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JANIS USER'S GUIDE - OECD Nuclear Energy Agency

1. Coeff Time of flight gating used to reduce background and pulses caused by scattered neutrons ERR ANALYS No information STATUS APRVD Approved by author HISTORY 19691203cC Relative cross section 198008134 Converted to REACTION formalism Cross section ratio Nb points 3 AN Local Janis Interaction Data incident neutron Exfor E Cross sections U235 10016 006 0 L4S69 NINL 92 U 235 o L e 10047 096 0 BNW71 N TOT SIGsc Compare Le 10047097 0 BNW71 N TOT SIG C Searches gt L e Energy angle distributions U235 10016 0C Computations gt DE Energy angle d Det JEF 2 2 Cross sections U235 Weighting s Display EXFOR File Unselect all Settings Show horizontal lines 32 9 1 6 Computation JANIS offers different options for manipulating cross sections The Menu option Tools Computations allows simple arithmetic operations to be performed with basic data An example is shown in Figure 25 Here the aim is to define eta as the ratio of neutron production cross section nu bar times fission cross section and absorption cross section fission plus capture By placing the cursor in the Equation field and using the mouse to select the appropriate reactions in the tree list the user can form a simple equation The operators and and the parentheses can be entered using the keyboard
2. INEBHENUBH INRA n stable x INACTIVE M Materials 1 Hydrogen 2 Helium Lithium Beryllium 5 Boron Carbon 3 7 Nitrogen Oxygen 3 Fluorine 10 Neon 11 Sodium Lt co H E ee 4 E e c espe EE E e co zi Databases 7 73 file H Jjanis bases base jef22 3 Interaction Data incident neutron JEF22 Energy angle distributions Q Energy distributions Q Angular distributions Q Cross sections 7 73 Radioactive Data 73 JEF22 4 Q Fission yields data Radioactive decay data Radon Rn N 148 Z 86 A amp A 234 5 pixels 1 The Menu bar 2 Legend for the Chart of the Nuclides Depends on the category of data displayed 3 Nuclide Explorer Elements available in the database are displayed by ascending Z number Expand one element to see the corresponding isotopes 4 Database Explorer All loaded databases are displayed here The category of data and the evaluation name are given The selection of one evaluation highlighted text causes the display of the appropriate Chart of the Nuclides 5 Zoom level control 6 Zoom scroll bar 7 The Chart of the Nuclides Provides access to nuclides contained in the selected database Empty if no database 7 2 Navigati
3. Stable 144 pixels 1 Diagonal displacement of the Chart of the Nuclides 2 Horizontal scroll bar 3 Vertical scroll bar The Chart of the Nuclides can be navigated using the following means e Keyboard arrows e Horizontal and vertical scroll bars e Diagonal displacement buttons e Mouse displacement Select any position on the chart and move the mouse while holding down the left button Any displacement of the Chart of the Nuclides can easily be done in this way The properties of a single nuclide can be shown at a higher zoom level by right clicking on the corresponding cell An enlarged square containing information on the selected nuclide will appear as shown in Figure 3 for 5 Ag Figure 3 Details for one particular nuclide Ag IS Janis file H janis bases base_jef22 Radioactive Data JEF22 Radioactive decay data File Database Tools Chart Help BRANCHING e EC Betat List hr L2 Beta mL i Cde s Cds Uu ct amp m 4 MH NL 0ND ISIS d z gt e m No data dt rin LLj2 mLI Materials H AgtU2m M Ag103 Agt03m 107 Q Ag104 47 Ag 60 Q Agio4m Q Ag105 zal Q Agi05m ITE Agi06 nae Agio6m Q Agi07 Q Agt07m m b a Databases 3 filezH janis bases base jef22 Int
4. Figure 25 The computation window iol xl Create Pool Source y1 Lz ri r Section 4 MT 80 z n30 Cross section 4 amp MT 81 z n31 Cross section MT 82 z n32 Cross section MT 83 z 33 Cross section amp amp MT 84 z n34 Cross section MT 91 z ncj continuum Cross section 1 23 MT 102 zy radiative capture Crazz ection Cross section Variance RJ Hy MT2452 z nubar T 9 Eta L Neutron production 4 Equation MT452 Neutron production MT18 Cross section i lt M118 Cross section MT102 Cross secti Marre Eta Apply Save The Apply button causes the operation to be performed and the result added in the Renderer window for plotting When all operations are performed the Close goes back to the Renderer window By default the result of the operation is added to the first parameter in the equation here to nu bar The Save button enables the operation to be saved for further use For example the equation for eta can be established for one fissile nuclide say U and applied for another fissile nuclide e g Pu or a different evaluation file The Save button also enables the default level under which the operation is displayed in the Renderer Anchor node to be changed In the example shown in Figure 26 the user can choose to save eta under fission capture or n
5. Printing options The File Print option enables to print the information displayed in the Renderer panel Note however that the settings of the printer can not be changed through the properties of the printer The menu option File Print Setup should be used instead 54 15 References The format of the evaluated nuclear data files the ENDF 6 format is described in the following manual ENDF 102 Data Formats and Procedures for the Evaluated Nuclear Data FILE ENDF 6 Report BNL NCS 44945 01 04 Rev an electronic version in pdf format is available at the site http www nndc bnl gov nndcscr documents endf The ENDF B VI 8 data used in the JANIS 2 0 CD ROM was taken from Cullen Dermott E POINT 2003 Temperature Dependent ENDF B VI Release 8 Cross Section Library Report UCRL ID 127776 Rev 2 The JENDL 3 3 data used in the JANIS 2 0 was taken from the JENDL 3 3 CD ROM distributed by JAERI The EXFOR format is described in the following report EXFOR Basics A Short Guide to the Nuclear Reaction Data Exchange Format Report BNL NCS 63380 2000 05 Rev a pdf version is available at http www nndc bnl gov nndcscr documents exfor The content of the CINDA database is described in the CINDA 2003 book a publication of the OECD Nuclear Energy Agency ISBN 92 64 02144 2 ISSN 1011 2545 The NUBASE file describing nuclear data properties was taken from Audi G et al Nuclear Physics A Vol 624 pp 1 124 1997
6. When right clicking with the mouse in panel 2 a pop up menu offers several features for the manipulation of data Most of these features will be described in more detail later The Unselect all and Settings options are specific to the Renderer The first is fairly straightforward When selecting the Settings option the window seen in Figure 6 1s displayed It enables to define change the hierarchy of parameters in the parameter selection panel 2 The default option is shown in the figure above however it might not be the most appropriate choice when specific comparisons are performed For instance if the user wants to compare cross sections for the same nuclide but with different libraries the order can be changed to Base Datatype Category Material Reaction Evaluation 13 Figure 6 Definition of levels in the selection tree i01 xi Levels order Base Datatype Radioactive Interaction Top Evaluation Jef2 2 Jeff3 0 Category Cross amp naular Material ReactioanAMorLk OK Save as detauts Cancel The Display Panel 1 Figure 5 gives the result of the selection The example in Figure 5 shows a cross section plot One can change the settings of the plot e g the colour of the line or of a table by clicking on the corresponding cell in Column 2 the Settings column which opens the dialog box shown in Figure 7 Figure 7 Adjust display properties dialo
7. an electron version can be obtained at http www csnsm in2p3 fr AMDC nubase nubtab97 asc 16 Acknowledgement A team of computer software students see the list below belonging to the Aquitaine Electronique et Informatique a Bordeaux based Junior Enterprise developed the first version of JANIS Nicolas Soppera was certainly the most active contributor to the project and he continued to work on the development of JANIS 2 0 during his stay at the NEA in 2003 Ergun Tuncay and Mark Kellett contributed with the CINDA search part Ali Nouri has been in charge of the project since the beginning and contributed to the specifications and testing JANIS benefited from the useful feedback provided by several users Emmeric Dupont CEA Cadarache and Christopher Dean Serco Assurance made important contributions to the testing of beta versions and suggested many improvements 55 JANIS DESIGN AND DEVELOPMENT TEAM AEN NEA N Soppera A Nouri P Nagel E Tuncay OECD Nuclear Energy Agency www nea fr janis AQUITAINE ELECTRONIQUE INFORMATIQUE N Soppera A Ahite B Taton J Patrouix F Lecompagnon C Cunin O Rioland and L D Eurveilher Aquitaine Electronique Informatique www enseirb fr aei 56
8. hAT E c or 6d Em M m um i 30 9 5 Comparison with experimental data EXFOR The comparison between evaluated and experimental data can be made using the Tools Compare Menu item and selecting the EXFOR library in the Compare Explorer window or using the option Searches EXFOR This latter option can also be accessed by selecting a reaction and right clicking with the mouse With the Tools Compare option the user needs to select the EXFOR works he wants the data to be compared with Figure 22 Figure 22 Selection of EXFOR works iol xi W235 Add to list 10015 005 0 LAS69 NJNL382 LI 235 SIG 10047 096 0 BMWT1 N TOT SIG Load base 10047 097 0 BMWT1 N TOT SIG 10054 002 0 LAS69 NF SIG 10057 002 0 LASTO NF SIG 10120 002 0 LAST1 NF SIG Siue 10225 025 0 BET73 M TOT SIG Al 10225 026 0 BET73 M TOT SIG 10233 D02 0 4NL64 M ELY92 U 235 SIG 10249 004 0 ORL73 NF SIG AV Show datatypers 10249 005 0 ORLT3 N G382 LI 235 SIG 10267 006 0 ORL76 NF SIG AV 10267 007 0 ORL76 N G382 LI 238 SIG 10267 008 0 ORL76 N ABS SIG AV 10257 022 0 ORL6 NF SIG AV noxevaMtens ede 10267 023 0 ORL76 M ABS SIG AV Al 10267 024 0 ORL76 MF SIG 10267 025 0 ORL76 N ABS SIG E 10267 030 0 ORL76 NF SIG AV Show category es 10267 031 0 ORLTE M ABS SIG AY 10267 037
9. tt Pt tt Ee cea P ee PL ee PL ee te PL cae Pt Pt EERE PL ee EISE BEES 0 0101 BEET L s N E U EL 010 S O e O a S EERTE EERTE BEADNI i a 35 9 2 Energy distributions The energy distribution gives the probability of emission of a secondary particle at a given energy E This probability also depends on the energy E of the incident particle 2 in Figure 30 and it is generally represented as p E E Figure 30 shows an example of an energy distribution for secondary particles Energy distributions are given in the ENDF format in File 5 Different methods may be used in the evaluation for the representation of the energy distribution tabulated function or analytical expression The method used in the evaluation is shown in the display window 3 in Figure 30 Figure 30 Example of an energy distribution for secondary particles CO Local Janis JEF 2 2 Energy distributions U235 File Tools Selected ky Energy distributions Plotter MT 18 z fission total Energy distribution for U235 from JEF 2 2 from Local Janis x IL v1 v 1Li v y E rgy og in eV j Ene xminefi00 8 xmax ozr Ymin 3 78091 0000000038E 24 Ymax 3 49074E 7 More Move zoom x Secondary energy 1 Energy distribution E Display 1 0E 5 2 Representation 7 F arbitrary tabulated 3
10. 0 in ev Theta fus 5000 0 in ay E fus h AUTET in ev Ce a The available options are e Constant spectrum The constant is to be specified by the user e XY spectrum Allows the user to use a hyperfine flux structure to take into account effects such as self shielding The flux can result for instance from a hyperfine slowing down calculation The user needs to specify the location of a text file containing the weighting flux definition AE Each line of this file contains a value of E and fi separated by blank s A continuous weighting function AE is constructed by assuming a linear linear interpolation between successive values of jfj Note that no blank lines are allowed after the last E fi values e PWR spectrum Details are given below e General spectrum Details are given below The PWR spectrum and General spectrum are defined using the following components e A Maxwellian spectrum used at thermal energies Where 0 KT is the thermal energy to be specified in eV x E C Bex 2 e Aslowing down component defined as C 2 eec e A fission spectrum characterised by 0 the fission temperature in eV 3 KE c E ex E fis 21 e A fusion component of the neutron spectrum as in the d T He n reaction characterised by a fusion energy and a fusion temperature both to be defined in eV X E C ex sc JE JE 4 Jus The PWR spectrum uses components
11. 2 from Local Janis x Log v y Log x 5 xsqn X Xmin h DE 5 2 5 Xmax 2 07 Ymin o 16165236297025642 Ymax E 675807999119706 More 7 xis Move Zoom 0 5 0 25 le 5 le 4 0 001 0 01 0 1 1 10 100 1000 le4 le5 le6 le E fin e ACT E UTTTI F P L 4 MT 17 z 3n Cross section PT L MT 18 z fis Cross sec iia ci PT tta Searches gt N v 6 9 MT 19 nf f Computations New PT 9 MT 20 nnf weighting Absorption E PT r MT 21 n 2nt Dis PT play EXFOR file L MT 37 z 4n Pr L e wr 38 nni Unselect all PT L 4 amp naT_c4 6 4 Settings lor In the Computation window a tab called Pool displays the list of operations saved by the user A checkbox for each equation in the Pool allows the user to control whether he wants the equation to be automatically performed or not If the Auto checkbox is selected the result of the equation will always be displayed when the basic components are present In the example presented in Figure 28 every time a fissile nuclide is explored eta will be calculated and saved under the appropriate anchor Figure 28 Automatic application of a pre defined operation iol Create Pool Prefix expression Absorption C K Cross section MT102 Cross section Eta I C0 M7452 Neutron production Cross section Cross section MT102 Cross section 34 Note that a computed cros
12. 95969e2 8 20164e1 1 8959262 7 83769e1 1 83426e2 68256e1 1 77464e2 43597e1 1 717e2 7 19766e1 1 6612582 6 96734e1 1 60737e2 6 74476e1 1 65527e2 6 52969e1 1 504892 6 32187e1 1 45619e2 6 12108e1 14091122 5 82709e1 1 363862 5 7 3958e1 1 319862 5 55855e1 1 27706e2 5 38381 e1 1 23595e2 21494e1 1 1962162 05186e1 1 1578e2 4 89439e1 1 12068e2 4 74236e1 1 0848e2 4 59559e1 1 05013e2 4 45392e1 1 01662e2 4 31718e1 9 84245e1 4 18524e1 4 05794e1 Cross sections for Fe56 from 300K from file I xpl datZ users nouri POINTZ2000 More ENDF Cross section Reaction G value n o eV Weighting 3 52962e1 Source Settings Display Fe58 from 300K Mfileviuko1 dat2 users nouri POINT20004 9 1 2 Weighting of pointwise cross sections JANIS offers various options for cross section averaging When a cross section 1s selected from the Parameter Selection Panel the Weighting button appears in the right hand side panel Options Selection Panel When this button is pressed the dialog box shown in Figure 18 appears Two tabs are available for entering the group structure and weighting spectrum descriptions 25 Figure 18 The Weighting dialog box Group tab AF Weighting JOf Group Spectrum Gr
13. AE15 pr Biz15 mas B BS n 11 A218 ME Poets Bass f jen ms n 12Bi214 Beta Pois Fa min iI EE n 13puz18 Bits prn 1 78 ms iti pao ms n 14 P0715 laphi P1 1 78 rg 5 agag D ms n 15415 Alpha Bizi 1 n 1ms n 02 ms n 1 amp Pbz11 Beta pi2t1 38 1 rnin 2 8 p 1TBi211 jBeta Po2it 2 17 min p 33 pas p 18Bi211 Alpha mmn 2 17 min Bar2Te Fag 18P 5211 Alpha Pb207 51G ri 1 dm n 20 TOT Beta P5207 4 77 rnin 1 lags Source Settings Display Oo Rao Hla HE anismepaentonidatabasestbase ja Radioactive Data I jay Radioactive decay data ey uas General informations Girmeral infamatons i MTs451 Heading or time inf rmatian 2 73 Decay datas Decay data Continuous Nisutr n o Deray general data ry pam Deecrebe Alpha Discrete Electron T PI 33138 853 g Discrete X Rays Pam p Garena DZponlamegus fission 8 7 U2T5m BOBO Ios Figure 37 Example of a decay path in graphical format E uzas iff Decay path for uzas Decay path Tm 134 135 138 qa v T TA 141 Ta ucl If required information for continuing the chain is not available in the evaluation nuclide produced by the decay mode not available in the evaluation the frame is left empty The chain may be represented on either A Z or N Z axes which can be interchanged by clicking on the appropriate button switch to N Z or switch to A Z A scroll bar exists to cont
14. File Tools Selected kx Angular distributions Plotter vie 120 elastic scattering Angular distribution for Pu239 from JEF 2 2 from Local x Lin M M Lin Y in Sys Enerzy 1 OE 5 Xnin 1 o Energy 1 0E Xmax f 0 Ymin 0 004392495205368027 Ymax 2 0 More Move Zoom M cos of angle t m Angular distribution E Display 1 0E 5 2 EE 1 0E7 ERES Representation Polynomial Frame of reference ECCEE mM toe A C3 Local Interaction Data incident neutron JEF 2 2 Angular distributions Pu239 General informations MT2451 z Heading or title information 5 EHS MT 2 z z0 elastic scattering C Angular differential cross section Angular distribution MT 16 z 2n Angular distribution MT217 z 3n Angular distribution o UBD lOOMNOROR Le 1 Selection of the x axis variable mu or 2 List of incident energy points at which the angular distribution is tabulated 3 Method used in the evaluation for the representation of the angular distribution 4 Frame of reference Centre of masse CM or Laboratory system 5 Reaction selection list The contents of fields 2 3 and 4 Figure 33 depend on the selected reaction on the selection item list Even when a reaction 1s selected highlighted but a display not requested these fields will reflect the informati
15. fin eV ACC Settings Display 3 Local Janis Interaction Data incident neutron JEF 2 2 Energy distributions U235 fe e General informations MT 451 z Heading or title information C H S MT 18 z fission total 4 E Distrib x section P Energy distribution Iv F MT2455 nubar d p 1 Selection of the x axis variable or E 2 Incident energy E 3 Method used in the evaluation to represent the energy distribution 4 Reaction selection list By default the distribution is displayed for the first tabulated incident energy The list of incident energies E at which the distribution is tabulated in the evaluation is shown in the field indicated by 2 in Figure 30 The panel for incident energy selection has the form of a table with an empty last row When selected this empty row enables to enter a new incident energy by either selecting it from the scroll panel or inputting a real number with the keyboard The entry is validated by hitting the Enter button The energy distribution corresponding to the new value 1s added to the graph and a new empty row is added at the end of the table Note that for energies between tabulated values JANIS constructs the distribution by interpolating according to the interpolation law specified in the evaluation 36 The scroll list 2 and field 3 in Figure 30 depend on the selected reaction highlighted line in the list of items to be displayed I
16. infanrieian Ln Resonances dala Hesohed parameters 1 UE 5 E gU LUI m Uniniohasd pasarnmelers E8200 f E 300000 0 al Indegral dats n LIEST E fT MTz2 r3 C Pm MT 4 rh 2 L mim MI 16 iz 2m TPIT MT 27 zm L Pm MT 20 gno Crim MT 51 nl TPIT MTz52 fen CRM MT253 nin3 C em Ed 1 The display panel 2 The parameter selection panel 3 The options selection panel 4 The Menu bar representation of the data up to a certain precision The result of that is a pointwise file which covers the whole energy range and represents the cross section at a certain temperature see an example in Figure 14 This format of data is more appropriate for users who are interested in viewing and comparing cross sections The databases distributed with JANIS contain a combination of processed and evaluated data In fact the cross sections were constructed and Doppler broadened to 300 K The original cross sections in the evaluation are then replaced with these constructed data thus forming a hybrid file containing both resonance parameters and constructed cross sections Resonance data can be displayed in tabular format see Figure 15 where Eo eV is the resonance energy e is the orbital momentum e Jis the target nucleus spin e Jis the compound nucleus spin e gammar gammay gammac and gammar eV are the resonance widths e sigmao T is the cross section at Eo where the
17. m 1h 5 2577 4 8077 D 8 32942e1 p 1 1 1 35295 8 0285e 1 0 5 04476e1 o 2p 3 38073 2 8073e 1 m 8 20782 p 0 6 1205e2 6 1146e2 ge n 3 64065e1 0 1 5e 3 8278 3 5228 05e n 3 22096e1 8 3628e4 0 D 5e 1 1 21564e3 1 2151e3 5 4e 1 0 3 224441 9 033864 0 111 5 2 240201 2 1979e1 4 23e 1 5 85976e1 x Source Settings Display Fe56 from 300K fileI xp1 dat2 usersiouri POINT2000 a General information l Resonances data X S Interaction Data incident neutron for Fe56 from JEFF 3 T2 File Data Help k Resonances Resonances Resonances for Fe56 from JEFF 3 T2 from file I xp1 dat2 users nouri JEFF3P Sigma E Resolved parameters 1 0E 5 E 862000 0 fin barns Xmin oo O TU j ymin 0 7013246392059871 O Resonances Tho gt in Formalism Reich Moore o in 1000 led 1e6 E in eV Source Settings Display Fe58 from JEFF 3 T2 file l xp1 dat2 users nouri JEFF 3P a General information I Fs Resolved parameters 1 0E 5 E 852000 0 iv PIM Unresolved parameters 862000 0 E 3000000 0 T Integral data I MT 1 n total Notes The formalism used to represent the resonance parameters in the evaluation file File 2 is given in the right hand side panel Reich Moore in this example The temperature in Kelvin is also shown and is used to compute the Doppler width which is combined with the total width for the calculation of
18. sigmao T The user can enter a new value for the temperature and confirm by pressing the Enter key on the keyboard 24 Cross sections can also be represented using the graphical and tabular modes the tabular mode is shown in Figure 17 and an example of the graphical mode was shown in Figure 14 The reaction Q value is given in the right hand side panel and in the graphical mode other information is available The energy range for the two axes Xmin Xmax and ymin Ymax These values can be changed in order to control the zoom level press the Enter key for confirmation A click on the panel close to Xxmin Xmax Vmin OF ymax Will cause the plot to come back to the automatic zoom level A checkbox close to x sqrt X If this checkbox is crossed the quantity displayed is then sigma E sgrt E as a function of E where sigma is the selected cross section This parameter is used to study the behaviour of cross sections at thermal energies The Weighting button enabling to calculate a groupwise cross section This item will be described in more detail later Figure 17 Example of tabulated cross section data j Interaction Data incident neutron for Fe56 from 300K File Data Help W Cross sections amp Cross sections cmm 2 237382 9 35173e1 MT 1 n total MT 2 z z0 21543862 3 0484461 2 08384e2 8 75721e1 2 02564e2 8 47471e1 1
19. the incident and emergent particles and E is the energy of the incident particle The distribution may be defined in either centre of mass or laboratory systems This frame of reference is shown in field 4 see Figure 33 f may be given as a tabulated function of u as an expansion of Legendre polynomials or as a constant value over the whole energy range when the distribution is isotropic The representation used in the evaluation is shown in field 3 Figure 33 In some cases the representation used for the same reaction changes over the energy range In such a case JANIS will show the two representations in the display selection list The incident energy points E at which the distribution is tabulated are given in panel 2 which has the form of a table with an empty last row When selected this empty row enables a new incident energy to be entered either by selecting it from the scroll panel or inputting a real number with the keyboard The entry is validated by hitting the Enter button The angular distribution corresponding to the new value is added to the graph and a new empty row is added at the end of the table Note that for energies between tabulated values JANIS constructs the distribution by interpolating according to the interpolation law specified in the evaluation the default value being the first tabulated point 38 Figure 33 Example of an angular distribution j Local JEF 2 2 Angular distributions Pu239 Bl x
20. width used is the square root of the total width squared and the Doppler width squared calculated at a temperature 7 to be specified in the Options Selection Panel 3 in Figure 5 at the right of the screen 23 Resonance data can also be plotted to show sigmao Eo as a function of Eo see Figure 16 Figure 15 Example of tabulated resonance parameters f Interaction Data incident neutron for Fe56 from 300K File Data Help Resonances kx Cross sections Resonances Cross sections Resonances for Fe56 from 300K from file I xpl dat2 users nouri POINT2000 EO Jic 4 es J Res gammar t gammaN t gammaG gammaF sigmaom lu 3 084665 4 733665 5e 1 3 084615 5 6991 D D 24213e4 0 D5e 1 2 708163 2 707183 1 1 11375e2 2 4381e3 0 O 5e 1 1 94282 1 9334e2 8 5e 1 1 10159e3 1 1497e3 Q0 1 5e 1 6 357e 1 B 17e 2 5 74e 1 2 27744e2 2 3495e3 0 21 5 5021e 1 2 1e 4 7 5e 1 p 42822e 1 1 2448e4 0 1 5e 1 j4 5281e 1 2 81e 3 4 5e 1 1 3448 1 774884 0 1 4 548e 1 1 48e 2 4 84 o 21 4 17e 3 0 1 2 1481e 1 0 0 1 41016e3 1 4093e3 0 9 70131e1 b 1h 2 79132 3 5132e 1 0 1 98365e1 TSE D 1 1 08 5 7e 1 3 84137e1 T l0 0 lo 1h 978e 1 QD 38e 1 m 3 41769e1 D 1h 5 4241 5 1391 Y 1 11002e2 Formalism D 1 1 1 7688e1 1 7294e1 n 1 01175e2 0 1 1 7042 1 1242 n 3 32257e1 D 1 4 87e 1 3 7e 2 0 3 81842
21. work automatically Please contact the JANIS development team janis nea fr for troubleshooting JANIS can also access data contained in a user s file This can typically be used to view the data contained in an ENDF 6 formatted file or processed file in PENDF or GENDF format which contains a single material or a collection of materials This is performed using the Menu option File Open which allows to browse the user s directories and specify the target file to be opened This option is offered for users who want to view the data without necessarily storing the structure of the data on a hard drive for further use If the user wants to use the data frequently it is better to import it into a database and use it as a local database see the import option in Section 8 1 Whatever the option used JANIS structures the data in a hierarchical way Type of data Dataset Category as shown below Database name location on the local or network disk or on the Internet i Type of data e g neutron interaction data decay data Data set typically an evaluation e g ENDFB67 or experimental data EXFOR Category e g cross sections angular distribution 17 Typical examples are given here POINT2000 Interaction data incident neutron 300K Energy angle distributions data of File 6 in the ENDF format Energy distributions data of File 5 in the ENDF format Angular distributions data of File 4 in the ENDF format Cros
22. 0 ORL76 NF SIG AV 10267 038 0 ORLTE M ABS SIG AY 10280 005 0 MBS74 N TOT SIG 10286 002 D 4NL70 NF SIG see Bel 10302 002 0 ORL74 M F SIG AY All 10304 002 0 NBS72 M F SIG SPA 1034 4 002 0 MHGT amp M F SIG 10333 002 0 AL 74 NF Sle Show reactions 10333 003 0 4NL74 MF SIG FI 10 333 DD4 0 ANL74 MF SIG 10333 DD5 0 4NL74 MF SIG 10333 006 0 ANL74 MF SIG 40333 nnm OPA TAn eR ir all d HE Close M Interaction Data incident neutron M M Cross ection EEE ERE ERE ERE ERE ERE LE BEEBEBEEBEBEBEBEEBEBEBEEEBEBE EEB EEBEEEB EEEBEEBEE t Ss oso The Searches EXFOR option Figure 23 provides more flexibility by allowing the user to search in the experimental database for data satisfying criteria such as the energy range the year the experiment was performed and the reaction definition particle product or process 3l Figure 23 Result of an EXFOR search Ini x Criteria PERN Work subwork Reset Target Z B2 A p35 I Open results range E ev C value c TUS ev Save results Print Lab Year Lab lt Year lt Close Reaction Products Particle Particle Process Product Branch Parame conside Modifiers Dataty st ch m hf NT ibe I NT zi zi Serhhitoy a e Energy Search work Subwerk Lab Year Tar
23. 1 2 and 3 as given in the following formula E CLE e for E S E n sth C x E E for B n lt E Pin E C VE EL RoR X SUUS S Exp 0 Or gt max epi _ fis This is equivalent to IWT 4 in NJOY The user needs to specify the following energy limits Emi Where components 1 and 2 join Emaxepi Where components 2 and 3 join C5 the constant value of the slowing down component is set to 1 Ci and C3 are calculated by the continuity conditions at Emax and Emax epi CxS E and C T E 2 max th exp ae E exp _ JT max epi 0 A The General spectrum uses all the components as given in the following formula C E ex for E E i sth C X E E lord oS SE vas y E C VEe Tes exf S WE ca j for E gt E _ fis fus This is equivalent to IWT 6 in NJOY The following energy limits need to be specified Exi Where components 1 and 2 join Emaxepi Where components 2 and 3 join Efi where components 3 and 4 are equal 28 C2 the constant value of the Maxwell thermal spectrum is set to 1 Ci and C3 are calculated by the continuity conditions at Emax tn and Emax epi as above and C4 the constant value of the fusion spectrum is calculated such that spectra 3 and 4 are equal at Emax fus Components 3 and 4 are added for E gt E max epi The averaged cross sections are calculated using the following definition o E x E dE g S8
24. 3 3 experimental data EXFOR bibliographical data CINDA nuclear structure data NUBASE 97 All this data could fit on a single CD ROM Consequently two CD ROMs were produced and some information was duplicated to ensure an easy manipulation of the data Both CD ROMs contain the software the documentation and the necessary scripts to run the software In addition the first CD ROM contains all the evaluated nuclear data libraries the experimental data EXFOR and the NUBASE 97 nuclear structure data The second CD ROM contains the bibliographical data CINDA the experimental data EXFOR and the nuclear structure data NUBASE 97 The two CD ROMs have a similar structure Directory data contains the basic files e g evaluated files EXFOR works etc Directory databases contains the relational databases Directory software contains the JANIS and database executable jar files Directory java contains the Java runtime environment for Windows and Linux Due to the lack space on the first CD ROM this directory is only available on the second CD ROM Files janis bat and janis sh are the executable files to be used for running the software e Directory documentation contains the users manual file janis 2 0 manual pdf The relational database management system used within Janis is the Java Mckoi SQL database see http mckoi com database 3 Requirements and compatibility To use JANIS th
25. Databases panel without the folder sign Use the Remove button folder structure to unload it The Chart of the Nuclides and Nuclide Explorer display the content of the category selected by the user in the Databases panel This category is highlighted 2 8 3 Viewing data directly from a file The Import and Load operations discussed above are recommended when the user is dealing with an important number of nuclides and for which he wants to keep the data on the disk for repeated accesses to the database Otherwise the option File Open is preferable when the user wants to view the data contained in a file without necessarily storing the interpreted file to the disk In this case the original file is typically an ENDF material an output of a processing code or an EXFOR work A pop up window is opened when the File Open Menu option is selected This enables selection of the file from the appropriate location on the disk The data contained in the original file will then be interpreted by JANIS and converted to a database and stored in the user s temporary directory This database will be deleted upon exiting JANIS When the original file contains data for more than one material or when different data types are present e g cross section angular and energy distributions the data selection list in the Renderer will show a structure reflecting the various data categories 9 JANIS features through exampl
26. F3T2 Radioactive decay data BRANCHING D Neutron n Hydrogen Helium Lithium Beryllium Boron Carbon Nitrogen m E Ay filevIp1 dat2fusers nouri E Radioactive Data 8 8 JEFF3T2 Radioactive ded 7 3 Visualisation tools The Renderer The Renderer see Figure 5 offers e different ways of representing the nuclear data for a particular nuclide e g graphical tabular e provides tools for the manipulation and comparison of different nuclear data sets The main window is composed of three main panels and a Menu bar The content of these panels and the options available in the Menu bar depend on the context category of data and kind of information displayed The Parameter Selection Panel 2 Figure 5 is a table of three columns and as many rows as available information to be displayed The following information is displayed e Column I Gives the designation of data ENDF MT no EXFOR work no etc e Column 2 Shows the colour of the generated plot which links to another panel enabling the modification of the curve settings e Column 3 Contains a checkbox for selection deselection of data sets 12 Figure 5 Data visualisation The Renderer fs Local JEF 2 2 rd sections F19 File Tools Selected i Cross sections Tabler Plotter b MT 1 n total Cross section for F19 from JEF 2 2 from Local x Loa y 1 xs
27. HOLT SS DeC data SOak6lbeseceteansdudt trm ud e odit NEL nsa idi pd oe t ea uinea Er 47 POD TXT OR SCOR uin et tui Mee tibus tee Men 48 TU 3 CINDA SOUFC V ssec vea eed E E edd bu Due 49 10 3 1 CEINDA Search Dialog Box ODIOTRS i itn tp o toad hito Redes ees 49 103 2 The CINDA Search histoF y DOX ssi i oU Ub c abo diu 50 10 33 Sorne of CINDA VOU CV Ol POS UES sos emus arm tic dae a qe tir eat 50 10 34 Accessine linked DANCTS GDSITOCIS i AW WR M GE 50 VAG zoe drerhetetoas EE os icon Fete au aad asp omae EU eu unn Mani 50 CUSCOHISTUOD iere deed sara eue sain imei E adimi M RUM 5 JPN GOTO nec vc rr ET 51 12 2 Options for the display of the Chart of the Nuclides sss 51 12 3 The Renderer panel options cccccccccccccc cece cence cece eee eene nnn nnne ns 53 Saving the displayed data to the disk ccc ccccccccsssssseeeeeeeeeaaaeeeeeeeeseeeeaaeeseseeeeeesaaeeeees 54 I3 SAVING tabula d li uut ede eor p ete uu udi EM 54 PIL WAVING PIOUS ih De REO e NN ua M dm VM M M Mid 54 13 3 Saving textual information eet aet er e a Ed Yao UR RAE Ee TEUER o DAR OE dereud uox 54 gites ueri 3 45 inti 54 igudi eet P TT T 55 Acknowledment S EU LU I Tem 55 1 What is JANIS 1 1 Introduction Nuclear data are fundamental to the development and application of all nuclear sciences and technologies The knowledge of these data is then required for all applications where radioactive mat
28. Importing a whole pointwise library may take about one hour 20 6 2 Load Reload Remove a database The Menu item Database Load is used in order to view the data contained in an existing JANIS database A window similar to the import panel described in the previous section is prompted where the user should input the information that was used to create the database see Figure 13 The Type and JDBC parameters and file root fields enable to specify the type location and connection parameters of the database e Path is used to provide the location of the source data Figure 13 The Database load dialog box X E Load base Type DBC Label Local User Enter JOBC parameters and files root Driver com mckoi database jdbc MDriver URL jdbemckoilocalwiCuuserjanisidatabasesidb_testdbl cont ser janis Password janis Path DaJanisidata JEF _22 B OK Cancel When the database is loaded it appears in the panel Databases 4 on Figure 1 to the bottom left of the screen A right click with the mouse in this panel gives three options e Load equivalent to the Menu item Database Load e Reload refreshes the display of an already loaded database for which the contents have changed e Remove unloads a database If the database loaded is not recognised as being a valid database non existing database or its structure is not valid it is displayed in the
29. JANIS USER S GUIDE January 2004 NUCLEAR ENERGY AGENCY ORGANISATION FOR ECONOMIC CO OPERATION AND DEVELOPMENT TABLE OF CONTENTS What is JANIS eese a ican ee Tc Ee cU Ed Lot 5 DT AMT OCU COON ais uoi eei ine dence otiatal Oboe te E A EEE ERE E 5 L2 JEHat s TOW version 2 0 iti e set ule edi a ce Mam M REV 5 Content of the JANIS CDS iiiieeiesop ite uio iudot2 oe ed e ipod Ree ohas ele qui qo bases eed ee pat obeacaaoeebe qai do pese oo ed E egee 6 Requirements and compatibility 2 0 0 0 ccc ccc ccesseesseeceeeeesaeeeeseceeeeesseaeeeeeeesesssaaeeseeeeeees 7 Install atiol s ne renee ee tr PO ene reer en um UM M ecd E MU 7 vir dg dd LE P o D fs 8 BEroublesho0tlH 2 etre on Dorn e aec aie dun masa uS UEM eo EID MI CE 8 General dedi RUNE ORT NE rP E 9 Ad Xhe Browser WIHdOW ee e tuto NE n aves Nen od edita et us 9 7 2 Navigation tools The Chart of the Nuclides and Nuclide Explorer 9 As Visualisation tools The Renderer 2 on eese onere ie Reset caus iUd duss ood qu RUE eges 12 Data structure JANIS database 1 esses nennen enne nnns 17 8 1 Importing data from a standard format to create a database eese 18 6 2 Load Reload Remove a database essen eene 21 8 3 Viewing data directly from a file esses enne eene nnne nenne 22 JANIS features through examples cccccccccssssssseeccceccaeeesseecccceesaaessseec
30. ZHI ATA FOR JEND TABLE FIG ho u ND I JEM WOK ME c imio 248 Visits SHIRATOs ABE SIG FG CED DEBA CALC hoc 3 7 ND 1 dei JPM WK IE R JAFRCI M 107 199902 3HIRATO DADE CFO DWRA CALC FIG T I plocal jo T HD 1 447 JPH YOK 1506 4 EXFOR 221504004 1889008 T15PTSDA hoa ur ND Laer Kus WUR rT n NEJTRONFIZ 249 1967 T MIKMAJILINA EMULSIONS TOTAL SIGMA hoa uo ND RU KUR aB E B SPN 185 196100 ENGL OF NEJTRONFL 245 hoc 31 7 ND 1 457 RUS KUR 460E 4 EXFORA17B 008 189510 1 FT Si jLucal A T HE 10 7 Bile Rus lL AJT J MBE J3 1 200163 KOMADE E HEW CALC METH GRPH GFE loa xu V ND NOG SwT NEU WE if NUESBAUM JAA NUESBAUM TEP EsANGDIET DE 8 1 8M V hoa 31 7 ND 157 ux ALD ie u JMAB 17 273 I45568 BARRY 14 1 SMa REL U235 SIGF lors t 7 IND oe 1547 UK UK 00 R BINRIE O ET EA 136407 PENDLERURY ALD LHDL DEN 176 loa Cu rr IND hore seh UE UK Pap 3 UMMDL DFM 2138 180383 13PNTS hes xu iF ND 4347 a USA DAV MyE T LOWELL 1344 187667 ING JEEP HOLE STRENGTHS CFOM h sr 3 T ma atr UA nar 777E r TER a eS 1787 SOAS Dn WO SO BO ake BI a Ready The CINDA Search tool is opened via the Menu item Tools Search CINDA The user can then enter information into any or all of the fields shown Drop down menus in many of the fields allow to choose from the list of available parameters For users not familiar with the codes used in CINDA further information on the format of the database can be found via the links provided on the NEA website CINDA search
31. an be selected Finally the path to the directory containing the full EXFOR files can also be specified Figure 46 The File Preferences dialog box General tab iol xl Check for update Check for new versions of Janis at startup Internet bravvzer Command line to launch your favorite web browser C Program FilesAnternet Explorer sexplore exe Filez Root folder containing zipped EXFOR files Path data El 12 2 Options for the display of the Chart of the Nuclides 5 The background colour of the Chart of the Nuclides can be changed using the Chart tab available under the Menu item File Preferences Figure 47 The preferred zoom at start up for the Chart of the Nuclides can also be chosen 52 Figure 47 The File Preferences dialog box Chart tab ol x General Bases Chart Renderer Colors Cursor Zoom C restore previous preferred value Save Cancel 12 35 The Renderer panel options Two default features can be customised see Figure 48 The first option controls the refresh of display when new panes are added The second option concerns the maximum number of elements in a scroll list Figure 48 The File Preferences dialog box Renderer tab lox General Bases Chat Renderer Panes Test panes automatically showed When adding a pane show new panes C don
32. bottom of the list in the Parameter Selection Panel of the reference nuclide for comparison Multiple selection is possible using the Ctrl and Shift keys along with the mouse The user can expand any database to see all existing nuclides and expand further displaying the list of reactions for a single nuclide Data can be added for a single reaction or for all reactions of a specific nuclide Load base Used to add a database not already loaded in JANIS if the data of interest are not already in a loaded database A dialog box opens allowing the user to choose a database for loading Close Closes the dialog box and returns to the Renderer following the addition of data The selected reactions will be added at the bottom of the list and can be displayed as usual Figure 21 The Compare Explorer window IBi xi ROOT Add to list Remote Union F Local Janis Load base Radioactive Data r Interaction Data incident neutr EMDFB 6 6 Umm SB efor ow baze z JEF 2 2 4JEFF 3 0 Cross sections Show datatyperz _ Hes show evaluations Close General infarr Show category ies MT 1 rntota Ley Cross zer __ J MT22 2 20 __ J MT 4 zn Sh id i MT 51 tzr OE MT2323 z n2 J MT253 z n3 __ MT254 z n4 MT255 z nS Show reaction s MT 56 z nB MT25S7 zn __ MT258 z n8 MT 59 z n8 z
33. ceseesaegeseeeseeeesaaas 22 9 1 Cross sections and resonance parameters eese eese nnne eene nnne nenne 22 D Pd vsPOIDDUISO Qld istos pi OV et uai eite esed a ders 22 9 1 2 Weighting of pointwise cross sections eeeeeeeeeeeeeeeeee eene eene 25 Uy OUD WIS QU O EEE diu MEM M MEM LM M MD E 29 9 1 4 Comparison of data from different sources eese eee eene 30 9 5 Comparison with experimental data EXFOR sse 3l IRO COMPUTA OI see eyes apetel i usted ase Lie escas iue teste umero rsen 33 IS OPOSSSSOCHON un CrTi ni N 6 idteseststtetudass tete ado des ex dtu bei castufenud tio N 35 92 Enerey dISIIDUTOHBS casa REL UA EM MEI 36 9 3 Angular distributions esses enne eee eennnn rnnt hes essna ann ntre esse sna nnne nnns 38 9 4 Enereoy dnole distributions ee oce o E Men edam a De TUN Deae Fes 40 10 11 12 13 14 15 16 99 DCCA UG EET 4 UO DCCA CONCHA GAA A e icon SEE idt a MEMM ECE 4 0o Deca PON iacentes sett ddp RRP eee Penne Oat A a bs en me 42 Uo s OPCO AU RR eR See OE ee NOCERE NM 43 Io Fission Vielas is oianeituted syncs M ei iade lauda i etudes au dauiau tien seas iain fu dace mec iunE 44 Br quw mr 46 10 1 Searching Evaluated ENDF data esses eeesesseseeeeee eene ense nnns 46 JU T General BAND ES COU CI satus os aes dte Man o duos ae aan tect tite 46 POTD ROSDROBCOSOOEO eeu qud EM MU 47
34. cross section can be constructed and Doppler broadened at different temperatures So in a typical evaluation file the cross section is set to zero in the resonance range pending its construction by a processing code Apart from the resonance range the cross section is described in a pointwise mode successive values of energy and cross section with an interpolation mode between the points The interpolation mode can be constant linear linear log log lin log or log lin JANIS correctly interprets all these interpolation modes and plots cross sections as described in the evaluation When the cross sections are processed the resonance part is reconstructed and the cross sections are linearised on the whole energy points are added between the initial grid in order to allow an accurate linear 27 Figure 14 Example plot of a pointwise cross section oJ pO Interaction Date incident newron hor Fe56 from IN File Data Hep 4 ke Cross sections it Cnr suction Plotter Cros serdions for FeSi run IEF27 fram fileA ania jie 227 a Log Log Agia WiT 1 nio I barni E x amp rto mine fi Qe to ct Mmmepor EE mire n 00384081 te ee ee yma 724 0547 i More 1 ENDF Cross section Roaclion 4 value TD uv b Weighting on 3 les Lye 0 051 021 0 1 1 M Ln 1000 led Ind lei dn E in at Source Display Fede from JEF 22 MileHAanis bases tase jetz Gener
35. cture on a hard disk or whether he wants to create a permanent database Let us examine the latter case The import function parses the original files and stores the information in a Java relational database management system RDBMS called Mckoi The amount of data stored in the database also depends on the kind of data For CINDA and NUBASE the whole amount of data is stored in the database tables Thus the original data files are not needed after the import stage For other kinds of data namely ENDF and EXFOR only partial information is stored in the database the remaining data is extracted from the original data files whenever needed Figure 11 shows an example of import for ENDF data files The import options are explained in the following starting from the bottom of the panel and going backwards e ENDF is the format of the original files e Inthe field Library the user may give a name of his choice to designate the set of data being imported For instance if the user is importing the whole set of an evaluation data library e g JEF 2 2 then the same label might be used to qualify the library e The Path field should contain a valid path to an existing directory where the database will be created In this example if directory db_ test does not exist under C user janis databases the import will generate a window error message e The User and Password fields provide the means to control the access to the da
36. dd a new evaluation library or a new category of data The procedure is similar to that described above The only restriction is that the source data files of different libraries should have a common root directory e g D janis data JEF 22 D yanis data JEFF 30 In this example the path given in the load dialog box should be D janis data During the Import operation a window see Figure 12 shows the progress status including the file currently being imported material file reaction and also a warning section where messages are printed These warnings are reported in a file date time err created during the import operation The Chart of the Nuclides shown is automatically updated after the successful addition of data for each nuclide and the file date time stats provides complete information on all imported data Figure 12 Status of the Import process Fey Janis Import 79145 mi Import acheived file DxuanisidataUEF 224NTERVEF22N6153 1 material mM part MF 1 rte nnkbsec mem 42Mbtree 198Mbtotal Import acheived Warnings Notes The category of data is automatically determined from the original files Importing a single ENDF material takes between a few seconds and 30 seconds depending on the content of the file 30 seconds is typically the time needed to import pointwise cross sections and energy angle and energy angle distributions for nuclides such as U
37. e can then be refined by adding further parameters in other fields or modified by changing the relevant field parameter as required 10 3 3 Sorting of CINDA retrieval results The retrieved results from a CINDA search can be re ordered by clicking on the required column header e g Date Laboratory etc The default sort order is by element isotope quantity and laboratory Note however that CINDA uses a blocking system for different references relating to the same work which will be lost following a sort e g EXFOR entries are blocked with the relevant publication 10 3 4 Accessing linked papers abstracts Where publishers have made papers abstracts available directly via the WWW the reference code is shown in red in the CINDA results box Double clicking on the reference code will launch the user s Internet browser and attempt to connect to the publisher s site If problems arise in launching the user s Internet browser then one should check the entry under internet browser in the janis settings txt file Under Windows this is stored in the user s folder under the Documents and Settings folder on the system disk A typical complete entry for a Windows machine is shown below internet browser C Program Files Internet Explorer iexplore exe 11 Live update Changes will continue to be made to the software after the publication of official versions A live update option enables the user who has a web connection to au
38. e disks with a FAT16 file system the size can be around 900 Mbytes The choice between these options depends on the available disk space on your computer and on the expected performance The best speed performance is obtained with the last option This increase in size is due to the minimum amount of disk space which is allocated per memory address on large disks 1 GB or so Depending on the actual disk capacity this can be much larger than the size of the actual files and so more disk space is allocated than is actually used 7 To install the software on your hard drive e Create a directory where you want to install JANIS e g C JANIS e Copy the relevant contents of the JANIS CD ROM to this directory i e directories help and groups files janis jar and janis bat or janis sh if you are running on the UNIX system e The databases can eventually be copied to the same drive or to any other drive including those on a network S Starting JANIS On all operating systems the command to run JANIS is java jar Janis jar This command is reproduced in the files janis bat and janis sh with additional options to select the database driver hence to run JANIS e On Windows double click on janis jar or janis bat e On UNIX execute the file janis sh You have now started JANIS Warning Windows only When executing the janis bat file a DOS window appears at start up and remains active while the software is running This windo
39. e information contained in one evaluated file general purpose decay data fission yields or a database specific to one category but with different evaluation sources etc The source files are selected from a local or network drive using the appropriate Browse button see Figure 11 If the files are grouped in a directory and the name of the directory is given the code will automatically select all files contained in that directory File selection options allow multiple selections using the Ctrl and Shift buttons in conjunction with the mouse as in standard Windows selections One file may contain any number of materials ranging from a single material up to a complete ENDF tape containing many hundreds 18 Figure 11 The Tools Import dialog box S x Source files D JanistdataUEFF 22 Browse Vsus o Type JDBC Enter JDBC parameters and files root Driver com mckoi database jdbc MDriver URL Jjdbc mcekailacal C userjanis databasesidh testidb canf LIger anis Password anis Path Cusenjanisidatabasesidb test g Format ENDF Library JEF 2 2 cancel import As explained in the beginning of this section several options are available to convert the original data to a structure readily usable by JANIS The import procedure is slightly different depending on whether the user is simply interested in temporarily viewing the content of a file without storing the resulted stru
40. e only main requirement is to run an operating system OS which has developed a Java Virtual Machine all modern OS have a Java runtime environment The Java Runtime Environment jre version 1 4 or higher is required to run JANIS The minimum required hardware configuration is considered to be e processor 350 MHz e 128 Mbytes of RAM N B the performances depends strongly on the available RAM hence 256 Mbytes or more is preferable e monitor with a resolution of 800 x 600 256 colours e CD ROM drive 4 Installation If you do not have jre version 1 4 then it can be installed from the second CD ROM under directory java where executable files are provided for the installation of Java on Windows Macintosh and LINUX The Java web site http www java sun com provides additional runtimes for free download Other UNIX operating system developers e g Digital IBM have developed their own versions of the Java Runtime Environment Once Java has been installed JANIS can be run directly from the CD ROM or installed on the hard drive Users may choose between e running JANIS directly from the CD ROM no further installation is required e installing the software onto the computer 3 Mbytes required and accessing the databases on the CD ROM or from the web e installing the software on the computer along with one or more databases N B 300 Mbytes are required per database however it should be noted that on PCs using larg
41. e unloaded prior to starting the search 10 1 Searching Evaluated END F data 10 1 1 General ENDF search This tool enables the user to search through the loaded databases for specific information The available search fields are shown Figure 41 This concerns Z A State Datatype and Libraries which corresponds to the those available in the loaded databases followed by the ENDF file MF and reaction MT Note that among the files available in the library only those treated by JANIS are available MF 1 6 8 9 10 31 35 and 40 Consequently a search with MF 13 will lead to a blank result although photon production data might be available in a the selected evaluated nuclear data library Figure 41 The ENDF search dialog box ini xi Criteria PE Material Z A State Reset Datatype Open results Libraries Save results MF MF 6 Energy angle distributions for emitted particles S Print MT hr et zne continuum Close Search history e za Results 267 rows Incident particle Evaluation Material MF MT Local Interaction Data incident neutron ENDFB 5 8 B14 Local Interaction Data incident neutron ENDFB6 8 016 E Local Interaction Data incident neutron ENDFB 6 8 AI27 b Local Interaction Data incident neutron ENDFB 6 8 i28 b Local Interaction Data incident neutron ENDFB 6 8 Si23 b Local Interaction Data incident
42. eraction Data incident neutron 73 JEF22 Qi Energy angle distributions Q Energy distributions Q Angular distributions Qi Cross sections Radioactive Data 73 JEF22 Q Fission yields data Radioactive decay data silver ag N 61 Z 47 A 108 144 pixels The Chart of the Nuclides is not the only available tool for accessing the properties of one nuclide The Nuclide Explorer 3 see Figure 1 provides an alternative navigation tool Expand the directory corresponding to one element and select the desired isotope The Go To option Ctrl G or via the Menu Tools Go To opens a dialog box in which the user can specify one or more parameters symbol A Z name N as shown in Figure 4 There is a full correspondence between the three parts e the content of the selected evaluation e the Chart of the Nuclides displayed e the Nuclide Explorer content The Chart of the Nuclides and Nuclide Explorer are two means for the selection of a nuclide Furthermore once the selection is made with one of these means the second means is automatically updated Double click on the selected nuclide on the Nuclide Explorer tree or on the Chart of the Nuclides to access the complete properties of this nuclide 11 Figure 4 The Go To pop up window ls Janis file l xp1 dat2 users nouri JEFF3RDDT2 Radioactive Data JEF
43. erials and nuclear fuels are present This represents a wide range of applications Nuclear data are thus needed for a variety of users including reactor and fuel cycle physicists engineers biologists and physicians Nuclear data involve radioactive decay properties fission yields and interaction data over a wide energy range and for different projectiles cross sections resonance parameters energy and angular distributions These data are structured into standardised formats to allow their exchange among users and their treatment with specialised computer codes Specific formats exist for experimental data EXFOR evaluated data ENDF ENSDF or processed data PENDF GENDF and relational databases are used to store and disseminate the data However the quantity of data required is so large that it is not always easy for an end user to access the information needed for his specific application Java based Nuclear Information Software JANIS is a display program designed to facilitate the visualisation and manipulation of nuclear data Its objective is to allow its user to access numerical values and graphical representations without prior knowledge of the storage format It offers maximum flexibility for the comparison of different nuclear data sets JANIS is the successor to JEF PC a software developed in the eighties and nineties by the OECD Nuclear Energy Agency the CSNSM Orsay and the University of Birmingham Basically all the featu
44. ers and the data type cross sections angular distributions Figure 44 The EXFOR Search dialog box fe EXFOR Search M Select hasers Bases Search parameters mu Target gc Clase Energy E e Lah rear Lab Year lt Reaction Products Particle Particle i Process Product Branch Parameter considered Modifiers Data types SFI 1 Results Choose parameters and clic Search Work Subwark Lab Year Target Reaction E min E max points 48 10 3 CINDA Search The CINDA Search tool Figure 45 allows the user to perform a comprehensive search of the bibliographic database CINDA Computer Index of Neutron DAta The CINDA database contains single line bibliographic information on neutron induced reaction data as well as some data on spontaneous and gamma ray induced reactions The database is essentially a complete reference list of all neutron induced experiments carried out throughout the world but also includes many theoretical and evaluation references Direct links are provided to the collated experimental data in EXFOR Where possible links are also provided to the original papers abstracts where these have been made available on the World Wide Web by the original publishers Figure 45 CINDA Search dialog box Te CINDA search Element Energy z uma Mni Beret f solope f Wax v Oven res
45. es The General information parameter contains a summary description of the evaluation work source of data analysis method and a dictionary of available files and reactions This is taken directly from the ENDF file MF 1 MT 451 Integral data are also available The utility code INTER 6 12 was used to calculate integral parameters such as thermal and fast neutron averaged cross sections resonance integrals etc from pointwise cross section data The output listings of the INTER code are contained on the JANIS CD ROM for all available libraries and the integral parameters were incorporated in the database during the import procedure The data are thus accessible through JANIS 9 1 Cross sections and resonance parameters Some aspects of cross section display were discussed in the section concerning the Renderer Both pointwise and groupwise cross section data can be displayed and compared Experimental data from the EXFOR database can be plotted numerical values and displayed in text form entire EXFOR work including the comment section Examples will be given here for the three categories of cross sections 9 1 1 Pointwise data Evaluated data files usually give cross sections for different reactions MT in the ENDF format over an energy range which goes from the reaction threshold or 10 eV for reactions with positive Q value In the resonance energy range resonance parameters are usually given from which the
46. f the emitted particle and associated error normalisation factor and associated error 43 9 6 Fission yields Fission yield data depend on the projectile causing the fission e g neutron induced fission its energy and the fissioning system Fission may also occur as a radioactive process 1 e without projectile Consequently fission yield data in JANIS might appear under several categories radioactive data fission yields for spontaneous fission yields interaction data neutron incident The content of the selection list depends on the nature of the nuclide i e whether it is the nuclide undergoing fission parent nuclide or if it is produced by fission product nuclide For parent nuclides there are general information available taken from the section File 1 MT 451 of the evaluation which contains brief documentation of the evaluation and a dictionary with the available reactions independent fission yields and cumulative fission yields The independent fission yield of a particular nuclide and its associated excitation energy state is the proportion of this nuclide directly produced by fission prior to delayed neutron beta decay etc Cumulative yields account for all decay branches after fission including delayed neutron emission Independent and cumulative yields are displayed in both tabular and graphical formats The tabular format gives the yield for all products isotope excitation energy state w
47. f the reaction is selected highlighted but not displayed display option not selected for this reaction the content of fields 2 and 3 may not correspond to the quantity displayed This might be confusing if the user tries to change the values of the incident energy in field 2 while the corresponding reaction is not displayed As the secondary energy distribution depends on the incident particle energy the user might be interested in knowing how the probability of emitting a particle at a certain energy E depends on the incident energy E This can be done by changing the x axis variable to E energy 1 The energy distribution may be represented in the evaluation as the combination of partial energy distributions p E E PUE f E gt E where px is the fractional probability and fk the fractional distribution This is typically the case for energy distributions of reactions with multiple incident particles or for delayed neutron distribution for which the distributions are given for several precursor families Figure 31 gives an example of delayed neutron distribution represented by six fractional distributions one for each precursor family The list of items to be displayed shows several quantities such as Energy differential cross section Energy distribution and six folders corresponding to the six families For each precursor family three rows are available in the reactions list corresponding to the fractional
48. g box m Adjust display properties X Marne C Manual Auto shows errors Errors drawing made two lines f thickness pu 14 The Name field corresponds to the string given in the legend for a curve or the column title for a table This can be automatically inserted by the software or entered manually For data given with error bars cross section uncertainties fission yields the Parameters field controls the display of these error bars The colour of the curve is chosen in the Color field with three choices of colour panels Swatches HSB and RGB The format of the Options Selection Panel 3 Figure 5 depends on the Display Panel 1 Figure 5 and on the data displayed For the example shown in Figure 5 the Plotter field shows the x and y limits etc It can be used to change the scales of the x or y axes linear or logarithmic and to enter new limits for the two scales Other information can be displayed in this panel this will be expanded upon through the examples The More button in the Options Selection Panel allows the more general options of the graph or table to be altered Figure 8 shows the dialog boxes for tabulated data and graphical data Figure 8 Dialog boxes for changing general table top and graph lower properties faq Janis Tabler Strings Title v show title f Auto Janis Plotter Ls Axis Colors Drawing order Strings A axi
49. get Reaction Emin Eme spon Local Janis 0047096 0 E 235 N TOT SIG 235 NTOT SIG Lorie _0276 028 0_ BET Tee quronso poses perses xw 235 N TOT SIG 496e5 f517e7 1680 Local 0935 006 0 ANL 7 235 i N TOT SIG d ET d 20766 1002 005 0 N TOT SIG ia 1108 044 0 N TOT SIG l l 4 AA mmo 0 SRE TATS WW r Once the experimental works are selected they can be added to the reference nuclide s list using the Open Results button Back to the renderer window the experimental data can either be plotted or the EXFOR work displayed as text as shown in Figure 24 This is performed by highlighting the EXFOR work right clicking with the mouse and selecting Display EXFOR File Figure 24 Display of the full EXFOR file SiLocal Janis JEF 2 2 Cross sections U235 File Tools Selected 10016 006 0 C 10016 006 0 Iz cross sections S Tabler 10016 10016001 10 19990617 19990617 17 ENTRY SUBENT BIB INSTITUTE 1USALASZ REFERENCE J NP A 133 108 196908 AUTHOR D M DRAKE TITLE Inelastic neutron scattering and gamma production from fast neutron bombardment of 235U FACILITY VDG 8 MeV Van de Graaff with Mobley bunching INC SOURCE P T T p n used for neutron energy 4 0 and 6 0 MeV D D D d n used for neutron energy 7 5 MeV Cross section DETECTOR NAICR NaI Tl detector surrounded by NaI Tl anti coincidence annulus and a large collimator shield
50. h which the search is performed the nuclides to be included in the search etc see Figure 42 Figure 42 The Resonances search dialog box fs Resonances search OF E E Save results Close E acl ety HERE o coe C value Evaluations haterials Isotopes Results Choose E datasetis materialis and isotopers and clic Search Evaluation Material E Search resonances for 10 1 3 Decay data search This option allows to search for radioactive nuclides which satisfy specified decay and spectral properties The search can be done by specifying the half life range and or the energies and intensities for alpha and photon lines see Figure 43 The results are given in a tabular format that can be saved to a file or sorted according to the output columns 47 Figure 43 The decay data search dialog box fe Line Search Search lines for Search Reset _ TEN Save results f e E f EF in ev Close 0 0 intensity lt f o normalized half life f minute Time Alpha lines ensity and clic Search Intensity Type Material Half Life EXFOR Search This tool Figure 44 allows the user to perform a comprehensive search through the experimental data EXFOR Search parameters include the target nuclide the energy range the laboratory and the year the experiment was performed the reaction specifi
51. hile the graphical representation gives the fission yield as a function of the chain mass sum of yields for a given mass number A Fission yields depend on the energy of the neutron causing fission Independent and cumulative yields are thus given for typical values of the neutron spectrum thermal neutron induced fast neutron induced and high energy neutron induced fission An example of an independent fission yields graph is shown in Figure 38 Figure 38 Example of independent fission yields graph for a parent nuclide SiLocal JEF 2 2 Fission yields data U235 l 0 x File Tools Selected Lx Fission yields E Taber Plotter i ion data Parent independant fission yields for U235 from JEF 2 2 from Local ES Lin Y ue Log Fiss Thermal 0 0253eV Xmin o1 9999999999999996 Fast 400keV Kmax 1181 8 High 14MeV Y minz 5 9771 1118038046E 11 Ymax o 931 9845928232484 More ay M EHH Parent independant fission yields 5 EHA Fast 400keV es v PIT r Chain mode same A PT L e Charge mode same Z PT High 14Me v T Iv PIT L Chain mode same A PT L e Charge mode same Z PT x 44 For product nuclides fission products the production yield for different fissioning systems can also be displayed Figure 39 when a specific product is selected from the chart of nuclides This information is not initially contained in the evaluation but JANIS construct
52. le distribution _ Product yield e iv f Pm El 1 Selection of the x axis variable u or 2 List of incident energy points E at which the energy angle distribution is tabulated 3 Choice of the u or E values 4 Method used in the evaluation for the representation of the energy angular distribution 5 Frame of reference for the variables 9 5 Decay data All the information contained in the evaluation files ENDF format is available through JANIS As for the other categories of data the display 1s composed of plots e g spectra text fields decay general data general information and tabular formats spectra The General information parameter contains a summary description of the evaluation work source of data analysis method and a dictionary of available files and reactions This is taken directly from the ENDF file MF 1 MT 451 9 5 1 Decay general data The Decay general data is a summary of important decay properties of the nuclide It contains the mass of the nuclide its excitation energy the spin and parity the half life the mean decay energies and decay modes The mean decay energies are given for three families of emitted particles e all electron related radiation such as beta betat conversion electrons Auger etc e all electromagnetic radiation such as gamma rays X rays and annihilation radiation e all heavy charged particles and delayed neutrons alpha protons fissio
53. n mode same A from 2 2 from Local 0 1 Pu239 Mass of product 90 0 Xminz 53 2 U235 Mass of product 90 0 Xmax jos Ymin o 0030 Ymax fo More Move Zoom Mass of product Display 30 0 EE Char ge of product ACC Sorc Settings Display EH Fission data Al 9 Parent cumulative fission yields L Fast 400keV EHH Thermal 0 0253e V Chain mode same 4 e Charge mode same Z HE Parent independant fission yields 45 10 The Search tool Three search capabilities are included in JANIS They concern general ENDF reaction searches resonance parameters decay data experimental data EXFOR and bibliographical references CINDA The search tool can be accessed from the menu option Tools Search in the Renderer by clicking on the right button of the mouse In both cases the search panels are similar However when accessing the search tool by right clicking on the mouse some search fields are automatically filled e g when selecting a specific reaction in the Renderer the EXFOR search will be launched with the corresponding target and reaction fields The search is performed through all the loaded databases Consequently multiple results might be obtained when information is contained in several loaded databases This occurs in particular with the local and remote databases If the user wants to restrict the search to a specific database the other databases should b
54. n products For each decay mode the corresponding Q value branching ratio and nuclide produced are given 41 9 5 2 Decay path The decay path also called the decay chain shows the path followed by a particular nuclide toward the line of stability see Figures 36 and 37 The decay chain is constructed from the information available in the library half life decay modes branching ratios The decay path is produced in both tabular Figure 36 and graphical Figure 37 formats The nuclide under study is represented with its symbol in red and is located at the top right of the screen The end of the chain has a bold frame when it is identified as a stable nuclide Figure 36 Example of a decay path in tabular format Euras WE Decay path tor uzas Tabler cay path for U235 for U235 from jef22 From file H jania rcepository databaarca Ebase jef22 M m z Parani Detay data itar moa Product Data data Half Lifi Loca data Branch ng Half L t amor Decay data Branching error pa OM Alpha WF Fa POECIE 1 5 QDO116e5 yr ihaj Data Paz 1 06333 d n Ir B Fardi Alpha Wall 3 2 T608B4 yr n 110 0048 yr dic dT Bata LUFET 11 2 7347 yr Spire 1 08575 d Lor Ft Alpha Frid I1 2 7347 yr EEEL at 1 08575 d STET lana Ra hg 1866 d 1 14 4 min Brava H ts Ra 11 8 min Guje ae H TFrI33 Alpha Ar 1 r1 8 min Bei ITE H BHa273 apra Fn219 naa f 8 min H TAE CES Fn219 as Bie bs n 10
55. nances csv EUM Cancel Export All tables can be sorted according to one of its columns The default sort is by ascending order of the parameter in the first column Click on the cell corresponding to the name of another parameter to sort the table accordingly An important component of any plotting package is its zoom capability JANIS offers different ways of zooming e With the mouse While maintaining the mouse button pressed draw a rectangle in the plot area The plotter will use the co ordinates of the rectangle corners to calculate Xmin Xmax Vmin and ymax A click on the right mouse button will cause the plotter to go back to the previous zoom level e By specifying the values of xmin Xmax Vmin and Vmax in the Parameter Selection Panel A right click On Xmin Xmax Vmin OF Ymax Will return the plot to the previous zoom level 16 8 Data structure JANIS database JANIS 2 0 can access the data in various ways depending on how it is structured The main options are listed below e Access to data supplied with the JANIS CD ROMs This will be referred to as Local janis or local CINDA e Access to JANIS data available on the NEA server This will be referred to as Remote Union e Access to users data contained in text files typically a single or a set of ENDF files The data contained in the JANIS CD ROMs is basically split into two parts Directory data contains several categories of data s
56. neutron ENDFB 5 8 Si30 b Local Interaction Data incident neutron ENDFB 6 8 CI35 b BM 5 5 iz 5 5 E Local Interaction Data incident neutron ENDFB 6 8 CrS Local Interaction Data incident neutron ENDFB 6 8 Cr52 Local Interaction Data incident neutron ENMDFB 6 8 Cr53 Local Interaction Data incident neutron ENDFB 6 8 Cr54 Local Interaction Data incident neutron ENDFB 5 8 Local __ Interaction Data incident neutron ENDFB 6 8 Fe54 Local Interaction Data incident neutron ENDFB 6 8 Fe56 Once the search is performed the list of results can be saved on a file button Save results Specific results corresponding to one or several rows can be displayed The user must first select the desired rows and press the Open results button 46 10 1 2 Resonance search This tool allows nuclides to be found which contain neutron induced cross section resonances in a specified energy range The tool can help the detection of the contribution from specific nuclides e g impurities when analysing experimental data The search is made through the processing of resonance parameters given in the original ENDF data File 2 Note that if a nuclide is described in the evaluation using pointwise cross sections without resonance parameters its resonance structure will not be detected through this search tool Options are available to choose the evaluation throug
57. now accesses directly to the text files eventually zipped in order to reduce the required storage and the table of contents of these files the ENDF dictionary for instance is contained in a relational database This enables both quick access to the data and a better separation between the methods classes and the data itself Access to the full EXFOR files The first version of JANIS accessed the EXFOR data through the computational files i e only numerical experimental data was accessible In the new version the user can access the full EXFOR work including the comment section Access to the CINDA database and link between CINDA and EXFOR Basically the features of CD CINDA were implemented in JANIS and a link to the EXFOR works was added Access to NUBASE data Generalisation of the computational features available in conjunction with interaction data these features such as linear combinations ratios of data were restricted to cross section data It is now possible to perform more advanced combinations such as a product of cross sections with energy and angular distribution Access to centralised data available on the NEA server through the Java servlet technology 2 Content of the JANIS CDs The Java software and a selection of recent nuclear data were packaged to produce the new release JANIS 2 0 This selection of data includes evaluated nuclear data libraries processed at 300 K ENDF B VI 8 JEF 2 2 JEFF 3 0 JENDL
58. on contained in the evaluation displayed for this reaction This may cause confusion when a user tries to change this information for a reaction which is not displayed As the angular distribution depends on the incident particle energy the user can plot how the probability of emitting a particle at a certain cosine angle depends on the incident particle energy E This can be done by changing the x axis variable to E energy 1 It is also possible to plot differential cross sections When a reaction has an anisotropy law in the evaluation the angular distribution is not isotropic JANIS constructs the product of the angular distribution and the cross section It is thus possible to plot the cross section as a function of energy for different angles as shown in Figure 34 39 Figure 34 Example of differential cross sections ETT JEF 2 2 Angular distributions Pu239 File Tools Selected E Angular distributions E Angular differential cross section Plotter MT 51 z n1 Angular differential cross section for Pu239 from JEF 2 2 from Local x Log Y Log id coe a Eu mt os of angle 0 ome Cos of angle 1 0 xsqt X Xmin 7832 91 3 Xmax por Y minz o 00351 35883093154333 Ymax 0 228461607835347 More Lowe zm Move Zoom x Eneray m Source MT 37 z 4n Angular distribution MT 38 n 3nf fourth chance Angular distribution EI 23 MT 51 zn Angular differential cr
59. on tools The Chart of the Nuclides and Nuclide Explorer Different navigation tools are available to select a particular nuclide for accessing its nuclear properties Position the cursor left mouse button click on one area of the chart and move the zoom scroll bar 6 to the right or choose another value for the zoom level 5 A zoom of the chart for the Z range 45 48 and the A range 105 108 is shown in Figure 2 The zoom level can be increased further Depending on the category of data selected some nuclear properties are displayed for each nuclide here for radioactive decay data the half life decay modes and branching ratios are shown Figure 2 Details of the Chart of the Nuclides showing radioactive nuclides properties i Janis file I xp1 dat2 users noun JEFF3RDDT 27 Radioactive Data JEFF3T2 Radioactive decay data File Database Tools Chart Help BRANCHING H IM Ec Betar v v iv rz v ic EC Betat Beta Alvha IT SF D table iv INACTIVE Materials Agio3 Agt03m Q Agio4 Agt04m Agi05 d Q gt05m Q Agi06 gt 5m Q Agt07 Agt07m emn rm 4 gt Databases E filevixp1 dat2 usersinouri 3 Radioactive Data E e JEFF3T2 0 EIE MER gt A Silver Ag N 61 Z 4 1 2 1 Stable ETFI 17 Ag 62 l 20A Pd i
60. oss section L e Angular distribution HA MT 52 z n2 i MT 53 z n3 9 4 Energy angle distributions The distribution in energy and angle of the reaction products is described in File 6 of the ENDF file It provides an alternative and more accurate representation of the reaction products characteristics compared to the separate representations using energy distribution File 5 and angular distribution File 4 The double differential cross section o hu E E is related to the energy angle distribution fiu E E by o p E E o E y E f u E E 2n where is the incident energy the energy of the product emitted with cosine u o is the reaction cross section and yi the product yield The energy angle distribution and the yield can be displayed by JANIS see Figure 35 Different representations for the energy angle distributions are used in the evaluations shown in the field Representation at the bottom of the Parameter Selection Panel The incident energy is always given in the laboratory system while secondary energy and angle may be given in the centre of mass or laboratory systems this information is also given in the Parameter Selection Panel The energy angle distribution has three independent variables which can be plotted along the x axis As JANIS can only plot one at a time the distribution is plotted as a function of one variable whilst fixing the other two The varying
61. oup type uniform in lag Uniform in lag Initial value File defined Subdivision in groupsidecade Group structure Two options are available e Uniform in log In which the user specifies the minimum energy limit and the number of groups per decade e File defined Allows the user to enter a multi group energy structure defined in a text file The user needs to specify the location of a file extension gst for instance where the first line is of the form neutron group structure anl 27 group The string anl 27 group located after six dots will be used to identify the group structure The remaining lines of the file have the following format Ng Emin Emax where Ng is an integer group number not used by JANIS and Emin and Emax are the energy limits of the groups Examples of group structures are available in the directory Group of the JANIS installation Note that no blank lines are allowed after the one describing the last group Spectrum definition The second tab of the Weighting dialog box see Figure 19 enables the definition of the weighting flux spectrum 26 Figure 19 The Weighting dialog box Spectrum tab fs Weighting Oop x Group Spectrum Spectrum type General spectrum Constant spectrum Emaxth f get spectrum heta th 0 025 in ev ANR spectrum Emaxepi 1 ORE STET T heta fis i 400000 in ev Emax fis s000000
62. page at http www nea fr cinda cindaora cgi where links are provided to the various dictionaries of journal codes etc 10 3 1 CINDA Search dialog box options The various functions of the CINDA Search facility are accessed by clicking on the available buttons at the right hand side of the dialog box as described below e Search Launches the database search once the required parameters for the different fields have been selected entered e Reset Resets all fields to blank 49 e Open results After selecting a number of EXFOR lines this button opens a Renderer window containing the data selected ready for plotting Multiple lines are selected using the Shift and or Ctrl keys along with mouse clicks as usual e Save results Allows the retrieved CINDA lines to be saved to a file for use in different software e g the data can be exported into a Comma Separated File CSV for later use in a spreadsheet word processor Note that the file name and column separator are specified by the user in the Export pop up dialog box which appears e Print Allows the retrieved CINDA lines to be printed e Close Closes the CINDA search dialog box e A useful tip Use key F5 to reset a single field composed of a drop down menu 10 3 2 The CINDA Search history box Previous searches performed on the CINDA database can be recalled by selecting them from the drop down list Thes
63. parameter 1s selected in the X list see Figure 35 field 1 The choices are Energy incident Secondary energy and Cosine of the angle The values of the other two parameters for example E and p if the variable is are fixed using fields 2 and 3 The general layout and the functionalities of the panel are similar to the ones studied in the previous sections for Energy distribution and Angular distributions 40 Figure 35 Example of an energy angle distribution IsiLocal ENDFB 6 8 Energy angle distributions Fe56 File Tools Selected E Energy Angle distributions kX Product yields Tabler Plotter 1 ne z 2n ENDF energy angle distribution Product n ZAP 1 0 x Log 7 Me Lin Lo LIP 0 a ele angle distribution for Fe56 from ENDFB 6 8 from Local Pind Cos of angle 0 0 Xmin n o Xmax 8775000 0 Ymin 42 746538749999994E 9 Ymaxe fi 59182825E 7 More Move Zoom X secondary energy 1 F Energy angle distribution Representation continuum energy angle l 3 10 100 1000 led le le E Legendre in eV Frame of reference e Display ai EAB E EHT MT 5 z anything ENDF energy angle distribution 3 MT 16 z 2n ENDF energy angle distribution r HT Product Fe55 ZAP 28055 0 LIP 0 E I HT Product Photon ZAP 0 0 LIP 0 a c F EEH I 3 Product n Z4P 1 0 LIP 0 Eneray ana
64. probability the delayed neutron energy distribution and the product of the fractional probability and the energy distribution Figure 31 shows the plot of delayed neutron energy distribution for two precursor families Figure 31 Example of a delayed neutron energy distribution represented by six fractional distributions s JEF 2 2 Energy distributions U235 lol x Fie Tools Selected E Energy distributions E Platter 26 rey 1 Energy distribution for U235 from JEF 2 2 from Local Janis x Loo E f Lin hu pi er A oe DE 5 Xmn oo Xmax 90000 0 Ymin 5 59583E 31 Ymax 2 a5097E 6 More Move Zoom X secondary energy b ne ere iY Sets HSI MT 455 z nubar d 5i aj e Energy differential cross section P Energy distributio P EHS component He m Energy distribution Es v P Fractionnal probability PT Partial distrib x frac prob 0 P ES component 32 5 si 9 Energy distribution SY n Fractionnal probability PT Q Partial distrib x frac prob 1 P 5 23 component 3 5 a 37 The partial energy distributions might be combined according to the formula above to form the overall delayed neutron energy distribution JANIS provides under each component the fraction of delayed neutrons in the family multiplied by the energy distribution of the family It also provides the summation of these weighted energy di
65. qt X Xmin f 06 5 Xmax Boer t Ymin fr a857 Ymax es 031 94 More Move Zoom Cross section Reaction value le 5 le 4 0 001 0 01 0 1 1 10 100 1000 le4 le5 le6 le E fn e C O OOO a oen CA Local Interaction Data incident neutron JEF 2 2 Cross sections F19 Lg EH General informations ra ri m1 ZI Integral data L e MT 451 z Heading or title information MT 1 n total Cross section T iv P T MT 2 z z0 elastic scattering Cross section Compare PT MT 4 zn Cross section Searches gt PT MT 16 z 2n Cross section Computations gt PT go iio avec anil Weighting E f 28 z np Cross section 1 MT 51 z n1 Cross section 2 Display EXFOR file PT MT 52 z n2 Cross section Unselect all MPT MT 53 z n3 Cross section Settings PT Sd meum z n4 Cross section Show horizontal lines E j 1 The display panel 2 The parameter selection panel 3 The options selection panel 4 The Menu bar There are three different ways of representing the data e P for graphical plots cross sections energy and angular distributions fission yields decay spectra e T for tabular data resonance parameters x y representation of cross sections or discrete decay spectra e I for information text decay data constants general information
66. res available under JEF PC were reproduced cross section display in pointwise and groupwise format decay data and fission yield display and several others were added resonance parameters energy and angle distributions cross section uncertainties Additionally all the former limitations were removed number of data sets displayed etc and the new software is more flexible and ergonomic JANIS users can view their own evaluated or processed data starting from any ENDF formatted file or from GENDF libraries JANIS runs on almost all computer operating systems UNIX Windows Macintosh 1 2 What s new in version 2 0 The first version of JANIS 1 0 released in October 2001 was used by more than 700 users around the world Important feedback was accumulated and improvements were added to the software These improvements targeted the following areas e Management of the data through a relational database One of the limitations of JANIS 1 0 was its structure of data The basic data contained in the original ENDF and EXFOR files had to be converted into an internal structure serialised Java objects This option allowed a very quick access to the data However the data could not be easily updated and the structure was highly dependent on the classes used to generate the data In particular the structure of data became obsolete when these classes were updated To solve this problem a new strategy was implemented in JANIS 2 0 The software
67. rol the zoom level of the graph 9 5 3 Spectral data Discrete and or continuous spectra are given in the evaluated file for each type of emitted particle Discrete spectra Discrete spectra are represented in JANIS using tabular and graphical formats The tabular format gives the following information e energy of the emitted particle and the corresponding uncertainty e relative and absolute line intensities and their associated errors e for gamma and X ray spectra internal conversion total K shell and L shell coefficients and internal pair formation coefficients are also given for each line e for electron capture and or positron spectra the type of transition is given for each line allowed first or second forbidden unique or non unique as well as the positron intensity The discrete spectrum plot gives the absolute line intensity ordinate and the energy of emitted particle abscissa The right hand panel provides complementary information such as e the number of lines e the sum of intensities calculated e the average decay energy and associated error e the normalisation factor ratio between the absolute and relative intensities Continuous spectra Continuous spectra are given in plot format The spectra are given piece wise in the evaluations and are reconstructed by JANIS using the interpolation laws given in the evaluation Additional information is given in the right hand panel average energy o
68. s v draw vertical grid lines v draw axis draw axis at 0 position if possible v draw horizontal grid lines C draw axis at bottom OK Apply Save as defaults Close 15 Under the Strings tab common to both the title of the table or graph can be specified This can be constructed automatically by JANIS as a combination of strings giving the type of data the nuclide the evaluation name and the location Alternatively manual specification of the table and graph titles can be entered in the free text box when the Manual option is selected No title is displayed when the show title checkbox is not selected The settings panel for a graph contains three other tabs e The Axis tab controls the drawing of x and y axes and gridlines e The Colors tab allows colours for different areas to be altered e The Drawing order tab controls the drawing orders foreground background for multiple curve graphs Saving tabulated data Tables can be saved to disk using the option File Save on the Menu bar 4 Figure 5 The dialog window shown in Figure 9 appears where one can specify the file name and location Browse button and other options including the choice of column separator The default column separator is a comma Figure 9 Dialog box for File Export fas Janis Export Ea Cay file print headers W use a special column separator Output file n name feso
69. s it from the parents fission yield information The information is also available as independent or cumulative yields and at typical energies of the neutron inducing fission Figure 39 Example of fission yield graph for a product nuclide j Local JEF 2 2 Fission yields data Sm149 15 x File Tools Selected kx Fission yields SE Tabler Plotter eroi pur dr rms cri cel es e C EE Xmin 232 2 Xmax pas 8 Yrnin 0 0036378999999999995 Ymax o 0263434 Move Zoom Thermal 0 0253ewv Mass of parent AW ce Settings bie 3A Local Interaction Data incident neutron JEF 2 2 Fission yields data Sm149 Fission data 51 3 73 Product cumulative fission yields r e Fast 400keV Det He High 14MeV Pr pt I fau Spontaneous Thermal 0 0253e V T EHT Product independant fission yields It is also possible to display the fission yields for a set of nuclides with similar properties same mass number chain mode or same charge number charge mode The graph in Figure 40 shows a comparison between U and Pu fission yields for fission products of mass 90 Figure 40 Comparison of yields for products of a given mass sj Local JEF 2 2 Fission yields data U235 loj x Fie Tools Selected Lx Fission yields E Tabler LY Fission yields rabie Plotter Fission data Parent cumulative fission yields Thermal X Li Y y Log Md Chai
70. s section can be re used to build other equations Also the Computation and Compare options can be combined to produce e macroscopic cross sections for a mixture of nuclides e ratio of cross sections of different isotopes 9 1 7 Cross section uncertainties Experimental data are always given with associated uncertainties Evaluated data however may or may not include covariance data The current version of JANIS uses the covariance data on neutron cross section contained in File 33 to derive cross section uncertainties Note however that since the uncertainties are displayed for pointwise cross sections the component of the uncertainty related to average cross sections LB 8 in ENDF File 33 is not taken into account When uncertainties are available the cross section is displayed with error bars The user may choose not to display the error bars for a specific curve This is done using the settings see 2 in Figure 14 of the appropriate curve In the dialog box shown in Figure 29 the Parameters field gives the choice of showing or not the error bars and the preferred mode of uncertainty representation Figure 29 Definition of plot properties fas Adjust display properties Plot properties Table properties Name C Manual I show Y errors Errors drawing mode two lines v thickness Calor Swatches HSE RGE Recent EEEL BERETT aa Pt tt Pt Tt
71. s sections data of Files 3 2 1 and 33 in the ENDF format Figure 10 displays the structure as seen by a file system explorer Figure 10 Data structure of a typical JANIS database Databases Gl Radioactive Data aj EC 3 Interaction Data incident neutron E 7 ENDFB 6 8 BI Exfor DHCQUEF 2 2 EHE JEFF 3 0 00 B JENDL 3 3 J Interaction Data incident proton LJ Interaction Data incident gamma Ee Interaction Data incident alpha Ee Interaction Data incident deuteron J Interaction Data incident triton lL Interaction Data incident HE3 ED Interaction Data incident electron IL C Nuclear properties x The Chart of the Nuclides and the Nuclide Explorer are dynamically constructed from the content of the selected category of data A number of operations are possible with regard to the database as described in the following sections 8 1 Importing data from a standard format to create a database The Menu option Tools Import allows the conversion of data from one of the original formats to the JANIS database format The original formats supported are the ENDF format including the PENDF format and hybrid ENDF PENDF the GENDF format as prepared by NJOY the computational format of EXFOR used at the NEA and NUBASE A database may contain different categories of data and or many evaluations For instance a user may create a database from all th
72. stributions row entitled Energy distribution and located just above the folder of the first partial spectrum component 1 6 Figure 32 shows the combined distribution and the contribution of each group to the overall distribution Figure 32 Example of a multiple component energy distribution Local Janis JEF 2 2 Energy distributions U235 File Tools Selected L COMPUTED Plotter adhe nubar d for U235 from JEF 2 2 from Local Janis x Log E Y Log Y Ene ion sa fies Ebr Bb o E E x sato component 2 6 aed DE 5 component 3 6 Enerzy 1 DE 5 Xmin o o component 4 6 Energy 1 0E 5 cofnponent 85 6 Energy 1 DE 5 Xmax s000000 0 Ymin fi DE 10 Ymax fi 3800848798116E 5 More Move Zoom Me Secondary energy v Energy distribution Representation General evaporation spectrum EHT MT 18 z fission total UE EY MT 455 z nubar d a Energy differential cross section P Q Energy distribution es v P EHS component 11 5 zi Energy distribution P Fractionnal probability PT Partial distrib x frac prob 0 Es v P EHEJ component 2 6 si Energy distribution P L4 Fractionnal probability PT Partial distrib x frac prob 1 N v P x 9 3 Angular distributions Angular distributions of secondary particles are given in File 4 of the ENDF format as fu E where u is the cosine of the angle between
73. t change visible pane Variable editors J Show at most f O00 Valles Lise this to decrease memory usage Save Cancel 53 13 Saving the displayed data to the disk The user may wish to use the result of the JANIS display outside the software All forms of output can be saved to the disk The format of the output file depends on the type of information displayed 13 1 Saving tabular data Tabular data generated by JANIS can be saved to disk while maintaining the column format When the option File Save is selected while the Renderer shows tabular data a pop up window is displayed Figure 49 It allows the user to select the output file name and the column separator i e the character to be inserted between the contents of two successive cells The default column separator is a tab Figure 49 The Janis Export pop up window SRELE Export xc C Sv file Iv print headers use a special column separator f Output file n nares fable csv Browse Cancel Export 13 2 Saving plots Plots generated by JANIS can also be saved to disk using the following formats ps postscript eps encapsulated postscript and png Portable Network Graphics the latter being ideal for use in many Microsoft Windows applications 13 3 Saving textual information Textual information can also be saved to disk The formats available for the output file are txt unformatted text and rtf rich text format 14
74. tabase The default value for both fields is janis e The URL field is composed of the name of the driver jdbc mckoi local and the absolute path to the database configuration file which will be created by the import function In this example the absolute path is C user janis databases db_test db conf Note that this path is the same as the one provided in the Path field except that two forward slashes are added in the beginning and the forward slash is used in stead of the backward slash db conf is the file name of the database configuration file and the user might make a different choice 19 e The two fields Driver and Type describe the interface between the Java software and the relational database The old structure of data used in JANIS 1 0 is one of the choices available in the field Type The recommended options are shown in Figure 11 e The remaining field Source files allows the user to select the directory where the original data files are contained In this example we selected directory JEF 22 contained in the CD ROM under directory data This directory contains two sub folders HENDF and INTER JANIS will automatically import all information contained in these two sub folders and create a database with multiple categories of data according to the content of the files The Tools Import option can also be used to update an existing database a
75. ter Cross seciions far 1238 from Gend jeft ran filez E iJanis Aladi s I og Log ia Denk Indirets diesen fm Barns techno 50 bars Tw sageiixy HOT biriigi bara Mmirr 1 0E 5 EE S7 m r1 wwehbon mac 1 000 0 I Morn IT T 1 T 1 1 1 1 1 7 la 5 lid 3 0L b bl N 1 wW 1m bat lik ni le he F wah Goure semngs Dupuy Samin amp D D bens MT lt in seal L FIM Mi a C em MT 10 fasio F MT 102 i E grin Es Crim Sigma VO cams MT 1 on Aata CPM Mizi gun C Pm MT 10 aasian C Fm 19 L Pm is Crim igma0 800 0 b MTe1 n betar Crim Mi 2 C Fim WT 10 iz asian C Fim iz 29 9 1 4 Comparison of data from different sources JANIS offers a flexible means for comparing data cross sections or any other parameters Starting from one nuclide reference nuclide the user can compare with another nuclide contained in the same library or with a nuclide from a different database There are two ways to access the Compare feature One is through the Menu option Tools Compare and the other one is by selecting a reaction and right clicking with the mouse and selecting Compare Either action will open a dialog window called Compare Explorer see Figure 21 showing the list of databases already loaded in JANIS and three buttons Add to list Adds the selected component s to the
76. tomatically check for updates and download the necessary files from the NEA web site However as this option replaces the old versions 50 of the files they should not have a read only status Thus running this option requires the file Janis jar to be installed on a hard drive with a write permission This option is not activated by default To run the live update at each start up or at regular time intervals see the next section for details To run the live update instantaneously choose the menu option File Check update Each time a new version of the software is available on the NEA web site the program downloads it and replaces the old version The old version 1s not deleted but rather renamed The user is advised to clean up his software directory after an update by deleting the file named JANIS jar bckDate and time 12 Customisation The default values of many options can be changed in order to better satisfy the user s preferences This is done through the Menu item File Preferences which contains several tabs as described in the following sections Any change of these options should be confirmed by pressing the button Save followed by OR 12 1 General The first tab General enables to select several options see Figure 46 The Live Update option described in the previous paragraph can automatically be launched at start up if the corresponding box is checked The default internet browser c
77. u bar Figure 26 Selection of the level at which an operation is saved x 9 Please select the branch were vou want bo insert the result node This choice impactera la reutilisabilit de la Formule Local Janis Interaction Data incident neutron JEF 2 2 Cross sections U235 MT218 z fission total Cross section Local Janis Interaction Data incident neutron JEF 2 2 Cross sections U235 MT 452 z nubar T Neutron production m S Local Janis Interaction Data incident neutron JEF 2 2 Cross sections U235 MT218 z fission total Cross section lacal danis Interactinnm Data rincident neimtenm FF 7 Cros gectinnz DPSS MT21TI2 C v radiative canture Cries zRectinn 33 Suppose the result was saved under the fission cross section to apply the equation to another nuclide select its fission cross section right click with the mouse or choose the Menu option Tools Computation and select the label of the equation here Eta This causes the operation to be performed and added to the reaction list under the appropriate anchor see Figure 27 The operation is saved after quitting the software and can be accessed when JANIS is launched later Figure 27 Application of a pre defined operation TET Janis JEF 2 2 Cross sections Pu239 El x File Tools Selected bk COMPUTED Plotter MT 18 z fission total Eta for Pu239 from JEF 2
78. uch as evaluation libraries EXFOR and NUBASE files The basic data is contained in separate text files which can be compressed to reduce the storage size Typically a text file contains an ENDF material or a collection of EXFOR works for a given target nuclide Directory databases contain one or several relational databases specially designed to either include the whole content of bibliographical data CINDA or to provide the JANIS software with dictionaries that enables rapid access to the text files contained in the data directory The databases are constructed with JANIS see the import option in Section 8 1 In principle these databases are connected when the software is launched Two CD ROMs were necessary to include all data The first CD ROM contains a collection of evaluated data files NUBASE data and experimental data EXFOR The second CD ROM contains the bibliographical CINDA data and a second copy of the EXFOR data To access the data contained in the Remote NEA database an Internet connection is required Furthermore since a large quantity of information is transferred a high speed Internet connection is preferable JANIS enables an automatic connection to the Remote Union This is performed using the servlet technology Thus in principle one can access the data simply by launching the JANIS jar file However depending on the configuration of the firewalls in the users computer environment this option might not
79. ults Compound z Documentatii Quanti 5 S PA t nai Tree Print Goar Reference l Lab Date Range TMD TTD ps vaa Gipsa Work Tyne aD Author End Dine Search history Resulf amp 41 row Jearth Glemant KL Quanti Energy uem County Reterence Datumentsion Data Humb 2 Raf Vol Pag a eem flocar T H NDSWIG HA V E uL OMIKHAILUNA CAS MB focal ub 14 iE D jE BA os 40 196705 VALKCMICG DIFF GS AT THE TMCH Je amp DEG Local L IND E zm EL AREE 4 EXFOR 30185 005 197711 DIFF CROSS SECTIONAT 5 DEG C M Local 3 u HE Last SRO RBZ ATOE J BPA 4D J12 Tu E MILIAHIC AHG DIST TO GHO ST CFD TH Boa u if ND Laer CRO RBZ am U MBIA 16 110 VIT TT MILIANIC DWBA CALC ANGDEST ST hoc 34 7 Inti cho RBT 4E A INDC BECH 147158 P156 SMALL REPORT NO lors 1t 7 HD E cro RI 0G 4 EXFOR DOIN 002 1971037 PTS SIAN hoa uF IND Laer CRO REZ am U MPA IIa 109 10007 MILJANIC REL SCAT SIOG AT 180 DEO les ru ND T HUN DES Wey FEA 7493 185312 CSIKAI BIG HL COMP FOR N ACTN ANAL hoa 31 7 ND ide HUM IKFI Hc U JRC 7 365 19106 MAGY SIGMA AND BETAKE GIVEN floral su T HE 1 527 IHG PAT 4700 J re 3585 lari 30 ARG gio FOR LGA NF UTH OH hoa uo ND 1 557 IND PAT am C SBOMBAY 2 208 VITRY2 GARG WRONG VAL EUPEREEDED BY IPA 17 hor 3 7 ND IND PAT SE l ExFORr3 6 003 I 3 WEB HTED EUM Hi PL TUN E hors i 7 HD 1447 ING BAH IC J MUC 238112 19650g CHATTERJEE TABLE WITH REFS Local 3 Ll JT HD DER Lie JPH JAE 1400 R JAEFSE M 04 204 ud
80. w should not be closed otherwise the software will terminate 6 Troubleshooting The execution files bat or sh assume that the Java command is in the users command path If this is not the case the program will not run Hence the Java command must be added to this path or alternatively you may change the execution command to specify the complete path to your Java executable For instance if Java 1s installed in the directory E Mycomputer Program Files JavaSoft jre1 4 bin then this path should be added with double quotes before the first word java in the relevant execution file JANIS runs better with the Java runtime environment version 1 4 or higher If you are using jre 1 2 you may experience some problems with the size of the windows and panels To check the Java version installed on your computer type the command java version in a DOS UNIX command window 7 General overview 7 1 The Browser window If the program has correctly started then the first window to appear the Browser should have the components shown in Figure 1 Figure 1 The Browser window upon starting JANIS fej Janis file 7H janis bases base_jef22 Radioactive Data JEF22 Radioactive decay data File Database Tools Chart Help 1 BRANCHING 0 45 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 105 110 115 120 125 130 135 140 45 150 EC Betat 104 Beta Aloha m 2 SF v
81. x EME S8 where g is an energy interval 9 1 3 Groupwise data Multi group cross sections can also be generated using processing codes which offer additional features for use in transport codes As discussed in the previous paragraph multi group cross sections are obtained by integrating the pointwise cross sections over pre defined energy intervals using a weighting flux The weighting flux 1s either described by the user or calculated by the processing code A smooth weighting flux as described in the previous paragraph is valid for nuclides without resonance structure For resonant nuclides however the flux must be representative of the mixture in which the resonant nuclide is contained This can be calculated by solving the neutron slowing down equation for the resonant nuclide This equation contains a term called the background cross section or dilution that characterises the contribution of non resonant nuclides The equation is solved for different values of the background cross section The result is a GENDF file containing for each value of the background cross section the corresponding flux and cross sections of the resonant nuclide Figure 20 shows an example of the U multi group cross section at different backgrounds A tabular format representation of the cross sections is also available not shown Figure 20 Example of a multi group cross section for U Fila Data Help be Cross sachons Bj Cross sections Fict

JANIS USER'S GUIDE - OECD Nuclear Energy Agency

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