOUND stndrd n in CURRENT DIRECTORY FOUND stndrd p using DATAPATH ENVIRONMENT VARIABLE gt C Program Files LANLlVisedlstndrd p File Not Found usr n ile Not Found usr p Click in the Plot Window to use these k lt gt Yaw PNTSrc 1 upXdown outside Alt Home Alt End c File Created by meshield Home 1 outsideworld Insert Delete el 1 outsideworld Pa up Pg Dwn Surfaces for cell outsideworld sdef cel 1 pos 5 0 0 e Tally information created by NucWiz nps 100000 Close Update Delete selected Pont sphere Cylinder Box Nome x v fz Js 1 PNTSrc 1 5 0 0 New wer Enter Energy Spectrum Below space tab delimited energy particles sec Histogram Bins zl Figure 5 4 Point Source Configuration 18 5 2 Sphere Source To create a sphere source select the Sphere tab in the Source window and then click on New in the first column Specify the X Y and Z location for the center of the sphere and the radius then select Update to create the source and update the input file Figure 5 5 shows an input file with a sphere source at x 0 y 0 and z 0 and a radius of 10 cm
36. create and manipulate the graphics The project team also decided to use the DirectX 9 libraries to be compatible with older operating systems The current release of DirectX 11 will only run on VistaO and Windows 70 Nucwiz is compiled using the following DirectX library C Program Files Microsoft DirectX SDK August 2009 Lib x86 The following library files must be included when linking d3dxof lib dxguid lib d3dx9d lib d3d9 lib To run the NucWiz program users must download the DirectX 9 0c runtime libraries or they will receive an error message indicating that the libraries cannot be found This library can be downloaded from the Microsoft website As of this writing the library can be downloaded at this link http www microsoft com downloads details aspx displaylang en amp FamilyID 2da43d38 db71 4c1b bc6a 9b6652cd92a3 NucWiz was tested by verifying that the files it created could be run in MCNP X both from within NucWiz and also at the command prompt The NucWiz user s manual can be found in Appendix A with complete details on how to run the program 6 0 References 1 MCNPX User s Manual version 2 6 0 April 2008 LA CP 07 1473 D B Pelowitz editor Los Alamos National Laboratory New Mexico Page 24 Phase Final Report Graphical User Interface for Simplified Neutron Transport Calculations 2 MCNP Visual Editor Computer Code Manual November 2005 L L Carter and R A Schwarz Visual Editor Consultants
37. e information on setting materials Other shields can be added by clicking on New in the first column for each additional shield and setting the thickness and material as was done for the first shield To create the geometry select Update at the top of the Geometry window and NucWiz creates the cells materials and surfaces in the input file Figure 2 3 shows an input file consisting of three cylindrical shields each 5 cm thick The first and last shields contain steel and the middle shield is composed of lead A mcshield mcshield1 File Geometry Source Physics Tallies Input Run Edit View Window Help Dg age L input c File Created by meshield X 0 3 1 8 SCylinerGeomi Z 224 7 872 6 4 11 3 1 8 cylinderShield1 delta5 3 252 11 35 9 7 13 6 4 11 ScylinderShield2 delta5 4 224 7 872 12 10 14 9 7 13 cylinderShield3 delt 5 0 15 12 10 14 outsideworld 6 0 15 outsideworld FOUND stndrd n using DATAPATH ENVIRONMENT VARIABLE gt C Program Files LANL Vised stndrd n FOUND stndrd p using DATAPATH ENVIRONMENT VARIABLE gt C Program Files LANL Vised stndrd p File Not Found usr n File Not Found usr p WP mcshield1 Num Name show Color Solid Trans Wire A Click in the Plot Window to use these ke X Yaw CylinerG X ubXdown c Surfaces for cell CylinerGeomi 2 cylinder X s x Alt Home Alt End e 2
38. e located in the same directory as the NucWiz executable or if they are placed in the Vised directory beneath the directory specified by the DATAPATH environment variable When MCNP is installed on a computer the installation script will generate a DATAPATH environment variable showing the path to the MCNP cross section directory This variable can be seen by opening a command prompt window and typing set This command will show all the environment variables An example is shown below 10 Microsoft Windows AP Version 5 1 2600 lt C gt Copyright 1985 2661 Microsoft Corp C Documents and Settings Owner gt set ALLUSERSPROFILE C Documents and Settings All Users APPDATA C Documents and Settings Owner Application Data CLASSPATH C Program Files Java jrel 6 6_ 5 lib ext QTJava zip CLIENTNAME Conso le CommonProgramFiles C Program Files Common Files COMPUT ERNAME VEC8 ComS pec C WINDOWS s ystem32 cmnd exe CPU i386 DATAPATH C Program Files LANL MCNPDATA DISPLAY localhost DRSDK_DIR C Program Files Microsoft DirectX SDK CfAugust 2686 gt FP_NO_HOST_CHECK NO HOMEDRIUE C HOMEPATH Documents and Settings Owner IFORT COMPILER18 C Program Files Intel Compiler Fortran 1 1 821 INCLUDE C Program Files Microsoft Visual Studio UC98 atlN include C Program Fil les Microsoft Visual Studio UC98 mfc inc lude C Program Files Microsoft Visual St udio VUC98 inc lude INTEL_LICENSE_FILE C Program Files Common Files Int
39. e the geometry using special keys as outlined in the table below Table 2 2 Three Dimensional View Display Keys Leftarrow Right Yaw Move the view either left or right AITOW Up arrow Down Vicinity Move toward or away from the geometry Arrow Alt Home _ Alt End Pitch Move the view up or down Roll Rotate about the axis coming out of the plot plane Orbit Rotate the view about the vertical axis Page Up Page Orbit Rotate the view about the horizontal axis Down By using different combinations of these keys the user can move through the geometry in three dimensions In addition to the top list of objects a list on the right also included Clicking on the objects in the list on the right brings up the window used to create the object allowing the user to edit the object 3 0 Project Activities In general the project followed the guidelines provided in the proposal The project team decided early on to develop a stand alone program to create and run the MCNP X input files instead of enhancing the Visual Editor to create the files As a new program NucWiz is independent of the complications in the Visual Editor associated with the inclusion of the MCNP Fortran code as part of the Visual Editor executable The Visual Editor can be used in combination with NucWiz to allow the simplified NucWiz models to be enhanced in the Visual Editor All of the sources shield configurations and tallies specified in the proposal were incorpor
40. e user must install the DirectX 9 0c End User Runtime libraries from the Microsoft website http www microsoft com downloads details aspx displaylang en amp FamilyID 2da43d38 db71 4c1b bc6a 9b6652cd92a3 Using the DirectX graphics libraries allows NucWiz to take advantage of state of the art graphics capabilities and potentially the hardware acceleration available for DirectX applications With this initial implementation only spheres boxes and cylinders are supported These objects are standard graphics objects that can be created by DirectX Additionally DirectX has functions for the many vector calculations required for three dimensional visualization applications By default NucWiz will show a three dimensional perspective of the geometry On the right side of the plot window is a pull down menu that allows the user to change the view basis to the six orthogonal views along with an isometric view identified as XYZ The right side of the plot also has an Axis toggle that allows the user to turn on and off the display of the axis 33 R sphere geom mcshield DEAR Click in the Plot Window to use these key functions Num Name show Color Solid _ Trans wwe pee spur spere x B x upy down Move Toward Spheres X x Alt Home Alt End Pitch sourceb X x Home End Roll T InsertY Delete Rotate Vert outside X x Pg up Pg Dwn Rotate Horiz Update XYZ Materials M show Axis SphereGe SphereS
41. ecececececs 11 FIGURE 2 7 RECTANGULAR PARALLELEPIPED SOURCE CONFIGURATION 0c cccececececececececececececececececececececececececesecececececececs 12 FIGURE 2 8 CREATING A SURFACE TALLY 0c cccccccccececececececececececececececececececececececececececececececececececececececececececececececececececececess 13 TIGURE2 O SPHERICAE ALLIES Los sione eoim ania as ibl PE 14 TIGURE2 IO CYEHNDRICAL TAEEIES Seba ace anie n e ae i v oes 15 FIGURE 2 11 RECTANGULAR PARALLELEPIPED TALLIES 0 cccccccecececececececececececececececececececececececececececececececececececececececececececs 16 FIGURE 2 12 MATERIAL LIBRARY WINDOW occ cccccccccecececececececececececececececececececscececececececececececececececececececececececececececececececess 17 FIGURE 2 13 RUNNING THE NUCWIZ INPUT FILE oc cccccccccccccececececececececececececececececececececececececececececececececececececececececececececece 18 FIGURE 2 14 THREE DIMENSIONAL GEOMETRY WINDOW ce cccecececececececececececececececececececececececececececececececececececececececececececs 19 FIGURE 21S OBJECT AIST eles asisoaioeatetonamut aom ino aei IRB AERA 20 FIGURE 2 16 WIRE FRAME GEOMETRY DISPLAY icccccccccccssssssccscecscesssssscscesscecsessscssesscecsessensesssescesssesssssseeseesesssessesesessensees 21 FIGURE 2 17 CROSS SECTIONAL VIEW OF THE GEOMETRY ccc cecececececececececececececececececececececececececececececececececececececececececececs 22 Page 3 Phase 1 Final Report Graphical User Interface for Simplified Neutron Transpo
42. el Licenses LIB C Program Files Microsoft Visual Studio UC98 mfc 1lib C Program Files Micro soft Visual Studio UC98 1lib ILOGONS ERUER UEC8 MS DevDir C Program Files Microsoft Visual Studio Common MSDev98 NUMBER_OF_PROCESSORS 2 OS Windows _NT Path C Program Files Microsoft Directk SDK CAugust 2686 gt Utilities Bin x86 5C Program Files Microsoft DirectX 9 6 SDK CAugust 26 5 gt Utilities Bin x86 C MCNP Nncnp5NbinNMindous C NProgram Files LANL MCNPS mcnpS bin Windows 5 C Program File is Microsoft Visual Studio Common Tools C Program Files Microsoft Visual Studio Common Msdev 8 BIN 5C Program Files Microsoft Visual Studio DF98 BIN C Program Files Microsoft Visual Studio UC98 BIN C WINDOWS s ystem32 5C WINDOWS 5 C WINDOWS NS ystem C Program Files Common Files Roxio Shared DLLShared C Program Files C ommon Files Roxio Shared DLLShared C Program Files Microsoft SQL Servery okd Figure 3 3 DATAPATH Variable in Command Window NucWiz uses this DATAPATH to find the material libraries It looks for a Vised directory that is at the same level as the MCNPXDATA directory In the example above the user would need to create a C Program Files LANL Vised directory and put the material libraries in this directory If this directory exists NucWiz will be able to read the material libraries without having the material libraries in the same directory as the NucWiz executable If the DATAPATH variable was never set by t
43. es Page 15 Phase 1 Final Report Graphical User Interface for Simplified Neutron Transport Calculations Figure 2 11 shows a plot of the geometry and input file created for a rectangular parallelepiped tally configuration consisting of three volume tallies NucWiz created the geometry and tally definitions in the input file to correspond to these tallies The panel used to create these tallies is also shown A mcshield mcshield1 File Geometry Source Physics Tallies Input Run Edit View Window Help DEH teel FOUND stndrd n using DATAPATH ENVIRONMENT VARIABLE gt C Program Files LANL Vised stndrd n FOUND stndrd p using DATAPATH ENVIRONMENT VARIABLE gt C Program Files LANL Vised stndrd p File Not Found usr n File Not Found usr p c File Created by mcshield d 0 123 4 5 6 S RPPTal 4 783 9 10 6 RPPTal 14 7211 9 5 12 RPPTal 24 139 GF 2 35 4 5 6 Soutsideworld CUM a pi xz Hei oS s du e6y SC S EB BE Be So xz xe 5 13 Soutsideworld uS 0 UN ooo VW mcshield1 Num Name Show Color Solid Trans Wire Click in the Plot Window to use these ke 6c Yaw 5 RPPTat4 X x x upXdown Move Towa 6 RPPTa14 X x x Alt Home AIt End it lg 7 RPPTa24 X x x Musae Ri 1 px 7 5 S Ins le z 4 outside x x Pa upXPg Dwn z z E 4 px 12 5 S py 25 pz 72 5 7T px 2 8 8 py 7 5 e surface reused 3 pz 2 5 9
44. from within NucWiz The output file can also be viewed directly from NucWiz NucWiz is designed to create simple geometries with simple sources and simple tallies The possible configurations are constrained to the types specified in Table 1 1 This simplification allows for 100 shield source tally combinations Only one source and one shield geometry is allowed per input file however multiple tallies and tally configurations are allowed Table 1 1 Shield Source and Tally Configurations Supported by NucWiz Shield Geometry Tally Rectangular Parallelepiped Rectangular Parallelepiped Rectangular Parallelepiped Sphere Cylinder Cylinder Cylinder po Surface 0000 NucWiz creates an MCNP input file by allowing the user to make choices in three primary elements 1 Geometry where the surfaces cells and optionally materials are generated 2 Source where surfaces cell the source definition and optionally materials are generated 3 Tallies where the surfaces cell tally definition and optionally materials are generated NucWiz automatically creates the surfaces cells and materials for these elements allowing the user to focus on the elements of the input file and not the details of how the file will be generated The user can create the geometry source and tallies in any order NucWiz dynamically creates the input file As each element is added to the input file the input file is completely regenerated to include this new elemen
45. geometry information For example the core region is defined by the values in the X center Y center Z center and Radius fields The core is listed in the shield list below the coordinate fields to allow the user to assign a material and name for the core region 2 1 Spherical Shields To create spherical shields select the Sphere tab in the Geometry window and specify the X Y and Z location for the center of the interior sphere along with the radius These values define the interior volume of the sphere To add spherical shields click on New in the first column of the shield list and enter the thickness for the spherical shield Once a user enters a thickness NucWiz automatically offers another line designated New Next click in the Mat column to set a material for this shield see Section 3 for more information on setting materials Other shields can be added by clicking on New in the first column for each additional shield and setting the thickness and material as was done for the first shield To create the geometry select Update at the top of the Geometry window and the cells materials and surfaces will be created in the input file Figure 2 2 shows an input file consisting of three spherical shields each 5 cm thick The first and last shields contain steel and the middle shield is composed of lead F meshield mcshieldt Eje Grometry Source Physes Tales Input Run Ear Mew Window Heb oe eat z Pile Created by mcshicld
46. gure 6 66 Selecting a Surface of a Box to Tally On essent 27 Figure 6 7 Creating Box Cell TOlli su ue ec e eS nete adepta pda eie qeu miuus 30 Figure 7 1 Appending Additional User Data to the Input File esses 22 Figure 8 1 Three Dimensional Geometry Window sees enne 34 Figure 8 2 Object EU iiit esrau de een ep sese Ig eed c n pesaluu Uo spada sea auo N adu epah 35 Figure 8 3 Wire Frame Geometry Display 4 ce dic euin ecd ge see eco teat oro aaepe dread 36 Figure 8 4 Cross Sectional View of the Geometry eese eene 37 Figure TOD R n WIBdOW aiiud vo lide dtes t Res deed A E totais R a 39 Figure 10 2 Specifying the Input and Output File Names eese 40 Figure 10 3 Selecting the Executable 10 Run za dae ue etes cU Dacia di sedora t Da Ui bee Saat 41 Figure 10 4 Executing the NucWiz Input File uico eset d e sas Sonesta ea 42 Figure 11 1 Displaying the Output File ut rie eot ei scite hea fies idet birutSacai eden aln 43 1 Introduction NucWiz is a program that can set up and run Monte Carlo N particle MCNP calculations The input file is constrained to a number of simple geometries source and detector configurations The interface allows a user to specify a simple geometry configuration select from specific source geometries and then specify detector types and locations Once the user specifies these parameters NucWiz generates a complete MCNP input file that can be run
47. he MCNP installation the user can set this variable manually by right clicking on My Computer then selecting the Advanced tab Click on the Environment Variables button on the bottom of this tab In the Environment Variables window select New under System Variables 11 Once the shield configuration and materials have been defined the user selects Update from the menu at the top of the Geometry window to create the input file To see the input file select Input from the main menu The input will now include the geometry information and all of the material information Notice that no particle mode has been set so the materials default to using neutron cross sections Note also that an outside world sphere is created and by default set to transparent 14 mcshield mcshield1 Geometry e Update File Geometry Source Physics Tallies Input Run Edit View Window Help Del e amp FOUND stndrd n in CURRENT DIRECTORY FOUND stndrd p using DATAPATH ENVIRONMENT VARIABLE gt C Program Files LANL Vised stndrd p File Not Found usr n File Not Found usr p Sphere Cylinder Slab Box X center Y center Zcenter Radius 5 B mcshield1 Deta Width Mat core 204 0 001225 SphereGeomt Name Show Color Solid Trans wire oes m leche eus ur 5 228 235 SphereShield dettas Sphere X o x x up down Alt Home Alt End outside X
48. hi sourcebox1 outsideworld Figure 8 1 Three Dimensional Geometry Window Note that all geometries appear as a sphere because NucWiz creates the outside world and this is always outside a sphere By default this outside world is set to a transparent sphere because typically this sphere is not of interest to the user 34 On the top of the plot window is a list of the bodies that have been created so far All the bodies are listed except the outside world The numbers listed do not refer to cell numbers but to object numbers NucWiz gives a default name to each of the objects These names can be changed to something more meaningful to the user In this example the objects are listed in nonsequential order 1 2 4 3 but in the input file these objects are assigned cell numbers that are sequential 1 2 3 4 So it is important to not confuse the object number with the cell number With Nuc Wiz cell numbers are only assigned on creation and until that time different elements are referred to with these object numbers WP sphere geom mcshield fel Nun neme Show coor saa Trans we Clekinite Pet Window to uge these ey functions SphereGeom1 updown Move Toward SphereShield1 deltaS Ll Alt Home Alt End Pitch sourcebox1 HomeX End Rall Insert Delete Rotate Vert outsideworld Pg up Pq Dwn Rotate Horiz Figure 8 2 Object List The row for each object has a number of display options By clicki
49. icking in the Mat column see Figure 2 1 for the core row which brings up a list of materials as shown below Materials Number Standard Materials air LIS S Atm at sea level 0 001225 aluminum 2 699000 beryllium metal 1 850000 beryllium oxide BeO 3 025000 boron natural 2 450000 carbon steel with ENDF VI 7 872000 carbon steel with ENDF V Fe 7 872000 concrete ordinary with ENDF VI 2 350000 concrete ordinary Fe ENDF V 2 350000 Number User Materials 7 Mitrogen 7014 60c 0 755636 75 56 8 Oxygen 8016 6 c 0 231475 23 15 18 Argon 18000 59c 0 012889 1 29 Figure 3 1 Material Library Selection Window By default no material is entered for the core or shield regions To keep this default the user should not select the material column When the user clicks on a material the material number and density is set for the core region Once the user selects a material the Material window closes In the example below concrete material 228 has been set for the 5 cm spherical shield region mcshield mcshield1 SEE File Geometry Source Physics Tallies Input Run Edit View Window Help Osea se 6 FOUND stndrd n in CURRENT DIRECTORY FOUND stndrd p using DATAPATH ENVIRONMENT VARIABLE gt C Program Files LANL vised stndrd p File Not Found usr n File Not Found usr p meshieldt Materials E3 Nu se l selected a Number Standard Materials Density o 204 air LIS S Atm at
50. igure 3 3 DATAPATH Variable in Command Window eese 11 Figure 3 4 Creating the Geometry and Updating the Input File esses 12 Figure 4 1 Setting the Problem Mode s eue e td etia asta Rein od daa E nda Goccodedesece Do ERI Re id qid 13 Figure 4 2 Changing the Problem Mode siete ntes edle td lute miedo Reti do dart ad meade 14 Figure 5 1 Example Source WIBdOW inia e enit dei Urea kh Ve Sana aunt saisean Sada tdala Desa e vod abee Tae 15 Figure 5 2 Creating a Rectangular SORGE io opea sa taadaciatunnda e idi edge eade dd 16 Figure 5 3 Adding the Source to the Input File tee etie eoa Aasdssa sudan Gis edad 17 Figure 5 4 Point Source Configuration 23 iic udites poti etkca celeb et ee ssc BAA es Fa Da d ea aiden 18 Figure 5 5 Spherical Source C ONIS HEOORS i Ia opes e uites ice Miedo tf Ra dere ta dados 19 Figure 5 6 Cylindrical Source COnpi cura saec dsbecl vets citant bei dd gec Ue Fu RR QR towne 20 Figure 5 7 Rectangular Parallelepiped Source Configuration eese 21 Figure 0 1 Jules WIRdOW ied atre etie eoe nn ustedes teh Bad eso ataia 22 Figure 6 2 Creating Point Detector Tallies ui aiite iiie eite ete oido ep gode ul oa Fa guae dica Rida 23 Figure 6 3 Specifying Additional Point Detector Tallies eese 24 Figure 6 4 Point Detector Tallies Added to the Input File eene 25 Figure 6 5 Selecting the Surface of a Sphere to Tally On esses 26 Fi
51. ing DATAPATH ENVIRONMENT VARIABLE gt C Program Files LANL isedistndrd n FOUND stndrd p using DATAPATH ENVIRONMENT VARIABLE gt C Program Files LANL Visedistndrd p File Not Found usr n File Not Found usr p c File Created by mcshield EH o 1 2 3 4 5 6 BoxGeoml 2 224 15972 7 8 9 10 AL z BoxShieldi deltaS i SZ s EE ey 3 252 11 35 13 14 15 16 17 18 BoxShield2 delta5 BHO T S gg 10 x DP n d25 4 224 7 872 19 20 21 22 23 24 BoxShield3 delta5 mcshield1 13 14 15 16 17 18 Name E 5 0 25 19 20 21 22 23 24 outsideworld 6 o 25 outsideworld BoxGeo up down BoxShiel Alt Home AIt End BoxShiel Home End lee pae aga a ESS a en ea aan E 5 Gnsert Delete c Surfaces for cell BoxGeoml EU H vw PaupXPa Dwn Ca Se eee 1 px 2 5 2 py 5 3 pz 7 5 4 px 2 5 5 py 5 6 pz 7 5 7 px 7 5 8 py 10 9 pz 12 5 10 px 7 5 11 py 10 12 pz 12 5 13 px 12 5 14 ov 15 Geometry Sphere Cylinder Slab Box X center Y center Z center Xlength 5 Ylengn 10 Z length Deta width Met Density Name core BoxGeomt 224 7872 BoxShield1 deta5 252 4135 BoxShield2 deltaS 224 7 872 BoxShield3 delta5 Figure 2 5 Rectangular Parallelepiped Shield Geometry 3 Adding Materials to the Geometry The material for the inner core can be set by cl
52. ion and optionally materials are generated NucWiz automatically creates the surfaces cells and materials for these elements allowing the user to focus on the elements of the input file and not the details of how the file will be generated The user can create the geometry source and tallies in any order NucWiz dynamically creates the input file As each element is added to the input file the input file is completely regenerated to include this new element NucWiz detects if any of these elements interfere with each other and issues an error message although the user should take care to avoid entering interfering elements because there still may be configurations that are not accurately detected Figure 2 1 shows the main window of the NucWiz program As the geometry is created the three dimensional plot window shows the objects as they are created At the same time the input window is updated to show the MCNP input file that has been created The main menu has options for the user to specify the Geometry Source Physics and Tallies Figure 2 1 shows a point source a slab shield containing steel and a spherical tally on the other side of the slab shield The input that has been created is shown in the input window Page 5 Phase 1 Final Report Graphical User Interface for Simplified Neutron Transport Calculations 33 meshield meshield Ple Geometry Source fhwsks Tales input Pun Edt yew Window Heb Dna eet OUND stn rd p use DAT
53. llies can be specified by clicking on New and entering the tally information for that row Tallies Close Update Delete Selected Click New to add a new tally Point surface Sphere Cylinder Box SESS a 77 X17 TRU a fiscus ar i Iit Mew Additional Data Taly 5 Conversion Factor None mremjhr Figure 6 2 Creating Point Detector Tallies 23 Figure 6 3 shows a second point detector added to the input file Once the user has specified the point detector values the user must select Update to update the input file with these point detectors Tallies Close Update Delete Selected Click New to add a new tally Point surface Sphere Cylinder Box PDetTal 5 15 5 p 5 H5 p ppeTai5 c qp cur New Additional Data Tally 15 Conversion Factor None mremjhr Figure 6 3 Specifying Additional Point Detector Tallies 24 Figure 6 4 shows an input file after Update has been selected Notice that point detectors 5 and 15 have now been inserted in the input file The tally window allows for additional user data to be inserted for any tally and also allows the user to specify a conversion factor and the units for the tally Rem hr mrem hr or Sieverts 14 mcshield mcshield1 ES Dg met File Geometry Source Physics Tallies Input Run Edit View Window Help IFOUND stndrd n in CURRENT DIRECTORY FOUND stndrd p using DATAPATH ENVIRONMENT VARIABLE gt
54. llies cerato crece te re are oe uolentes deerit oe Gata ws atts sedes vean oaa esas aae 22 6 1 Point Detector Tallis 5e eI EI eiie t ere OR V RAN VIR aa 22 6 2 S utiabe Tallies cue cuba ie tatit icon cft cp cious opis sue cta Mane E tot esca cease o aN S 26 6 3 le LE Tale ys noU Cmadtutedt E estas cag ede A AT 29 7 The Input File and Inserting Additional User Data eee 31 INUCWIZ PIOU ODE OMS esseere tive oei tine eoe eoo eye saan auastend qaia soon ede eo E aE Ea 33 Oh Savins and Loading Nuc Wiz PUES inienn aa dee x a E EE AERE puRGE 38 10 Running MCNP from Inside Nuc W 12 oss iscasessscaengoacedassegvaasesdaedaagsocesssessasteei en e EIN teqeenaiane 39 11 Viewing Output Files from Inside NucWiz eese enne enne 42 List of Figures Figure 2 1 Geometry Creation WIHdOW uxaelass Seed abe o emen ep sd ie Fi eR dui Op ete u e Gee be Epig 4 Figure 2 2 Spherical shield geomtelbyas oes avt sese tente e deudor o npe zia ca tease be Sica ad 3 Figure 2 3 Cylindrical Shield Geomelryuu idest sott bed burskioua tete ci dere locea toda bincfiod das obl Bard 6 Figure 2 4 Mab Shield Geometry ui oe odi ease qa RES RA2 UU ES da Ee RES EU EUN UU DEAL qud 7 Figure 2 5 Rectangular Parallelepiped Shield Geometry essere 8 Figure 3 1 Material Library Selection Window ok Sa ed ida a ddete Na cie Fissac olia e Face du eb Serb Fadpige 9 Figure 3 2 Adding Materials to the Geometry Shields eese 10 F
55. lls NucWiz to not increment the file names as is normally done in MCNP but instead to delete any existing file that has the name specified and create new ones Overwriting is particularly useful when using the name options because if the file exists MCNP gives a fatal error 11 Viewing Output Files from Inside NucWiz To view the output file select WordPad from the Run window A file browser will open allowing the user to select the output file which will then open in WordPad 42 l Sphereout o WordPad File Edit View Insert Format Help Del 464 amp ser amp 16000 60 57647 16 s nat from endf b vi mati600 11 25 93 19000 60c 11978 19 k nat from endf b vi mat1900 11 25 93 20000 60c 29795 20 ca nat from endf b vi matzooo 11 25 93 26054 60c 63619 endf b vi 1 fe54a mat2625 11 25 93 26056 60c 92647 endf b vi 1 fe56a matz2631 11 25 93 26057 60c 72092 endf b vi 1 fe57a mat2634 11 25 93 26058 60c 49684 endf b vi 1 fe58a matz637 11 25 93 tables from file misc5xs i18000 59c 2059 1800 06 19 82 total 604229 RAKERAAAAEAAAREREAE AAA EAE RA RARER AERA AERA EAE AEA ERA A REE RAL EUR GUERRE GAUGE UE URGE EAGRUEOE EUG UEEUAURURUEE A AGRGUR A AGRGUR G ERE dump no 1 on file Sphereout r nps 0 coll ctm 0 00 nrn iU 1 warning message so far t starting merun epo 0 01 print table 110 c File Created by mcshield bad trouble in subroutine source of mcrun you need a source subroutine For Help press F
56. lso shown P mcshield mcshield1 Elle Geometry Source Physics Tallies Input Run Edit View Window Help Dal ae c File Created by mcshield IFOUND stndrd n using DATAPATH ENVIRONMENT VARIABLE gt C Program Files LANL Vised stndrd n 4 3 1 2 CYLTal 4 FOUND stndrd p using DATAPATH ENVIRONMENT VARIABLE gt C Program Files LANL Vised stndrd p File Not Found usr n 2 6 4 5 CYLTal 14 File Not Found usr p 3 o 9 7 8 S CYLTal 24 4 D 10 3 1 2 6 4 5 9 7 8 outsideworld 5 10 Soutsideworld E mcshield1 c u ee ceoeLesoerepesececer Num Name Show Color Solid Trans Wire sede cea tudo toe nes d lc Surfaces for cell CYLTal 4 1 CYLTa4 X x x updown Move To G manae 3 CYLTat14 X x x Alt Home AIt End Pitch d px um 4 CYLTa24 X x x Meath Ha 2 px 30 Insert le le Ver 2 outside X x Pa upyPy Dwn Rotate Hori d ex 5 4 py 10 5 py 30 6 cy 5 7 pz i0 8 pz 30 9 cz 5 t eee c Tally information created by NucWiz fiin A fc4 CYLTal 4 f14in 2 fcl4 CYLTal 14 Click New to add a new tally Point Surface Sphere Cylinder Box Par Name mat Den xBase YBase zBase ten Rad axis 4 n CIL 10 20 Parallel to X 14 n ens 10 20 5 Parallel to Y 2 n Obe 10 20 5 ParaleltoZ New Additional Data Tally 14 Conversion Factor None m mente x Figure 2 10 Cylindrical Talli
57. metry The source is defined in air or void 2 Slab shield geometry The user can define a single slab geometry or multiple slabs with different shield compositions This configuration allows for a simple source detector pairing with slab shields in between 3 Box shield geometry The user can define a box or multiple box also called a rectangular parallelepiped shields with different thicknesses and compositions encased inside each other The source is either inside or outside the box Page 6 Phase Final Report Graphical User Interface for Simplified Neutron Transport Calculations 4 Sphere shield geometry The user can define a sphere or multiple sphere shields with different thicknesses and compositions encased inside each other The source is either inside or outside the sphere 5 Cylindrical shield geometry The user can define a cylinder or multiple cylinders encased inside each other The source is either inside or outside the cylinder Once a user selects a geometric configuration NucWiz generates all of the surfaces required to make the geometry and creates the cells Figure 2 2 shows a spherical shield geometry with a central internal volume surrounded by three spherical shields F meshield mcshieldt Eje Geometry Source Physes Tales input Run Ede yew Window Bei DH nat Pile Created by meshield Ei stn dr n Using DATAPATH ENVIRONMENT VARIALLL gt C Program Mes LANt Wisedletnded n n 1 8phereGeoml te
58. namic creation of tallies including point detectors surface tallies and cell tallies When a tally is specified NucWiz creates the supporting surfaces and cells for that tally The Tallies window can be displayed by selecting the Tallies option from the main menu or by right clicking in the plot window and selecting Tallies Either method will bring up a tabbed window showing the possible tally options as shown in the figure below In this case the Point tab has been selected Tallies Close Update Delete Selected Click New to add a new tally Point Surface Sphere Cylinder Box Additional Data Tally Conversion Factor None mremjhr Figure 6 1 Tallies Window 6 1 Point Detector Tallies To add point detector tallies select the Point tab in the Tallies window click on New to start a new tally and then fill in the point detector tally parameters Once a user enters the parameters NucWiz automatically offers another line designated New NucWiz sets a default tally number ending in 5 particle type and name but the user can override these 22 Figure 6 2 shows the initial values set for the point detector tally The user must now specify the X Y and Z location of the point detector tally and Ro The user must take care in specifying the location of this tally because NucWiz does not check to make sure the location is not in a scattering media or even in the outside world Additional point detector ta
59. ng in the different columns the user can change the display of any of the objects listed By clicking in the Name column the user can set the name for the object By clicking in Show the user can choose to hide or display the object The Color column allows the user to select the color of the object An X in the Solid column causes NucWiz to display the object as solid an X in the Trans column causes NucWiz to display the object as transparent An X in the Wire column allows the user to display a wire frame around the objects Note that to show an object as transparent the user must unselect Solid and select Trans because solid supersedes transparent 35 In this example to hide the outside world sphere the user would remove the X in the Show column on object 3 by clicking in that colum To make the shield cells objects 1 and 2 transparent the use would turn off Solid and turn on Trans by clicking in the appropriate columns The resulting geometry plot is shown below RF sphere geom mcshield Mum Neme Show color So Tene we Cikinthe Pot Window to use these key functions SphereGeomt X up down Move Toward SphereShield1 detta5 X Alt Home Alt End sourcebox1 X Ll Home End outsideworld Ll Insert Delete Rotate Vert Pg up Pg Dwn Rotate Horiz Update XYZ v Materials MV Show Axis SphereGe SphereShi sourcebox1 outsideworld Figure 8 3 Wire Frame Geometry Displa
60. ngth of each side Select Update to create the source and update the input file Figure 5 7 shows the input file for a box source with a center at x 0 y 0 and z 0 and an x length of 10 a y length of 20 and a z length of 30 f meshield mcshield1 File Geometry Source Physics Tallies Input Run Edit view Window Help Dc ael FOUND stndrd n using DATAPATH ENVIRONMENT VARIABLE gt C Program Files LANL Vised stndrd n FOUND stndrd p using DATAPATH ENVIRONMENT VARIABLE gt C Program Files LANL Vised stndrd p File Not Found usr n File Not Found usr p WP mcshield1 c File Created by mcshield TF 1 0 1 2 3 4 5 6 SRPPSre 1 Click in the Plot Window to use these ke wam wame show coor soia Tons wie e X Yaw 2 0 7 1 2 o 3 48 8 6 Soutsideworld 1 RPPSCA X H x x upXdown 3 0 7 outsideworld 2 outside X x Alt Home Alt End it Home End Insert Delete Pg upXPg Dwn c Surfaces for cell outsideworld 7 so 28 06243 sdef cel 1 x dl y d2 z d3 sil H 59 5 01 D H D H D Point Sphere Cylinder Box Name Mat Den xcent Ycent Zcent xien vien zien se 1 RPPSrc 1 204 0 001225 10 20 30 New wet Enter Energy Spectrum Below spacestab delimited energy particles sec Histogram Bins gt Figure 5 7 Rectangular Parallelepiped Source Configuration 21 6 Creating Tallies NucWiz allows for the dy
61. nsional geometry visualization NucWiz is designed using the DirectX 9 0c libraries allowing for backwards compatibility with the Windows XPO operating system Higher library versions only work with Windows Vista and Windows 76 To use NucWiz the user must install the DirectX 9 0c End User Runtime libraries from the Microsoft website http www microsoft com downloads details aspx displaylangzen amp FamilyIDz2da434d38 db71 4c1b bc6a 9b6652cd92a3 Using the DirectX graphics libraries allows NucWiz to take advantage of state of the art graphics capabilities and potentially the hardware acceleration available for DirectX applications With this initial implementation only spheres boxes and cylinders are supported These objects are standard graphics objects that can be created by DirectX Additionally DirectX has functions for the many vector calculations required for three dimensional visualization applications Page 18 Phase 1 Final Report Graphical User Interface for Simplified Neutron Transport Calculations By default NucWiz will show a three dimensional perspective of the geometry On the right side of the plot window is a pull down menu that allows the user to change the view basis to the six orthogonal views along with an isometric view identified as XYZ The right side of the plot also has an Axis toggle that allows the user to turn on and off the display of the axis td sphere_geom mcshield Show Color Sofa
62. om the main window to bring up the Problem Mode panel Although Nuc Wiz was created primarily to run neutron problems additional particles can be set or the particle type can be changed completely For example to run a mode N P problem the user can select the N and P check boxes in this panel and select Apply Notice that the input file is then updated to include a mode n p line in the data section of the code as shown below 14 mcshield mcshield1 Eile Geometry Source Physics Tallies Input Run Edit View Window Help ing seals e E input FOUND stndrd n in CURRENT DIRECTORY c File Created by mcshield FOUND stndrd p using DATAPATH ENVIRONMENT YARIABLE gt C Program Files LANLIVisedist T 204 0 001225 1 SphereGeoml File Not Found usr n zi n File Not Found usr p 2 228 22235 2 SSphereShieldl delta5 3 3 2 Goutsideworld 4 3 S outsideworld VW mcshield1 a Name Show Color Solid Trans Wire i c Surfaces for cell SphereGeomi 1 Sphere X x x oA SRR Gere errr Sas 2 SphereS X x x Alt Ho 1 so 5 osse x B x G ase ree cee ae mein e Surfaces for cell SphereShieldi delta5 i eS e Surfaces for cell outsideworld 3 sy 2 5 24 01171 mode n p m2z04 7014 70c 0 755636 Gair US S Atm at sea level 8016 70c 0 231475 18036 70c 3 9e 005 18038 70c 8e 006 18040 70c 0 012842 m228 1001 70c 0
63. ow to use these key functions SphereGeom1 up down Move Toward SphereShield1 deltaS L Alt Home Alt End Pitch sourcebox1 HomeX End Rall Insert Delete Rotate Vert Pg upj Pg Dwn Rotate Horiz outsideworld Figure 2 15 Object List The row for each object has a number of display options By clicking in the different columns the user can change the display of any of the objects listed By clicking in the Name column the user can set the name for the object By clicking in Show the user can choose to hide or display the object The Color column allows the user to select the color of the object An X in the Solid column causes NucWiz to display the object as solid an X in the Trans column causes NucWiz to display the object as transparent An X in the Wire column allows the user to display a wire frame around the objects Note that to show an object as transparent the user must unselect Solid and select Trans because solid supersedes transparent Page 20 Phase 1 Final Report Graphical User Interface for Simplified Neutron Transport Calculations In this example to hide the outside world sphere the user would remove the X in the Show column on object 3 by clicking in that colum To make the shield cells objects 1 and 2 transparent the use would turn off Solid and turn on Trans by clicking in the appropriate columns The resulting geometry plot is shown below RE sphere geom mcshield Cli
64. piped Shield Geometry 2 3 Supported Source Configurations NucWiz also includes a limited set of source configurations Supported sources are a point source sphere source cylinder source and box source Only one source geometry is allowed in this initial implementation A panel is used for setting the source geometry parameters The user can also specify a source weight and energy distribution Page 9 Phase Final Report Graphical User Interface for Simplified Neutron Transport Calculations Figure 2 5 shows a plot of the geometry and input file created for a spherical source configuration NucWiz created the source definition SDEF in the input file to correspond to the spherical source f meshield mcshield1 File Geometry Source Physics Tallies Input Run Edit View Window Help Deute DEAR exceeds max length1 Formatting error in routine padstring incoming string length 2 exceeds max length1 Formatting error in routine padstring incoming string length 2 exceeds max length1 mcshield1 Nan tame sow coe su Trens wee Sener 1 SPHSrcA X 8 x x up down 4 c File Created by meshield 2 outside X x Alt Home Att End 1 a 1 SPHSre 1 Cones RO 2 2 1 Goutsideworld Leese i 3 a 2 outsideworld e Surfaces for cell outsideworld 2 so 25 98076 sdef cel 1 rad dl sil L 0 10 spl 212 e Tally information created by NucWiz nps 100000
65. px 2 3 i0 py 12 5 e surface reused 6 pz 2 5 e surface reused 7 px 2 5 c surface reused 2 py 2 5 ii pz 7 5 e surface reused 9 px 2 5 e surface reused 5 py 2 5 i2 Click New to add a new tally Point l Surface Sphere Cylinder Par Name Mats Den xce vcen zcent xten vien zien se 4 n RPP 10 5 5 5 14 n RPP 10 5 5 5 10 5 5 5 Additional Data Tally 24 Conversion Factor None x mente x Figure 2 11 Rectangular Parallelepiped Tallies 2 5 Supported Data To create a complete running input file additional data most importantly about materials must be supported Under this work the material library from the Visual Editor reference 2 was transferred to NucWiz Additionally the neutron material library was updated to include materials listed in reference 3 Page 16 Phase Final Report Graphical User Interface for Simplified Neutron Transport Calculations Figure 2 12 shows the updated material library window highlighting the composition of fertilizer as provided in reference 3 Materials Number Standard Materials Explosive Compound AM 0 000000 Explosive Compound NC 0 000000 Ferrous Sulfate Standard Fricke 0 000000 Fertilizer Muriate of Potash 0 000000 Gadolinium 0 000000 Gallium Arsenide 0 000000 Gasoline 0 000000 Glass Borosilicate Pyrex 0 000000 Glass Lead 0 000000 Number User Materials
66. rameters NucWiz automatically offers another line designated New NucWiz sets a default tally number ending in 2 and particle type but the user can override these The user can now select surfaces that exist in the geometry to tally on When the user clicks in the Surface numbers column NucWiz displays a menu of all available surfaces The user can then select which surface to tally on with only one surface included per tally This limitation may be modified in the next release For a sphere object only one surface is available Figure 6 5 shows the menu that is displayed for selecting a surface tally on a sphere object The description of the surface not the actual surface number is shown in the window Tallies Close Update Delete Selected Click New to add a new tally Point Surface sphere Cylinder Box Pa Name Surfacenumbers 0 0 0 0 0 0 2 p SurfTal 2 Sphere Object 2 ram rmm Eri Sphere Object 1 New Sphere Object 2 Additional Data Tally 12 Conversion Factor None v mremhr v Figure 6 5 Selecting the Surface of a Sphere to Tally On 26 If the object is a box when the user clicks on the Surface numbers column NucWiz displays a list of objects When the user selects an object NucWiz displays a list of box surfaces to tally on The surface is not a number but a surface location on the object Close Update Delete_Selected Click New to add a new tally Point Surface sphere Cylinder
67. reates the cells materials and surfaces in the input file Figure 2 4 shows an input file consisting of three slab shields each 5 cm thick The first and last shields contain steel and the middle shield is composed of lead 7 mcshield mcshield1 File Geometry Source Physics Tallies Input Run Edit View Window Help D c aeg FOUND stndrd n in CURRENT DIRECTORY Aa a spy HoSHield stndrd n in ag en FOUND stndrd p using DATAPATH ENVIRONMENT YARIABLE gt C Program Files LANL Vised stndrd p E Rel TESI Shoe o DMIePooDEL File Not Found usr 2 252 11 35 2 3 5 SlabShieldi delta5S File Not Found usr p 3 224 7 872 3 4 5 SlabShield2 delta5 4 0 5 L o 2 2 3 3 24 Soutsideworld 5 0 5 outsideworld E mcshield1 REO a i Click in the Plot Window td Num Name Show Color Solid Trans Wire XX le Surfaces for cell slabceont 1 SlabGeo x D x upXdown o ROSS Re ee SOE SaaS Se sus 2 Slabshie x BH ox ENIM n D 0 3 SlabShie X x lome 4 odsie X m x tss Xe DM E DPI Pa upXPa Dwn li c Surfaces for cell SlabShieldi delta5 O c surface reused 2 px 5 3 px 10 e Surfaces for cell SlabShield2 delta5 4 px 15 e Surfaces for cell outsideworld 5 a 2 5 15 X5 33 75 m224 6000 70c 0 0006 carbon steel with ENDF VI 25055 70 0 0035 26054 70c 0 056755 26056 70 7nr9 nn n no44o orntn 9n n nanaonna Additional User Data np
68. rt Calculations 1 0 Executive Summary A number of codes perform simple photon physics calculations The nuclear industry is lacking in similar tools to perform simplified neutron physics shielding calculations With the increased importance of performing neutron calculations for homeland security applications and defense nuclear nonproliferation tasks having an efficient method for performing simple neutron transport calculations becomes increasingly important Codes such as Monte Carlo N particle MCNP reference 1 can perform the transport calculations however the technical details in setting up running and interpreting the required simulations are quite complex and typically go beyond the abilities of most users who need a simple answer to a neutron transport calculation The work documented in this report resulted in the development of the NucWiz program which can create an MCNP input file for a set of simple geometries source and detector configurations The user selects source shield and tally configurations from a set of pre defined lists and the software creates a complete MCNP input file that can be optionally run and the results viewed inside NucWiz 2 0 Significant Accomplishments The following sections list accomplishments for this grant each based on the background and capabilities of the NucWiz program as outlined in the proposal 2 1 Overview of the NucWiz Program NucWiz is a program that can set up and run MCNP
69. s 100000 Sphere Cylinder Slab Box X min o X max s Deta Width Mat Density Name core 224 7 872 SlabGeom1 5 252 11 35 SlabShield1 delta5 5 224 7 872 SlabShield2 dettaS New Figure 2 4 Slab Shield Geometry 2 4 Box Shields To create box or rectangular parallelepiped shields select the Box tab in the Geometry window and specify the X Y and Z location for the center of the box with an x length y length and z length These values define the interior volume of the box To add box shields click on New in the first column of the shield list and enter the thickness for the box shield Once a user enters a thickness NucWiz automatically offers another line designated New Next click in the Mat column to set a material for this shield see Section 3 for more information on setting materials Other shields can be added by clicking on New in the first column for each additional shield and setting the thickness and material as was done for the first shield To create the geometry select Update at the top of the Geometry window and NucWiz creates the cells materials and surfaces in the input file Figure 2 5 shows an input file consisting of three box shields each 5 cm thick The first and last shields contain steel and the middle shield is composed of lead Ay mcshield mcshield1 E input File Geometry Source Physics Tallies Input Run Edit View Window Help DEH e FOUND stndrd n us
70. sssesssesseses 18 3 0 PROJECT ACTIVITIES si svssasccssccscssscssecscecscsusvecssececsscesvavecscacsdsecsssacsescessccossscesscace 23 4 0 PRODUCTS DEVELOPED ccccscscscscscscscscscscscscscscscscssscsssescscscccscscscsesesesees 24 5 0 DETAILS OF THE NUCWIZ SOFTWARE PROGRAM cccccscscssscscssscveees 24 6 0 REFERENCES wisssssaccccscssccsscscaccsescessdvecssecescsccsvevacssacsdescossssecsdeceseacssessscssecesescesedvecse 24 APPENDIX A NUCWIZ USER S MANUAL eesesesereesesosoesesercecesosossesesoeeesosorseseseeoese 26 Phase 1 Final Report Graphical User Interface for Simplified Neutron Transport Calculations List of Figures FIGURE 2 1 THE NUGWIZ MAIN WINDOW eec e NP E UNE TEN S EN VER A TERN LENS Pee EO e vd 6 FIGURE 2 2 SPHERICAL SHIELD GEOMETRY ccc cececececececececececececececececececececececececececececececececececececececscececececececececececececececececs 7 FIGURE 2 3 CYLINDRICAL SHIELD GEOMETRY oc ceccecececececececececececececececececececececscecececececececececececececececececececececececececececececesess 8 FIGURE 2 4 RECTANGULAR PARALLELEPIPED SHIELD GEOMETRY coe cecececececececececececececececececececececececececececececscececececececececs 9 FIGURE 2 5 SPHERICAL SOURCE CONFIGURATION oc cccececececececececececececececececececececececececececececececececececececececececececececececececess 10 FIGURE 2 6 CYLINDRICAL SOURCE CONFIGURATION 0c cccecececececececececececececececececececececececececececececececececececececececececec
71. t NucWiz detects if any of these elements interfere with each other and issues an error message although the user should take care to avoid entering interfering elements because there still may be configurations that are not accurately detected For example the code will allow the user to make a source cube that is larger than a shield cube as long as the two elements don t intersect 2 Creating the Geometry To create an input file the user must specify at a minimum a source configuration then optionally a shield configuration and tallies The Geometry window can be displayed by selecting the Geometry option from the main menu or by right clicking in the plot window and selecting Geometry Either method brings up a tabbed window to choose among the possible geometry options as shown below Geometry Close Update Delete_selected Sphere Cylinder slab Box X center Y center Z center Radius 5 Deta Width Mat Density Name St Figure 2 1 Geometry Creation Window The default geometry is a sphere with optional spherical shields The user can define the dimensions of the source inner core and optionally add other shields and their materials The inner core for a sphere consists of the X Y and Z coordinates of the center of the sphere along with its radius In the example above the sphere is set at 0 0 0 with a radius of 5 cm The word core is used to refer to the central volume defined by the
72. t the bottom of the Input window Any valid MCNP text can be typed in this window The current release of NucWiz does not check to see if the data entered contains valid MCNP input commands so the user must be careful in validating the information that is entered in this window Anything typed in this window will automatically be appended to the user input file in the upper portion of the Input window Additional user data that should be entered here include at least a ctme or nps line to terminate the run Additional data might include print statements or phys control cards When the user saves a file in NucWiz all of this supporting text is also written to the NucWiz file that can be read in and modified at a later date This file is not an MCNP file but a list of NucWiz objects 3l NucWiz does not yet support the automatic creation of importances Because of this limitation the user must enter the importances by hand in the Additional User Data portion of the Input window In the example below an nps command has been included along with a print command and the neutron importance has been set to 1 for all cells except the outside world which has been set to 0 Close Edit 4 204 0 001225 2 228 2 6329 gt 3 d 4 o 9 5 9 1 so 5 2 so 10 de vp 4 py AL Se pz 6 px x 7 py 1 9 pz i 9 so 25 98076 sdef x di y d2 z d3 sil H 1 000000 spi D D aL siz H 1 000
73. ta5 Click in the Plot Window to use these F P Num Name Show color soia _ Trans wire oye cn By Beebe tes Re Romi cesa 1 Sphere X x x upXdown d 2 se to 2 Spheres X x x Alt Home Alt End le LEM EILS TT e ER 4 RPPSrC1 X Home End Surfaces for cell RPPSre 1 Insert Delete is 3 outside X Pg upXPg Dwn Ooo a a AES 3 px Ed 4 py sg 5 pz c 6 pr T 7 py Bu 8 pz 1 e eae eee eee eae le Surfaces for cell outsideworld mode p sdef cel 3 x dl y d2 z d3 sil H i 1 spl D GO si2 H i T sp2 D D d si3 H sg 1 sp3 D D mZ204 7000 02p 0 755636 Sair US 8 Atm at sea level Additional User Data Source Point Sphere Cylinder Box Xcent Y cent Zcent Xlen 2 Name RPPSrc 1 Y len 2 Zlen Sel 2 New wes Enter Energy Spectrum Below spaceitab delimited energy particles sec Histogram Bins z Figure 5 3 Adding the Source to the Input File In this example the surfaces and cells that define the source have been inserted into the input file Additionally the SDEF that defines the rectangular parallelepiped has been inserted into the input file Once the source is created the user can modify this source description geometry and or materials and then select Update to regenerate the input file 17 5 1 Point Source To create a point source select the Point tab in the Source window and click on New in the first
74. tsideworld 4 so 25 98076 sdef axs 1 0 0 cel 1 ext dl pos 10 rad d2 L 0 20 21 g L a 310 sen i Source Point Sphere Cylinder Box Rad Axis 10 Mat Den 0 001225 XBase Y Base Z Base Len Parallel to X wer o Enter Energy Spectrum Below spaceftab delimited energy particlesisec Histogram Bins v Figure 2 6 Cylindrical Source Configuration Page 11 Phase 1 Final Report Graphical User Interface for Simplified Neutron Transport Calculations Figure 2 7 shows a plot of the geometry and input file created for a rectangular parallelepiped source configuration NucWiz created the SDEF in the input file to correspond to the rectangular parallelepiped source Pi meshield mcshield1 File Geometry Source Physics Tallies Input Run Edit View Window Help Ooo eat FOUND stndrd n using DATAPATH ENVIRONMENT YARIABLE gt C Program Files LANL Vised stndrd n FOUND stndrd p using DATAPATH ENVIRONMENT VARIABLE C Program Files LANL Visedistndrd p File Not Found usr n File Not Found usr p mcshield1 c File Created by mcshield Wan p Nae show color soa Mii CENIE POEA ISe taaa e 7 n Ae zd AT 6 Soutsideworld 41 RPPS X x up down 3 o 7 outsideworld 2 outside X x Alt Home Alt End Home End Insert Delete OMNEA uL dL dE ERN Pg up Pg Dwn i le Surfaces for cell RPPSrc 1 ME S DE r
75. w Window Help indu msejet FOUND stndrd n in CURRENT DIRECTORY FOUND stndrd p using DATAPATH ENVIRONMENT YARIABLE gt C Program Files LANL Vised stndrd p File Not Found usr n File Not Found usr p WP mcshield1 1 SPHSci X x x upXdown 3 SPHTat4 X x Alt Home AIt End 4 SPHTa14 X x Tona 5 SPHTak24 X x Jet o oss R SPHTala4 X X Pg upXPg Dwn 1 SPHSrc 1 5 New wet Enter Energy Spectrum Below space tab delimited particlesisec Tallies Close Update Delete Selected Click New to add a new tally Point Surface Sphere Cylinder Box SPHTal 4 e o oa oam 14 n SPHTal 14 20 24 n SPHTal 24 20 34 n SPHTal 34 20 New i Additional Data Tally 44 Conversion Factor None Figure 6 9 Creating Sphere Cell Tallies 29 To insert box rectangular parallelepiped cell tallies select the Box tab and then specify the X Y and Z center of the box and the X length Y length and Z length of the box cell tally Figure 6 10 shows four box cell tallies arranged around a central spherical source The sides of the boxes are all different lengths to demonstrate that the box cell tallies are actually rectangular parallelepiped objects P mcshield mcshield1 Elle Geometry Source Physics Tallies Input Run Edit View Window Help Dg BH teel FOUND stndrd n in CURRENT DIRECTORY FOUND
76. y 36 The isometric view of the geometry can be changed to a cross sectional view by selecting the appropriate basis view in the pull down menu on the right under Update Shown below is an XY view of this geometry that can be displayed by selecting the XY option in the pull down menu WPsphere geom mcshield DER Num Name Show Color Solid Trans Wire _ Drs M i Plot Window to ps ues key functions SphereGeomt X up down Move Toward SphereShieldi deltaS X Alt Home Alt End sourcebox1 x Home End Insert Delete Rotate Vert outsideworld Pg upXPg Dwn Rotate Horiz Eo SphereShi sourcebox1 outsideworld Figure 8 4 Cross Sectional View of the Geometry 37 The user also has a number of options for moving the display in three dimensions The user can change the geometry using special keys as outlined in the table below Table 7 1 Three Dimensional View Display Keys Roll Rotate about the axis coming out of the plot plane By using different combinations of these keys the user can move through the geometry in three dimensions In addition to the top list of objects a list on the right also included Clicking on the objects in the list on the right brings up the window used to create the object allowing the user to edit the object 9 Saving and Loading NucWiz Files At any time the user can save the file that is being generated When the file is saved both the MCNP input file is saved with

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