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JANIS USER'S GUIDE - OECD Nuclear Energy Agency

1. m c eE c J 238112 195508 CHATTERJEE TABLE WITH REFS I zn c o IND PAT 478 C j 8BOMBAY 2 298 197812 GARG WRONG YAL SUPERSEDED BY IPA 17 nenn Jm 5 UK 150 AVRE O 61 164 196407 PENDLEBURY ALD UKNDL DFN 176 LEN gm 1 J 17 273 196308 BARRY 14 1 5MB REL U235 SIGF DAV 702 C jJ7eLOWELL 1273 197607 BRADY FOR BIO MED APPLICATIONS NDG t Ez E d tn o IND INI o o 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 page at http www nea fr cinda cindaora cgi where links are provided to the various dictionaries of journal codes etc 58 10 4 1 Accessing linked papers abstracts Where publishers have made papers abstracts available directly via the WWW the reference code is shown in blue 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 imternet browser in the janis settings txt file Under Windows this
2. 60 12 3 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 a ten Preferences In Test paries automatically shoved 9 61 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 CY Janis Export CSV file Columns separator i File name 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
3. 10 1 2 Sorting of retrieval results The retrieved results from a search can be re ordered by clicking on the required column header e g Date Laboratory etc 53 10 2 Searching Evaluated ENDF data 10 2 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 IEJENDF search Local interaction Data incident neutron ENDFB68 Li MF 4 MT 2 Local nteraction Data incident neutron ENDFB6 8 Li MF 4 MT 24 Local Interaction Data incident neutron ENDFB 6 8 Li MF 4 MT 25 Local Interaction Data incident neutron ENDFB 6 8 Li MF 4 MT 51 Local interaction Data incident neutron ENDFB6 8 Li MF 4 MT 52 Local interaction Data incident neutron ENDFB6 8 Li MF 4 MT 53 Local nteraction Data incident neutron ENDFB 6 8 Local nteraction Data incident neutron ENDFBE 8 Li MF 4 MT 58 Local
4. DA LEG f 482e6 48266 8 NEA D1825017 0 SWR 1982Pb206 NEL DA LEG f 728e6 72866 8 NEA D1825018 0 SWR 1982Pb206 NEL DA LEG f971e6 8971e6 8 NEA D1825019 0 SWR 1882Pb206 NEL DA LEG 2234e6 23466 9 NEA D1825020 0 SWR 1882Pb206 NEL DA LEG 2463e6 Dj463e6 8 NEA 21825 021 0 SWR 1982Pb206 MEL DA LEG 2 905e6 2 905e6 10 NEA 21825 022 0 SWR 1982Pb206 MEL DA LEG 2975e6 2875e6 10 NEA 21825023 0 SWR 1982Pb206 MEL DA LEG 83 045e6 3045e6 10 NEA 21825024 0 SWR 1982Pb206 MEL DA LEG 8 1566 3 15e6 10 57 10 4 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 o o w o a a
5. e all heavy charged particles and delayed neutrons alpha protons fission products For each decay mode the corresponding Q value branching ratio and nuclide produced are given 48 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 ETE Decay path for U235 for 0235 from jef22 from file H janis repository databases Bbase ef22 Pa c I LE HIPEPRIPH Hr ag M 3 Root tte ates Gbate J 72 Racioactwe Data Jj0 72 Racoactwe decay data 203235 General informations General informations MT 451 Heading or tito information mnmmmnnsmnmamnmammprs Figure 37 Example of a decay path in graphical format 49 If required information for continuing the chain is not available in the evaluation nuclide produced by the decay mode not available in
6. nteraction Data incident neutron ENDFB6 8 liz MF 4 Mr s58 de M is 7 0 BACA 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 54 10 2 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 through which the search is performed the nuclides to be included in the search etc see Figure 42 Figure 42 The Resonances search dialog box PERN Rhodium Maj 0 sj Local interaction Data incident neutron ENDL 3 3 Rh103 6 4137e3 Local Interaction Data incident neutron ENDL 3 3 Rm03 _B 416e3 55 10 2 3 Decay data search This option allows to search for radioactive nuclides which satisfy specified decay and spectral properties The search can be done
7. 0 BNW 19711235 NTOT SIG 2253e6 f4897e7 243 10047 097 0 Bnw 1971235 M TOD SI 2253e6 f4897e7 243 Loca 10225 025 0 BET 197310235 N TOT SIG_ 5o67e5_ 7408e6 352 Loca 10225 026 0 BET 19730235 NTOT SIG B023e5 Ba16e6 338 Loca f10280 005 0 Nes 19740235 M OT SIG H96e5 Loca 0588 002 0 RPI 19731235 NTOT SIG 5 009e5 Local 0935006 0 ANL 19811235 _ N TOT SIG Local f11002 005 0 ANL 1954U235 NTOT SIG_ P Local LRL 19601235 MWTOD si f 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 38 Figure 24 Display of the full EXFOR file fE Local Janis JEF 2 2 Cross sections U235 p x dal xi File Tools Selected 10016 006 0 E 10016 006 0 Ex Cross sections E Tabler ENTRY 10016 19990617 SUBENT 10016001 19990617 BIB 10 17 INSTITUTE 1USALAS REFERENCE J NP A 133 108 196908 AUTHOR D M DRAKE TITLE Inelastic neutron scattering and gamma production from fast neutron bombardment of 2350 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
8. 6 8 E Exfor amp A JEF 2 2 i EFF 3 0 Cross sections Guy 7 H2 Gjr3 S C Hes E He4 SLs E Li amp C Beg a B10 General informations E MT 1 n total Cross section E MT 2 z z0 elastic scattering amp MT 4 z n total inelastic scattering MT 51 z n 1 inelastic scattering to first exited leve Bj C MT 52 z n 2 inelastic scattering to second exited 7 MT 53 z n 3 inelastic scattering to third exited lev MT 54 z n 4 inelastic scattering to fourth exited le amp MT 55 z n 5 inelastic scattering to fifth exited leve amp 23 MT 56 z n 6 inelastic scattering to sixth exited lev amp MT 57 z n 7 inelastic scattering to seventh exited amp MT 58 z n 8 inelastic scattering to eighth exited le amp MT 59 z n 9 inelastic scattering to nineth exited le MT 60 z n 10 inelastic scattering to tenth exited le 2E 36 9 1 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 Jan
9. Environment JRE version 1 2 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 DVD reader Users who do not have a DVD reader can still use the JANIS 2 1 software The data can be accessed either on line if a high speed internet connection is available or on the two CD ROMs distributed with the JANIS 2 0 version In those cases the software needs to be installed on a hard drive and the databases loaded 4 Installation If you do not have JRE version 1 4 then it can be installed from DVD under directory java where executable files are provided for the installation of Java on Windows 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 DVD or installed on the hard drive Users may choose between e running JANIS directly from the DVD no further installation is required e installing the software onto the computer 3 Mbytes required and accessing the databases on the DVD or from the web e installing the software on the computer along with on
10. 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 Figure 43 The decay data search dialog box 4 Gd Gadolinium EN Search Evaluation E Intensity Type Materia _ Hatt Lite Loca ENDFB amp S 6 4565e3 D 245 X rays Gd153 2087424ETs Local ENDFB amp 8S 41e4 1812e 4 Gamma Gd153 D2 087424E7s Loca ENDFB6 8 B 9766e3 0 042 X rays Gdi59 668160s Loca ENDFB amp 8 6976623 0 101 X rays G61 2196s Loca ENDFB6 8 B 9766e3 0 045 X rays G62 5040s Loca JEF22 B05e3 015 Krays Gdl45m 850s Loca JEF22 f407e4 D007 Gamma G53 20909E7s Loca JEF22 B27e3 0 042439 X rays G59 668160s Local _ JEF22 B27e3 0128 X rays G61 2200s Loca JEF22 B 405e3 0 06251 X rays G62 5400s 56 10 3 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 specifiers and the data type cross sections angular distributions Figure 44 The EXFOR Search dialog box E mE m mu uM mu uM ICountrysLUX E Search Work Subwork Lab Year Target Reactio jen px NEA 21825 016 0 SWR 1982Pb206 NEL
11. 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 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 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
12. d n used for neutron energy 7 5 MeV DETECTOR NAICR NaI Tl detector surrounded by NaI Tl anti coincidence annulus and a large collimator shield Time of flight gating used to reduce background and pulses caused by scattered neutrons ERR ANALYS No information STATUS APRVD Approved by author HISTORY 19691203 19800813A Converted to REACTION formalism Settings Display 3 Local Janis Interaction Data incident neutron E E173 Extor r EAN Cross m Freee T EA PIT Y Compare Pet L 10047 087 0 BNW71 N TOT SIG C Searches DPr Energy angle distributions U235 10016 00 Computations gt DE Energy angle d DPr EHI JEF 2 2 Cross sections U235 Weighting a Display EXFOR file Unselect all Settings Show horizontal lines 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 39 F
13. distributions data of File 4 in the ENDF format Cross 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 r Databases Hl Radioactive Data aj E S Interaction Data incident neutron C ENDFB 6 8 Exfor i JEF 2 2 JEFF 3 0 JENDL 3 3 Interaction Data incident proton E Interaction Data incident gamma C Interaction Data incident alpha Interaction Data incident deuteron C Interaction Data incident triton C Interaction Data incident HE3 Interaction Data incident electron Nuclear properties si EEE H A A A BE E Pee 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 6 1 Importing data from a standard format to create a database 6 1 1 Import dialog The Menu options 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 ins
14. eaae ea aa seen sese eaae era 47 LEITET 46 DST Decay general AGI soca i ee pee ete hee ete tt edere ehe detta 48 9 5 2 Decay path isse etc Or ERE EC EORR TORRE 49 9 5 3 S pectral da a dieto ber vedi tl auaceb ERR EEG RR CERERI SEER 50 92 6 Fission yields eed ee tree e ex eene nee exeo end neca ivarvaseussetecsevenncivese 51 The Search 00 53 10 1 Search dialog box options 4 1eeeeee esee seen ene ee ener nn enero etta aestas eerta seta sese tane eaa 53 LOD DP The Search history Dos ec ate it tr edi eoit teret eei eet e E ines 53 10 1 2 Sorting of retrieval results esses eene nennen 53 10 2 Searching Evaluated ENDF data e eee eee ee eese eene eee ee eene etta seen to seen nest tae era 54 10 2 1 General ENDT search eese esee eese eene enne tenet EENE EE EA sees EASE 54 10 2 2 Resonunce search sia pater PRI AE 55 10 23 Decay data seare hi oie ett ete c Ateste a tae 56 10 3 EXFOR Search eee ttt AEE AREE EE desdavsdenseeunddursotsenedsevacests 57 I0 4 CINDA Search ii xe S REPERI NETS NER ERR eee XRS eR He exe PERS R A tee ccena eun 58 10 4 1 Accessing linked papers abstracts eese eese tenens 59 Liye UDO AtG PT osuo srs es 59 CUSEOMMIS ATION sess cai ssssnassascesccacestsediesssanesasossscnesnssueddesduaddasebs eassaseesesesasnadentecddessSeuscindanscssesedaciess 59 EET E canada ec
15. 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 automatically check for updates and download the necessary files from the NEA web site However as this option replaces the old versions 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 is 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 describ
16. oO JEF22 U235 hendf E U238 hendf oO JEFF3 E Pu238 hendf Pu240 hendf The user may enter in the Source files field S Data Processed JEF22 U235 hendf S Data Processed JEF22 U238 hendf or S Data Processed JEF22 then JANIS will import all files contained in this folder To specify the location of the database to be created the user should specify C Janis mybase db conf in the conf file field If this file already exists then the personal database already exists and will be updated see example below In our current example this file does not exist and will be created by JANIS along with the data and logs folders Please note that the user does not have to create the mybase folder it will be created by JANIS 22 JANIS stores relative paths to the source files in its databases So if the user specifies S Data Processed JEF22 as the root folder then the relational database will contain relative paths such as U235 hendf U238 hendf These relative paths are used later in combination with the root folder to rebuild the complete absolute path to the source files To load the database created the user should specify the same root folder see section 8 2 Please note that JANIS relational databases only store an index to the sources files ENDF and not the contents of these files hence during execution JANIS needs to access these files After successful
17. reaction Q value is given in the right hand side panel and in the graphical mode other information is available e 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 Xmin Xmax Ymin Or ymax will cause the plot to come back to the automatic zoom level e A checkbox close to x sqrt X If this checkbox is crossed the quantity displayed is then sigma E sqrt 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 e 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 E Interaction Data incident neutron for Fe56 from 300K BEE File Data Help Ex Cross sections SE Cross sections Cross sections for Fe56 from 300K from file I xpl dat2 users nouri POINT2000 E MT 1 n total MT 2 220 1e 5 2 237362 9 35173e1 Ll 06897e 5 2 16436e2 9 04944e1 1 14269e 5 2 09384e2 8 75721e1 2215e 5 2 02564e2 847471e1 1 30574e 5 1 9596962 8 20164e1 39579e 5 1 89592e2 7 93769e1 1 49205e 5 1 834262 7 68256e1 1 59495e 5 7746402 7 43597e1 1 70495e 5 1 717e2 71976661 82254e 5 1 6612662 6 96734e1 1 94823e 5 1 60737e2 6 74478e1 2 08259e 5 1 5
18. the other databases should be unloaded prior to starting the search 10 1 Search dialog box options The various functions of the 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 e Open results After selecting a number of results 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 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 results lines to be printed e Close Closes the search dialog box e Maximize Masks the criteria part and allows viewing more result lines 10 1 1 The Search history box Previous searches performed on the JANIS database can be recalled by selecting them from the drop down list These can then be refined by adding further parameters in other fields or modified by changing the relevant field parameter as required
19. 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 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 62 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
20. 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 CREER Tabler E Janis Plotter Colors Drawing order strings 0000000 17 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 dial
21. 1 Ci and C3 are calculated by the continuity conditions at Emax n and Emaxepi C 1 and C oa l 3 2 E max th px E max epi E max th exp Os E 2 exp e ES th fis The General spectrum uses all the components as given in the following formula max th cen for E lt E sth x E T3 for Bor lt E lt E oi E 0 5 x E cA Eesd E tC exl WE VES lj for E Eus fis fus 33 This is equivalent to WT 6 in NJOY The following energy limits need to be specified e Ewan where components 1 and 2 join e Emax epi Where components 2 and 3 join e Lis where components 3 and 4 are equal C2 the constant value of the Maxwell thermal spectrum is set to 1 Ci and C3 are calculated by the continuity conditions at Emax 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 E Components 3 and 4 are added for E gt Emax epi The averaged cross sections are calculated using the following definition olE x E ae Hu y EJdE o 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 is e
22. 5527e2 5 52969e1 Reaction Q value 2 22622e 6 1 50489e2 6 32187e1 D 37976e 5 45619e2 6 12108e1 oo ev D 54388e 5 1 40911e2 5 92709e1 2 71932e 5 1 3638e2 5 73968e1 Oo Wema 2 90686e 5 1 3196e2 5 55866e1 3 10734e 5 1 27706e2 5 38381e1 3 32164e 5 1 23595e2 521494e1 3 55072e 5 1 1982162 5 05186e1 3 7956e 5 1 1578e2 4 89439e1 4 05737e 8 1 12068e2 4 74236e1 4 33719e 5 1 0848e2 4 59559e1 4 63631e 5 1 05013e2 4 45392e1 M 95606e 5 1 01662e2 4 31718e1 5 29786e 5 9 84246e1 4 18524e1 5 66323e 5 9 52962e1 4 05794e1 Source Settings Display Fe56 from 300K Ifile I xp1 dat2 usersiouri POINT2000 ENDF Cross section 9 1 2 Weighting of pointwise cross sections JANIS offers various options for cross section averaging When a cross section is 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 First tab allows selecting other cross sections 30 Figure 18 The Weighting dialog box Group tab e Weighting romos m Uniform in log File defined a 2 0E7 foo Group structure Two options are available e Uniform in log In which the user specifies the minimum and maximu
23. 7 z 4n Angular distribution MT 38 n 3nf fourth chance Angular distribution EHA MT 51 zi Le Angular distribution BHA MT 82 z n2 EHA MT 53 z n3 LS 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 c u E E is related to the energy angle distribution f y E E by o u E E o E y E f u E E 2n where E is the incident energy E the energy of the product emitted with cosine u o is the reaction cross section and yi E 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 distr
24. Anchor node Please select the branch were you want to insert the result node 4 This choice will affect equation usability Local Interaction Data incident neutron JEF 2 2 Cross sections Fe56 MT222 zna Cross section Annuler 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 40 Figure 27 Application of a pre defined operation E Local Janis JEF 2 2 Cross sections Pu239 10 xi File Tools Selected b COMPUTED MT 18 z fission total Eta for Pu239 from JEF 2 2 from Local Janis Xmin 1 0E 5 Xmax 2 0E7 Ymin 0 16165236297025642 Ymaxe 5 675807999119706 MT 17 z 3n Cross section amp MT 18 z fis Cross sec MT 19 n f e MT 20 nf MT221 n2nt MT 37 zn L MT 38 nni La MT EA 6m nay 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 perf
25. 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 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 63 JANIS DESIGN AND DEVELOPMENT TEAM 72x cy AEN N Soppera A Nouri P Nagel E Tuncay OECD Nuclear Energy Agency www nea fr janis 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 64
26. Example plot of a pointwise cross section FA iy interaction Data fincident neutron for Fe56 from JEF22 Fle Osta Hep 4 Ez Cross sections iff Cross sections DENM A Cross sections for FeS6 from JEF22 from file H janis ases hasr je 22 x flog fios E rated tins F x sang wxmm o 5 mwepor Ymins f 00385081 vmaepaon Emi ENDF Cross section Reaction Q value r7 Weighting 3 e56 from JEF 22 Ille H Jjanismases base Jefz2 General information Resonances data Resolved parameters 1 UE 5 lt E lt 862000 0 Unresoived parameters 882000 0 E 3000000 0 integral data MTz2 20 2 MT 4 n C Pm MI 16 2 20 2 F Pin na Pim T D C Pim MT 51 zn rem MT 5 _ 42 Pim MT 53 nn3 C Pm IE 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 t
27. Fluorine 10 Neon 8 6 11 Sodium 8 12 Magnesium FI 5 8 868 22 8 r Databases B S file H janisibases base jef22 E S Interaction Data incident neutron E C3 JEF22 Energy angle distributions Energy distributions Angular distributions Cross sections 3 73 Radioactive Data 4 EQ JEF22 Fission yields data Radioactive decay data E Ns m Radon Rn N 148 Z 86 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 Navigation 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 curs
28. JANIS USER S GUIDE July 2004 NUCLEAR ENERGY AGENCY ORGANISATION FOR ECONOMIC CO OPERATION AND DEVELOPMENT ae uu TABLE OF CONTENTS TIBERIM 6 PEN IOVUII EE 6 L2 What s new in version 2 1 35e des teet sees SEELEN EE ve e epe Pete xe se ene ek ETEA bere vss edenda 6 Content of the JANIS DWVD eee von evan eoe eat earn eno ee te veo even ven ov emt epo regn erat erae p Sene S 7 Requirements and compatibility eee ee ecce ee eee ee ee eee seen sete to seta ee ense ee en setae seen ae eaa 8 incre 8 Starting PUN K A E 9 Uc 9 General overview E esee esee enses stato aeta sotto seta sesso seta stesse A stesso setas tese n sens ena 11 7 1 TRE Browser WwIndOW 4 iius eene e eerte eoe ees tuve e a evas ee pese eee iUt siae reae Fe eae iae rena 11 7 2 Navigation tools The Chart of the Nuclides and Nuclide Explorer 11 7 3 Visualisation tools The Renderer eee ee ee eee eese seen entente nete ne thee tn nennen 14 Data structure JANIS database eere eee eee esee enses senses enses etas es sonata seta sens ense tas tns ena 19 6 1 Importing data from a standard format to create a database eese 20 Onl T Import dialogzs su ee Uta te dee ee b ree 20 6 1 2 Example 1 Creating a new personal database esee 22 6 1 3 Example 2 Updatin
29. 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 13 Figure 4 The Go To pop up window ej Janis file I xp1 dat2 users nouri JEFF3RDDT 2 Radioactive Data JEFF3T2 Radioactive decay data EX zc Berar al EN V bere Oe Amas mv gt Ian MEV stable 5 a HHH nt ese ERR PSRs EE LL LL TL TL TL 1 1 jJ TESTES e E STE ESTEE a SES ESSET dl um LESE LOT CELECECEEETECEEEHECELTETI oe eee eee ara canal 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
30. 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 e Add to list Adds the selected component s to the 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 e 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 e 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 35 Figure 21 The Compare Explorer window s Janis Compare Explorer DER Add to list NEA 2 _Adato st amp Radioactive Data Losdbese base a Interaction Data incident neutron Close amp ENDFB amp
31. able on the NEA server This will be referred to as Remote NEA database e Access to users data contained in text files typically a single or a set of ENDF files The data contained in the JANIS DVD or CD ROMs is basically split into two parts Directory data contains several categories of data such 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 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
32. ate 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 is installed in the directory E Mycomputer Program Files JavaSoft jre1 4 bin This increase in size is due to the minimum amount of disk space which is allocated per memory address on large disks gt 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 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 3 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 When an execution problem occurs JANIS generates a window with the error messages This window enables to send the error message to the JANIS development team if an internet connection is available This is performed by pressing the button Send bug report O xd janus connection http client HttpConnectionException VO Err
33. 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 1 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 14 Figure 5 Data visualisation The Renderer fS Local JEF 2 2 Cross sections F19 5 x Fie Tools Selected E Cross sections Taber Plotter MT 1 n total Cross section for F19 from JEF 2 2 from Local x fos z Y Log T xst Xmin 1 0E 5 Xmax 2 0E7 Yminz 1 465371 Ymax 68 03194 More Move J Zoom Cross section Reaction Q value m Local Interaction Data incident neutron JEF 2 2 Cross sections F19 G 73 General informations integral data _ MT 451 z Heading or title information MT 1 ntotal Cross section MT22 z z0 elastic scattering Cross section MT 4 zn Cross section Searches MT 16 z 2n Cross section Computations gt NT Gp Coss section ein MT 51 z n1 Cross section ES Dipl ENTOR Ale MT 52 z n2 Cross sectio
34. braries were included JEFF 3 0 A and NUBASE 2003 This resulted in the need of increased storage capacity JANIS 2 1 is now distributed on DVD 2 Content of the JANIS DVD The software and a selection of recent nuclear data were packaged to produce the new release JANIS 2 1 The selection of data includes evaluated nuclear data libraries processed at 300 K ENDF B VI 8 JEF 2 2 JEFF 3 0 JENDL 3 3 activation library in ENDF 6 format EAF 2003 JEFF 3 0 A experimental data EXFOR bibliographical data CINDA nuclear structure data NUBASE 97 and NUBASE 2003 The DVD has the following 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 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 1_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 the 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
35. 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 Ag 12 Figure 3 Details for one particular nuclide Ag Sj Janis file H janis bases base_jef22 Radioactive Data JEF22 Radioactive decay data File Database Tools Chart Help BRANCHING x EC Betat a LASE he Lae Beta mht INACTIVE m e Ira LI g102m A 9 Ag103 ai 9 Agi03m 9 Ag104 9 Agi04m 0 Ag105 ma 0 Agt05m des 0 Ag106 At s106m o9 Agt07 Q 0107m e il Databases E filejH janisibases base jef22 B Interaction Data incident neutron QI JEF22 Energy angle distributions Energy distributions Angular distributions Cross sections B Radioactive Data Ea JEF22 Fission yields data o EARE 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
36. ccording 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 distributions 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 SEE Janis JEF 2 2 Energy distributions U235 E ini x File Tools Selected E COMPUTED Plotter MT 455 z nubar d for U235 from JEF 2 2 from Local Janis q y 2 11 Energy distribution Ene Ged x flog v Loo 54 component 1 6 Ene ETES aa cok osiot 82 6 nen DE 5 I x satoo component 3 6 Energy 1 0E 5 Xmins 0 0 cotaponent 4 6 Energy 1 DE 5 cofnpongnt 85 6 Energy E 5 Xmax 3000000 0 i Ymin 1 0E 10 Ymax 1 380084878115E 5 More Move Zoom X Secondary energy Energy distribution Representation General evaporation spectrum EHO MT 18 z fission total 73 MT 455 z nubar d e Energy differential cross section e Energy distribution ES component 16 Energy distribution 9 Fractionnal probability Q Partial distrib x trac prob 0 E component 2 5 Ene
37. d Password fields provide the means to control the access to the database The default value for both fields is janis 21 e The two fields JDBC 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 file U235 endf in EAF_99 directory By entering D Tapes EAF_99 JANIS will automatically import all files and sub folders in this directory Two examples are given below which illustrate the import function one for creating a new personal database and a second for updating or adding to an existing personal database 8 1 2 Example I Creating a new personal database Lets take the following example the Janis DVD was installed in C Janis so C Janis software contains the executable JAR files C Janis database contains the DVD database s and the user wants to create a new personal database in C Janis mybase by importing source files located on a shared drive S in folder JEF22 as shown below the files in JEFF3 will be used in example 2 79 Local drive C C3 Janis C3 software database janis C3 data o logs db conf Shared drive S Data Processed
38. d it will be impossible for JANIS to access the four sources files This example shows that it is impossible under Windows to import into the same database files stored on different drives because it is impossible to build a relative path from folders on different drives Notes If the user enters S Data as the root folder for the first import and the same value for the second one simply because a database can only store relative paths to only one given folder then the relatives path which will be stored in database will be AProcessedNJEF22NU235 hendf Processed JEF22 U238 hendf Processed JEF F3 Pu238 he ndf and Processed JEFF3 Pu240 hendf The two choices will give a usable JANIS database The reason JANIS stores relative paths and not absolute ones which would not require specifying a root folder is to obtain databases which can be used on different systems For example one can imagine two colleagues accessing the same shared data but mounted with different drive letters e g SA and ZA With absolute paths stored in the relational database the second colleague would not be able to use the same database because paths like S NData will not be valid on his system This may seem to be a rather advanced usage of JANIS sharing an in house created relational database but this is in fact the case of the database provided on the DVD as each JANIS user could have a different DVD drive letter A m
39. e 1 6 17e 2 5 74e 1 0 2 27744e2 2 349503 21 5 7 5021e 1 2 1e 4 7 5e 1 6 42822e 1 1 2448e4 0 1 5e 1 4 5201e 1 2 81e 3 4 5e 1 0 1 3449 1 7748e4 0 1 5e 1 4 648e 1 1 48e 2 4 5e 1 0 4 84 2 0168e4 21 5 p 5417e 1 417e 3 7 5e 1 1 47922 2 2801e4 0 1 5e 1 2 01481 21481e 1 4118 0 1 26144e1 2 7791e4 Dj5e 1 1 41016e3 1 4093e3 8 6e 1 9 70131e1 34234e4 0 11 5 279132 B5132e41 244 0 1 98365e1 Resonancas 3 672504 1 5e 1 1 08 5 7e 1 5 2e 1 3 84137e1 Ais oo 3 8418e4 0 11 5 9 78e 1 2 38e 1 7 4e 1 0 3 41769e1 4 6053e4 115 5 4241 5 1391 2 85e 1 a 1 11002e2 Formalism 5 214e4 11 5 1 7688e1 1 729401 3 94e 1 1 01175e2 Reich Moore 5 3561e4 0 1 5e 1 1 7042 1 1242 5 8e 1 0 3 32257e1 5 3677e4 1 5e 1 4 87e 1 3 7e 2 4 5e 1 0 3 81842 5 9232e4 0 111 5 5 2577 4 8077 4 5e 1 0 8 32942e1 6 347464 0 11 5 1 35295 8 0285e 1 5 5e 1 5 04475e1 7 2988e4 0 22 5 3 38073 2 8073e 1 31 0 9 20762 7 4029e4 0 O 5e 1 6 1205e2 6 1146e2 539e 1 0 3 64065e1 7 7082e4 0 1 5e 1 3 8278 3 5228 3 05e 1 3 22096e1 8 0842e4 0 22 5 1 2514e1 1 1781e1 7 33e 1 0 9 42475e1 8 362884 D 5e 1 1 21564e3 1 215163 5 4e 1 3 22444e1 9 0338e4 0 11 5 2 2402e1 2 1979e1 4 23e 1 0 5 85976e1 E Source Settings Display Fe56 from 300K ffilevlxp1 dat2 users nouri POINT2000 General information Resonances data Figure 16 Example plot of resonance parameters jc x Hj Interaction Data incident neutron for Fe56 fro
40. e 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 Version JANIS 2 0 was released in January 2004 The software and the corresponding data were distributed in two CD ROMs More than 1200 users requested the CD ROMs and many others downloaded the software from the web site In the current version JANIS 2 1 few other improvements were implemented e g search optimisation easy access to databases through wizards and new li
41. e or more databases N B 300 Mbytes are required per database however it should be noted that on PCs using large disks with a FAT 16 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 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 DVD to this directory i e directories software and groups file janis bat or janis sh if you are running on the UNIX system If the user does not have a DVD reader then the software can be downloaded from the following web site http www nea fr janis e The databases can eventually be copied to the same drive or to any other drive including those on a network 5 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 bat or janis jar 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 window should not be closed otherwise the software will termin
42. e weighting flux definition f E Each line of this file contains a value of E and fi separated by blank s A continuous weighting function f E is constructed by assuming a linear linear interpolation between successive values of Fifi Note that no blank lines are allowed after the last f 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 1 x E C Bex a e A slowing down component defined as 32 Weee e A fission spectrum characterised by 0 the fission temperature in eV fis X E cfEswd a 3 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 4E Cuero 2YE JEn d fus The PWR spectrum uses components 1 2 and 3 as given in the following formula E C zex for E E sth x E P for PN lt E lt E idi E C VE E forE gt E X z 34 exp ex e or gt max epi ofis This is equivalent to IWT 4 in NJOY The user needs to specify the following energy limits e Emax n Where components 1 and 2 join e Emax epi Where components 2 and 3 join C2 the constant value of the slowing down component is set to
43. ected EY Fission yields SE Tabler LX Fission yields Tabler p Plotter Fission data Parent cumulative fission yields Thermal x Lin Log z m Mr Chain mode same A from 2 2 from Local 0 17 Pu239 Mass of product 90 0 Xmin fs 2 235 Mass of product 90 0 Xmax o 8 Ymin fo o030 EHS Fission data EHS Parent cumulative fission yields GHD Fast 400keV E A Thermal 0 0253e V Chain mode same A L Charge mode same Z G Parent independant fission yields 52 10 The Search tool Five 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
44. ed in the following sections Any change of these options should be confirmed by pressing the button Save followed by OK 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 can 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 59 CIC ae Bases Chart Renderer r Check for update Check for new versions of Janis at startup Internet browser Command line to launch your favorite web browser C Program FilesAnternet Explorerjexplore exe RO X4 Files Root folder containing zipped EXFOR files Path deter I Save Cancel 12 2 Options for the display of the Chart of the Nuclides 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 Figure 47 The File Preferences dialog box Chart tab LT lox General Bases Chart Renderer Colors Cursor Zoom restore previous C preferred value Save Cancel
45. epend on the selected reaction on the selection item list Even when a reaction is selected highlighted but a display not requested these fields will reflect the information 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 46 Figure 34 Example of differential cross sections EjLocal JEF 2 2 Angular distributions Pu239 Ani x Fie Tools Selected LE Angular distributions E Angular differential cross section Lee f m i A Gnl Angular differential cross section for Pu239 from JEF 2 2 from Local Log 7 Y Log amp x santo Xmin 7832 913 Xmax 2 0E7 Ymin 0 00351358830931 54333 Yimax 0 228461607835347 More vere m Zoom X Eneray ha MT 3
46. g or adding to an existing personal database 23 OLA Import progress dialog deem eere RR ies votes E teet ee ERI Uere 24 8 2 Load Connect DisconnectRemove a database eee e eere eene nennen 25 6 3 Viewing data directly from a file e eee e eee e ee eee eee eee eene entente nee a tasses etta aee ra 26 JANIS features through examples 4 ecce esee eren esee e eee en nette setas etna eee ta sette s toas sten a ee 27 9 1 Cross sections and resonance parameters eeeeee esee ee ee eene eene eine ene etta nest aas en nee tn aestas 27 9T T Pointwiseddi da iii teet a keea ee E bo aea eru EEEE t 27 9 1 2 Weighting of pointwise cross sections eese eene enne enne 30 9 1 3 Groupwise data ete hti codi ettet ete co e ose tee ee ates 34 9 1 4 Comparison of data from different sources eese eterne 35 9 1 5 Comparison with experimental data EXFOR sss 37 10 11 12 13 14 15 16 9 10 COmpuldtiOn ip EG ER PERSEO A Eaa Eai 39 9 7 Cross section uncertainties eese NNA EE EEEE AEE enne nre EEKE AA 42 9 2 Energy distributions ie oer ene ea eei ease e EEEE EEA ce pin ed sobssuveseossand suave 43 9 3 Angular distributions sisiane ein eene ee then dena ee e nU EE Pe eS ehe ar oon resa vedo 45 9 4 Energy angle distributions eeeeeee esee ee ee eene senes te etta netta seen testen nest
47. hen 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 e Eo eV is the resonance energy e listhe orbital momentum e isthe target nucleus spin e Jis the compound nucleus spin e gammar gamman gammag and gammar eV are the resonance widths e sigmaco T is the cross section at Eo where the width used is the square root of the total width squared and the Doppler width squared calculated at a temperature T to be specified in the Options Selection Panel 3 in Figure 5 at the right of the screen 28 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 HE Interaction Data incident neutron for Fe56 from 300K File Data Help Z Resonances kx Cross sections Resonances Cross sections Tabler Resonances for Fe56 from 300K from file I xpl dat2 users nouri POINT2000 More Eo Jic IC Res Jt Res gammaT gammaN C gammac c gammaF c sigma T 4 7336e5 0 0 5e 1 3 08461e5 3 084565 u 5 6991 2 4213e4 0 0j5e 1 2 708163 27071e3 f 0 1 11376e2 24381e3 0 0 5e 1 1 84262 1 933402 8 6e 1 1 10159e3 1 1497e3 0 1 5e 1 6 357
48. ibution by interpolating according to the interpolation law specified in the evaluation 43 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 If 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 gt E Pl E 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
49. ibution is plotted as a function of one variable whilst fixing the other two The varying parameter is 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 E 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 47 Figure 35 Example of an energy angle distribution E Local ENDFB 6 8 Energy angle distributions Fe56 O xi File Tools Selected E Energy Angle distributions product yields SE Tabler pee MT 16 z 2n ENDF energy angle distribution Product n ZAP 1 0 X Log v Y Lin x Le LIF 0 Energy angle distribution for Fe56 from ENDFB 6 8 from Local r te t Cos of angle 0 0 Energy 2 UE a 1 5e 74 Xmax 8775000 0 Ymin 4 1746538749999994E 9 Ymax fi 5918282567 More Move Zoom X Secondary energy 1E r Energy angle distribution Representation Continuum energy angle 3 Legendre Frame of reference i Angle LAB system EHD MT 5 z anything ENDF energy angle distribution E LAB system amp B 34 MT 18 z 2n ENDF energy angle distribution HO Product Fe55 ZAP 26055 0 LIP 0 8 124 Pr
50. igure 25 The computation window o x Create Pool MT 80 z n30 Cross section MT 81 z n31 Cross section 9 MT 82 z n32 Cross section MT 83 z n33 Cross section 9 MT 84 z n34 Cross section MT 81 z nc continuum Cross section EHI MT2102 z y radiative capture Cro cross section variance R EHS MT2452 z nubar T Eta Neutron production ud b Equation lt MT452 Neutron production MT18 Cross section MT18 Cross section MT102 Cross secti Mame 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 nu bar Figure 26 Selection of the level at which an operation is saved
51. in the users computer environment this option might not 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 ux Type of data e g neutron interaction data decay data Data set typically an evaluation e g ENDF B67 or experimental data EXFOR Category e g cross sections angular distribution 19 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
52. ing 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 Importing a whole pointwise library may take about one hour 8 2 Load Connect Disconnect 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 e The Label field allows to specify an identification text field e The Type and JDBC parameters fields are scroll menus which enable to specify the type of the database and the corresponding Java driver These fields are pre selected For the connection to a local database the type is JDBC and the driver is Mckoi For a connection to the NEA database through the servlet the Type parameter is HTTP and the URL is specified For the connection to a local database the user should specify the name of the Mckoi configuration file e g file databases janis db conf on the DVD drive and the path to the folder containing the data Root folder 25 Figure 13 The Database load dialog box x Type Rez Label comit Enter JDBC parameters and files root JDBC Driver Mckoi x Embedded conf file ae Ei C Server host E por
53. is Compare Explorer Addto list E NEA E Radioactive Data jj a Interaction Data incident neutron Close Ez ENDFB 6 8 a Exfor a Cross sections n H BNZ EIH cxx HD20 H DXX Ez HPLE G CIHR 11020 002 0 MTR1964 N TOT SIG 11026 002 0 ORL1965 N TOT SIG E 11142 003 0 MIN1948 N TOT SIG E 11150 003 0 COL1949 N TOT SIG E 11162 002 0 GA 1966 N THS FA SIG E 11162 003 0 GA 1966 N TOT SIG 11172 002 0 BNL1953 N TOT SIG 11173 002 0 GA 1950 N TOT SIG E 11174 004 0 BRK1950 N TOT SIG 20907 002 0 ETH1969 N TOT SIG E 21078 002 0 MUN1961 N TOT SIG E 21234 003 0 ETH1947 N TOT SIG MON E 21262 002 0 CIS1956 N G SIG MON E 21341 002 0 MUN1961 N TOT SIG 40109 006 0 IFU1971 N TOT SIG C 40847 008 0 KUR1983 N TOT SIG FIS E HNat Sm E H2 mL Load base E amp amp E gm E ce E EE EH EE amp amp amp E amp amp amp amp amp amp amp amp i amp 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 37 Figure 23 Result of an EXFOR search CEDES z P20 trenium p _Lab vear Target i 10047 096
54. isplay 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 1 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 versions JANIS 2 0 and above The software now accesses directly to the text files eventually zipped in order to reduce the required storage and the tabl
55. ither 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 34 Figure 20 Example of a multi group cross section for U jel22 Fia Data Help bz Cross sectons Bi Cross sections Cross sections for U238 from Gerdf je 22 from file E Janis udi 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
56. iven 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 of the emitted particle and associated error normalisation factor and associated error 50 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 i 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 fi
57. ls order Base Datatype Radioactive Interaction Top Evaluation Jef2 2 Jeff3 0 Category Cross Angular Material Reaction Vork OK Save as defaults 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 dialog box g amp Adjust display properties x s Table properties Name C Manual Auto show Y errors Errors drawing mode C two lines thickness Cancel 16 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
58. ly importing the files the user will obtain the following tree Local drive C C3 Janis software database janis data C3 logs B db conf C3 mybase C3 data C3 logs E db conf 55 Shared drive S C3 Data C3 Processed JEF22 E U235 hendf E U238 hendf C3 JEFF3 E Pu238 hendf E Pu240 hendf 6 1 3 Example 2 Updating or adding to an existing personal database Now lets say the user wants to add to his new database the files stored in SADataWrocessedUJEFF3 he will have to give the location of the conf file C Janis mybase db conf in our example and enter the same root folder S Data Processed JEF22 Hence the resulting database containing the previously imported JEF22 files and the files from folder JEFF3 will contain the following relative paths U235 hendf U238 hendf WEFF3 Pu238 hendf and JEFF3 Pu240 hendf With these relative paths and the root folder parameter JANIS will be able to access all source files when needed If the user enters another root folder for the second import then the database will not contain the correct relative paths e g the user had specified S Data Processed JEFF3 as the root folder for the second import then the database will contain the following relative paths U235 hendf U238 hendf Pu238 hendf and 23 Pu240 hendf Since the database load function only allows one root folder to be specifie
59. m JEFF 3 T2 File Data Help bx Resonances a Resonances Plotter 31 Resonances for Fe56 from JEFF 3 T2 from file T xpl dat2 users nouri JEFF3P x Loo E v oo zi Sigma E Resolved parameters 1 0E 5 lt E 862000 0 AA fin barns L ksanod 1 Xmin 863 25 A Xmac 1411184 9 iud Ymin 0 7013246392059871 5v Ymax 27 323966686801 More rResonantes 3 10 Tho m 5 Formalism Reich Moore Y mi 1000 E fined Source Settings Display Fe58 from JEFF 3 T2 filesluxp1 dat2iusersinouriJEFF 3PA General information ui Resonances data Resolved parameters 1 0E 5 lt E d 0 TA Pm Unresolved parameters 862000 0 E 3000000 0 n Integral data In MT 1 n total Cem y E VE iol 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 sigmao T The user can enter a new value for the temperature and confirm by pressing the Enter key on the keyboard 29 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
60. m energy limits 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 groups of the JANIS installation Note that no blank lines are allowed after the one describing the last group 31 Spectrum definition The third tab of the Weighting dialog box see Figure 19 enables the definition of the weighting flux spectrum Figure 19 The Weighting dialog box Spectrum tab Constant spectrum ee pose PAR spectrum G spectrum ain 1400000 0 25000 0 emen o 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 th
61. n Unselect all MT 53 z n3 Cross section Settings MT 54 no Cross section Show horizontal lines 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 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 is 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 15 Figure 6 Definition of levels in the selection tree inj x Leve
62. n by interpolating according to the interpolation law specified in the evaluation the default value being the first tabulated point 45 Figure 33 Example of an angular distribution S Local JEF 2 2 Angular distributions Pu239 Bl x File Tools Selected ke Angular distributions Plotter i a 1 aa elastic scattering Angular distribution for Pu239 from JEF 2 2 from Local x fin hd NE n ps in sys Energy 1 0E 5 Xmin fa 0 Energy 1 0E Xmax fi 0 Ymin o 004392495205368027 Ymax P 0 X cos of angle t x Angular distribution E Display 1 0E 5 NENNEN 1 0E7 2 1 Representation olynomial Frame of reference Display Bie Local Interaction Data incident neutron JEF 2 2 Angular distributions Pu239 General informations MT 451 z Heading or title information 5 EHA MT22 z z0 elastic scattering E Angular differential cross section Angular distribution 9 MT 18 z 2n Angular distribution MT 17 z 3n Angular distribution Ooga mI 1 Selection of the x axis variable mu or E 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 d
63. nascdaveseaseiesscedsbesseasedstsassigesdeabetes desc sdveduesaiedsasddetadeaeeadd suctaahasnesauestaies 59 12 2 Options for the display of the Chart of the Nuclides eee eee eere enne 60 12 3 The Renderer panel options e eeeeee e eee esee esee ee ee eene enne annee easet eaae asas sense seta aestas 61 Saving the displayed data to the disk 4 e eeee eee eee ee eee eee eese ee eaae ee te seta nest eaae enun 62 I3 I Saving tabular data eee tete eei siena een Eee ve ESES ess se S VR VE REESE RS aoai 62 13 2 Saving 1 4 poete e te os bond na than teo ea aad repere EEEE E 62 13 3 Saving textual information e eee eee eene eee ee eene eene eaaet anos e eaae etta aee a aas e enses etna ee ra 62 Printing Options oes e eooeeeeeot eee o erra vo eo cen oen nae eoa CVa Ves eR e osa LUN Ea a ele eaae EVI Pn ka espe eoe ea eR ee n ERe oes STan 62 References o 63 Acknowledgement esee ece esses onere es ees eo en ea Tue pee oe ER REP p ssns Pe cue s osos vl phe see Ssss Pan E EE esssS 63 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 materials and nuclear fuels are present This represents a wide range of applications Nuclear data are thus needed for a variety of u
64. ng on whether the user is simply interested in temporarily viewing the content of a file without storing the resulted structure 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 The format of the source files must be chosen from the Format drop down list e In the 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 EAF 99 then the same label might be used to qualify the library e The Root folder field should contain a valid path to an existing directory The path entered here will be used to compute the relative path stored in Janis base e The User an
65. o 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 constructs 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 S Local JEF 2 2 Fission yields data Sm149 2lni xl File Tools Selected EY Fission yields S Tabler Platter Fission data Product cumulative fission yields Thermal X Lin x v Loa hd 0 0253eV for Sm149 from JEF 2 2 from Local 0 d Xmin paz 2 Xmax pass Ymin 0 0036378999999999935 Ymaxe fo 0263434 Thermal 0 0253eV a Local Interaction Data incident neutron JEF 2 2 Fission yields data Sm149 Fission data EHS Product cumulative fission yields Fast 400keV e High 14MeV Le Spontaneou Thermal 0 0253e V HH 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 E Local JEF 2 2 Fission yields data U235 z ni xj File Tools Sel
66. oduct Photon ZAP 0 0 LIP 0 EY Product n ZAP 1 0 LIP 0 Energy angle distribution L Product yield Ss v Pit zl 1 Selection of the x axis variable E u or E 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 is 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 allelectron related radiation such as beta beta conversion electrons Auger etc e all electromagnetic radiation such as gamma rays X rays and annihilation radiation
67. og window shown in Figure 9 appears where one can specify the file name and location and 66 99 other options including the choice of column separator The default column separator is a Figure 9 Dialog box for File Save s4 Janis Export CS file Columns separator i File name n zl 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 Ymin 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 Ymin and ymax in the Parameter Selection Panel A right click On Xmin Xmax Ymin OY Ymax Will return the plot to the previous zoom level 18 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 DVD or CD ROMs This will be referred to as Local database e Access to JANIS data avail
68. om JEF 2 2 from Local Janis q vli uon rgy x log Lin rey 1 Xmm oo Xmax 5 0E7 Ymin 3 780910000000038E 24 Ymax 3 49074E 7 More Move Zoom x Secondary energy ea p Energy distribution E Display 1 0E 5 Representation S Local Janis Interaction Data incident neutron JEF 2 2 Energy distributions U235 _ General informations MT 441 z Heading or title information 2 73 MT 18 z fission total 4 Distrib x section Energy distribution EHO MT 455 nubar d 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 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 distr
69. on 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 26 9 JANIS features through examples 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
70. or 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 11 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 ej Janis file 1 xp1 dat2 users nouri JEFF3RDDT 27 Radioactive Data JEFF3T2 Radioactive decay data File Database Tools Chart Help BRANCHING m g107m eo mm Databases B S Radioactive Data E C3 JEFF3T2 lea filesI xp1 dat2 usersinouri eo Radioactive ded M Ec Betar EC Betat GB Beta M Aloha EM T EH v sr EH v mM n EH stable EZ INACTIVE x Stable Sin ue Materials g103 j Ag103m Agios 109 g104m 47 Ag 62 s105 g105m g106 ween g106m nu g107 Pde A 2 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
71. or with http Awww nea frjanis JanisServlet 618 connection Versions Version 2 1 build 5 4 5618 timestamp Java 1 4 2 04 b05 Classes 48 0 Windows XP v5 1 x85 Virtual Machine Java HotSpot TM Client vM Sun Microsystems Inc Stack trace janus connection http client HttpConnectionException lO Error with http www nea fr janis JanisServlet b18 co at janus connection http client JanisServletClient postObjects JanisServletClient java 89 at janus connection http client JanisServletClient postObjects JanisServletClient java 1 00 Y rf E Close 10 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 Sj Janis file H janis bases base_jef22 Radioactive Data JEF22 Radioactive decay data BEES File Database Tools Chat Help 1 BRANCHING fd O 15 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 EXE ec beter a Td Ae Im Beta Aloha d x 8 2858 e EJ INENENDOBU ISISISITTISTIT ST 4 FI D INACTIVE Materials amp Q 1 Hydrogen 8 6 2 Helium 8 6 3 Lithium 8 6 4 Beryllium 8 6 5 Boron 8 6 6 Carbon 3 m Nitrogen 8 Oxygen 9
72. ore appropriate choice for the root folder might be to take the common part of all paths to any source files the user may wish to import into the personal database created Note that the root folder specified can never be changed following the creation of the personal database In our example a good choice may be S Data Processed or S Data or simply SN 6 1 4 Import progress dialog 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 XML file date time xml 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 xml provides complete information on all imported data XML file can be displayed by a recent browser IE 6 0 Netscape 6 24 Figure 12 Status of the Import process Ig Janis Import 791452 BEE Import acheived file D WanisidataWJEF_22UNTERWEF22N6153_1 material aoe xr part I2 m rate nose mem 42Mbfree 198Mbtotal queue 0 rs es 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 depend
73. ormed 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 inixi Create Poo ame Auto ross section MT102 Cross section Eta iv MT452 Neutron production Cross section Cross section MT102 Cros s section 41 Note that a computed cross 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 i
74. rgy distribution Fractionnal probability L Partial distrib x frac prob 1 9 3 Angular distributions Angular distributions of secondary particles are given in File 4 of the ENDF format as f u E where p is the cosine of the angle between 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 distributio
75. s 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 S Adiust display properties Eg Plot properties Table properties Name C Manual Auto Parameters M show Y errors Errors drawing mode two lines thickness r Color Swatches HsB RoB Epp a e A A e E a pps E Je r mie tT eee 42 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 EE Janis JEF 2 2 Energy distributions U235 File Tools Selected E Energy distributions Plotter MT 18 z fission total Energy distribution for U235 fr
76. sers 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 features available under JEF PC were reproduced cross section display in pointwise and groupwise format decay data and fission yield d
77. ssion 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 while 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 S Local JEF 2 2 Fission yields data U235 ziBl x File Tools Selected E Fission yields Tabler T Fission data Parent independant fission yields for U235 from JEF 2 2 from Local Thermal 0 0253eV eus Fast 400keV af P at E Xmin 0 19999999999999996 yH High 14MeV s Y Xmax 181 8 0 H t 1 Ymin 5 97711118038046E 11 Ymax 8 931845929232484 00Hf 0 00 T t le 4 E Parent independant fission yields EHS Fast 400ke V Chain mode same 4 Charge mode same Z High 14MeV 9 Chain mode same A Le Charge mode same Z 51 For product nuclides fission products the production yield for different fissioning systems can als
78. 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 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 Local Janis JEF 2 2 Energy distributions U235 o xl File Tools Selected Ex Energy distributions Plotter MT 455 r nubar d Fnergy distribution for U235 from JEF 2 2 from Local Janis X Loa Y flin z I component 2 6 Energy 1 0E 5 component 41 6 Energy 1 0E 5 Xmin oo Xmax 2190000 0 Ymin 5 59583E 31 Ymax 2 95097E 6 More Move Zoom X Secondary eneray x 1e6 2196 BY i Source Settings Display EHS MT 455 z nubar d Energy differential cross section Energy distribution ES component 176 Energy distribution 9 Fractionnal probability Q Partial distrib x trac prob 0 ES component 2 6 Energy distribution Fractionnal probability Partial distrib x trac prob 1 E component 3 6 MOOR BOON BOO 7739 vues v v 4 44 The partial energy distributions might be combined a
79. t I 1 User fois Password fais ss Root folder idatar A 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 four options e Load equivalent to the Menu item Database Load e Connect Disconnect allows choice of the database s used for search operations note that disconnect keep the database entry in the panel Databases so the user does not have to re enter the parameters e Remove disconnect if needed and remove database from panel Databases 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 Databases panel with a red cross icon Use the Remove button folder structure to unload it A green check icon means the database is connected and a black question is displayed during connection 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 6 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 opti
80. tance a user may create a database from all the 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 or directory are selected from a local or network drive using the appropriate buttons 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 dialog allow 20 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 Figure 11 The Tools Import and Tools Import Wizard dialog boxes re Source files pwapesEAF 99V235Wendf Browse Target Type pec x Enter JDBC parameters and files root JDBC Driver oi Embedded con file cCWyBasedbcont ks C Server host l port I User anis Password anis Root folder D Tapes A Format enor J Library Far ba cmn nen 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 dependi
81. 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 control 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 g

JANIS USER'S GUIDE - OECD Nuclear Energy Agency

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