User's Manual - JanLeenKloosterman.nl
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1. 131 091 003 NSLINK NJOY SCALE LINK User s Manual de Leege Delft University of Technology Interfaculty Reactor Institute Reactor Physics Department Mekelweg 15 2629 JB Delft The Netherlands May 1991 IRI 131 091 003 NSLINK NJOY SCALE LINK User s Manual P F A de Leege Delft University of Technology Interfaculty Reactor Institute Reactor Physics Department Mekelweg 15 2629 JB Delft The Netherlands May 1991 PROGRAM ABSTRACT NAME OR DESIGNATION OF PROGRAM NSLINK COMPUTER FOR WHICH THE PROGRAM IS DESIGNED AND OTHER MACHINE PACKAGES AVAILABLE Program name Package ID Orig Computer Test Computer NSLINK DEC VAX 8350 DEC VAXCLUSTER DESCRIPTION OF PROGRAM OR FUNCTION NSLINK NJOY SCALE LINK is a set of computer codes to couple the NJ OY cross section generation code to the SCALE 3 code system using 2 master library format retaining the Nordheim resolved resonance treatment option METHOD OF SOLUTION The following module and codes are included in NSLINK XLACSR This module is a stripped down version of the XLACS 2 code The module passes all 0 resonance parameters as well as the contribution from all other resonances to the group cross sections the contribution from the wings of the 0 resonances the background cross section and possible interference for multilevel Breit Wigner resonance parameters The group cross sections are stor2. 3 221 THERMAL 6 221 THERMAL SCATTERING 0 3 1 TOTAL 32 SCAT 3 18 FIS 3 102 CAPT 3 221 THERMAL 6 221 THERMAL SCATTERING 0 3 1 TOTAL 3 2 SCAT 3 18 FIS 3 102 CAPT 3 221 THERMAL 6 221 THERMAL SCATTERING 22 Appendix E Command file VAX VMS to run MILER SET PROCESS NAME MILERT ASSIGN USER DKB2 LEEGE NSLINK P1 M OUT FOR006 ASSIGN USER DKB2 LEEGE NSLINK MILERT INP FOR005 ASSIGN USER DKB2 LEEGE NSLINK P1 M DAT FOROSO0 MILER output ASSIGN USER DKB2 LEEGE NSLINK P1 GO DAT FORO022 output temperature independent data ASSIGN USER DKB2 LEEGE NSLINK P1 GT DAT FOR023 NJOY output temperature dependent data SET NOON SET DEF LOC DISK local scratch disk RUN DKA2 RFCODE FINE MILER DELETE FORO DAT temporary files Appendix F MILER input file for sample problems 1 and 2 22 23 30 0 90 0 P1 is a parameter which can be used in the VAX VMS operating system P1 is used to create the name of a file 23 Appendix G Command file VAX VMS to run UNITABR SET PROCESS NAME UNITABR ASSIGN USER DKB2 LEEGE NSLINK P1 MM DAT FOR001 output UNITABR ASSIGN USER DKB2 LEEGE NSLINK P1 U INP FOR005 ASSIGN USER DKB2 LEEGE NSLINK P1 U DOUT 006 ASSIGN USER DKB2 LEEGE NSLINK P1 X DAT FORO23 XLACSR output ASSIGN USER DKB2 LEEGE NSLINK P1 M DAT FOR024 MILER
3. IOPT 2 6 no meaning 70 array LORDER NL NFY MATID KMXB and no meaning 71 array MME MMI and MATEL no meaning 73 Only one base temperature The same energy boundaries as in NJOY must be used No built in group structures are available in XLACSR The energy group boundaries are input high to low in eV Appendix B Command file VAX VMS to run NJOY including XLACSR SET PROCESS NAME NJOY87 SET DEF LOC DISK local scratch disk COPY DKB2 LEEGE JEF11 P2 DAT P2 DAT copy input library to scratch ASSIGN USER DKB2 LEEGE JEF11 P2 DAT TAPE20 ASSIGN USER DKB2 LEEGE NSLINK P1 INP FOROO05 ASSIGN USER DKB2 LEEGE NSLINK P1 OUT FORO06 ASSIGN USER DKB2 LEEGE NSLINK P2 GO DAT TAPE26 NJOY output temperature independent data ASSIGN USER DKB2 LEEGE NSLINK P2 GT DAT TAPE27 output temperature dependent data ASSIGN USER P2 DAT 90 ASSIGN USER DKB2 LEEGE NSLINK P2 X DAT FORO097 NJOY XLACSR output ASSIGN USER FORO047 null device SET NOON RUN DKA2 RFCODE FINE NJOY87 DELETE FORO DAT temporary files DELETE TAPE DAT temporary files DELETE P2 DAT copy input library P1 and P2 are parameters which can be used in the VAX VMS operating system P1 and P2 are used to create the name of a file 1 This line can be removed if XLACSR is not used Appendix C NJOY input file for sample problem
4. in AMPX 2 master format is not yet tested in this version of MILER Input specification card 1 NINO is the GENDF input unit for all the temperature independent neutron data including the data for the first or base temperature as used in the Bondarenko resonance treatment The thermal scattering matrices at the first base tempera ture are to be included as well default 21 NINT is the GENDF input unit for all the temperature dependent neutron data including the data for the first or base temperature as used in the Bondarenko resonance treatment The thermal scattering matrices at all temperatures are to be included as well default 22 NOUT1 is the neutron or photon output unit default 23 NOUT2 is the gamma production output unit default 24 NDA is the scratch direct access unit default 90 Input specification card 2 LOPT is the Legendre component of the neutron angular flux to be selected 0 1 default 0 See the examples in Appendix C and D generation of temperature dependent cross sections with NJOY and Appendix E and F use of MILER 5 UNITABR This code is an adapted version of the original UNITAB code which merges selected portions of AMPX master libraries into a new AMPX master library The output file of the XLACSR module AMPX master format is merged with the AMPX master file obtained from MILER NJOY in such a way that group cross sections of the bodies of the 0 resonances in the
5. resolved energy range MT 1022 for fission and 1021 for capture calculated by XLACSR are subtracted from the infinite dilution values of the 1 D group cross sections for fission MT 18 and neutron capture MT 102 The cross sections of the bodies of the resonances MT 1023 for elastic 1022 and 1021 are added separately to the 1 D group cross section arrays MILER output The redundant infinite dilution values of the total cross sections MT 1 the ab sorption cross sections MT 27 and the neutron disappearance cross sections MT 101 values are adjusted the same way as for MT 18 etc The 0 resonance parameters are included in the new AMPX master library In the case of Bondarenko selfshielding data The total cross section values in the 1 D group cross section arrays are copied be fore adjustment and added to the 1 D arrays as well The reaction type identifica tion is MT 2000 The Bondarenko factors and infinite dilution values of the total cross sections MT 1 in the Bondarenko data part of the AMPX master library are copied MT 2000 for special treatment in the BONAMI code The infinite dilution values of the cross sections MT 1 18 and 102 in the Bon darenko data part of the AMPX master library are adjusted in the same way as the cross sections in the 1 D group cross section arrays The input description of the original UNITAB code can be used with the following input data underscored numbers are fixed
6. 0 1 12540E 00 1 09870E 00 1 07220E 00 1 06230E 00 1 05250E 00 1 04270E 00 1 01370E 00 9 92000E 01 9 71000 01 9 50650 01 9 10000E 01 8 76420E 01 8 33680E 01 7 82080E 01 6 25060E 01 5 03230E 01 4 14990E 01 3 57670 01 3 20630E 01 3 01120 01 2 90740 01 2 70520E 01 2 51030E 01 2 27690 01 1 84430E 01 1 52300 01 1 45720E 01 1 11570 01 8 19660 02 6 70000E 02 5 69220E 02 5 00000E 02 4 27550E 02 3 55000E 02 3 06120E 02 2 55000E 02 2 04920 02 1 23960 02 6 32470E 03 2 27690E 03 7 60220 04 20 2 53990E 04 1 00000E 05 T U235 JEF1 1 MATNO 4925 BASE T 293 16K 70 922350 49251002010 71 1 10 2 5 5 00000 73 293 16 T RECONR 20 22 PENDF TAPE FOR 0235 FROM JEF1 1 4925 2 001 0 7 U235 FROM JEF1 1 PROCESSED BY THE NJOY NUCLEAR DATA PROCESSING SYSTEM 0 BROADR 22 23 49253000 0 001 293 16 900 1500 0 UNRESR 420 23 22 4925 330 293 16 900 1500 1 E10 500 1 0 THERMR 0 22 24 0 4925831012210 293 16 900 1500 0 01 3 30 GROUPR 20 24 0 23 4925 10043111 U235 JEF 1 1 1T 1 0 293 16 1 E10 0 10 0 025 0 8203E06 1 4E06 3 3 221 FREE THERMAL 3 251 MUBAR 3 252 XI 3 253 G 3 452 NU 6 6 221 FREE THERMAL 0 0 GROUPR 20 24 0 25 4925 10043331 U235 JEF 1 1 3T 3507 21 293 16 900 1500 1 10 500 1 0 10 0 025 0 8203 06 1 4 06 3 1 TOTAL 3 2 SCAT 3 18 FIS 3 102 CAPT
7. 1 hydrogen in water different temperatures 0 5 RECONR 20 21 PENDF TAPE FOR H1 FROM JEF1 1 40112 001 0 7 H1 FROM JEF1 1 PROCESSED BY THE NJOY NUCLEAR DATA PROCESSING SYSTEM 0 BROADR 21 22 40113000 0 001 293 6 473 6 623 6 0 30 22 24 4001 401183402 222 0 293 6 473 6 623 6 0 01 3 30 GROUPR 20 24 0 23 401110043111 H IN H2O 293 6 1 10 0 10 0 025 0 8203E06 1 40E06 3 3 222 THERMAL 3 251 COS 6 6 222 THERMAL 0 0 GROUPR 20 24 0 25 401110043311 H IN H2O 3T 293 6 473 6 623 6 1 10 0 10 0 025 0 8203E06 1 40 06 3 222 THERMAL SCAT 6 222 THERMAL SCAT 18 0 3 222 THERMAL SCAT 6 222 THERMAL SCAT 0 3 222 THERMAL SCAT 6 222 THERMAL SCAT 19 Appendix D NJOY input file for sample problem 2 Op values U different temperatures 0 5 XLACSR AMPX MASTER SCALE 3 BASE TEMPERATURE 293 16 LANL 187 GROUP SET NUCLIDES FOR LWR ONLY RESONANCE TREATMENT MT 1 2 18 102 1023 1022 1021 IW 2 FISS 1 MAXW 1 11 187 522 2 0 80000 210000 250 0 970290000 3 110000 x 7U 6E12 5 2 00000E 07 1 70000E 07 1 60000E 07 1 50000E 07 1 46400E 07 1 44200E 07 1 42000E 07 1 39400E 07 1 37500E 07 1 35000E 07 1 30000 07 1 20000E 07 1 10000E 07 1 00000E 07 8 82500E 06 7 78800E 06 6 87290E 06 6 06530E 06 5 35260E 06 4 72370E 06 4 16860E 06 3 67880
8. CCC 466 March 1985 July 1986 SCALIAS 3 1 Selected FORTRAN 77 Modules from SCALE 3 1 October 1986 N M Greene private communication November 1988 G C Panini MILER Master Interface Library makER abstract NEA 1198 July 1988 MACHINE REQUIREMENTS XLACSR requires 1600 kbytes MILER 800 kbytes and UNITABR 400 kbytes of core memory a VAX computer Depending the input choice the following scratch disc space is necessary XLACSR 200 kbytes MILER 40 Mbytes and UNITABR 600 kbytes PROGRAMMING LANGUAGE USED FORTRAN 77 OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED VAX VMS 5 3 ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RE STRICTIONS 15 NAME AND ESTABLISHMENT OF AUTHOR P F A de Leege Delft University of Technology Interfaculty Reactor Institute Reactor Physics Department Mekelweg 15 NL 2629 JB The Netherlands Phone 31 15786618 Telefax 4 31 15786422 E mail LEEGEGHDETUDS BITNET or LEEGEGIRI TUDELFT NL 16 MATERIAL AVAILABLE 1T NJOY87 main source FORTRAN XLACSR source FORTRAN MILER extensively revised source FORTRAN UNITABR source FORTRAN BONAMI subroutines BFEDIT CAPY MAST and SELECT source FORTRAN Sample problem 1 input file NJOY87 Sample problem 2 input file NJOY87 including XLACSR Sample problem 1 and 2 input file MILER Sample problem 2 input file UNITABR Sample problem 1 output file NJOY87 Sample problem 2 output fil
9. Coupling information 2 entries 1 NNNC number of nuclides is 1 only one nuclide NCOM number of coupling commands is 2 e Coupling commands 2 lines of 4 entries 2 first line identifier of the nuclide in the new master data set logical unit number of the device containing data from XLACSR 23 identifier of the nuclide in the master data set type of data desired 5555 Nordheim resonance parameters Second ine identifier of the nuclide in the new master data set equal identifier in line 1 logical unit number of the device containing data from MILER 24 identifier of the nuclide in the master data set type of data desired 1111 All neutron data The output file of UNITABR is in AMPX 2 master format and includes Nordheim reso nance parameters or Bondarenko selfshielding parameters and Nordheim resonance parameters Do not use UNITABR to perform other options as described in the UNITAB manual See Appendix G and H for examples of the UNITABR command and input file 6 BONAMI BONAMI is the code which performs the Bondarenko resonance treatment for the nuclides containing Bondarenko selfshielding parameters BONAMI allows the user to specify whether or not the code will iterate to determine the effective oy value from previously shielded total cross sections for all groups and zones in the problem In the non iterative case BONAMI uses the potential scattering cross sections to
10. E 06 3 24650E 06 2 86500E 06 2 52840E 06 2 23130E 06 1 96910E 06 1 73770E 06 1 53350E 06 1 35340E 06 1 19430E 06 1 05400E 06 9 30140E 05 8 20850E 05 7 24400E 05 6 39280E 05 5 64160E 05 4 97870E 05 4 39370E 05 3 87740E 05 3 42180E 05 3 01970E 05 2 66490E 05 2 35180E 05 2 07540E 05 1 83160E 05 1 61630E 05 1 42640E 05 1 25880E 05 1 11090E 05 9 80370E 04 8 65170E 04 7 63510E 04 6 73790E 04 5 94620E 04 5 24750E 04 4 63090E 04 4 08680E 04 3 60660E 04 3 18280E 04 2 80880E 04 2 60580E 04 2 47880E 04 2 18750E 04 1 93050E 04 1 70360E 04 1 50340E 04 1 32680E 04 1 17090E 04 1 03330E 04 9 11880E 03 8 04730E 03 7 10170E 03 6 26730E 03 5 53080E 03 4 88100E 03 4 30740E 03 3 80130E 03 3 35460E 03 2 96040E 03 2 61260E 03 2 30560E 03 2 03470E 03 1 79560E 03 1 58460E 03 1 39840E 03 1 23410E 03 1 08910E 03 9 61120E 02 8 48180E 02 7 48520E 02 6 60570E 02 5 82950E 02 5 14450E 02 4 54000E 02 4 00650E 02 3 53580E 02 3 12030E 02 2 75360E 02 2 43010E 02 2 14450E 02 1 89260E 02 1 67020E 02 1 47390E 02 1 30070E 02 1 14790E 02 1 01300E 02 8 93980E 01 7 88930E 01 6 96230E 01 6 14420E 01 5 42220E 01 4 78510E 01 4 22290E 01 3 72670E 01 3 28880E 01 2 90230E 01 2 56130E 01 2 26030E 01 1 99470E 01 1 76030E 01 1 55350E 01 1 37100E 01 1 20990E 01 1 06770E 01 9 42250E 00 8 31530E 00 7 33820E 00 6 86800E 00 6 47600E 00 5 71500E 00 5 04350E 00 4 45090E 00 3 92790E 00 3 46630E 00 3 05900E 00 2 69960E 00 2 38240E 00 2 10240E 00 1 85540E 00 1 72610E 00 1 59490E 00 1 45740E 00 1 30790E 00 1 16640E 0
11. NITABR code The command and input files NJOY XLACSR MILER and UNITABR are shown in Appendix B D E F G and H respectively UNITABR will generate a file in AMPX master format including Nordheim resonance parameters or Bondarenko selfshield ing parameters and Nordheim resonance parameters Also thermal scattering ma trices at three different temperatures will be included The listings of the printed output files are available on magnetic tape as part of the code package documentation References 1 R E MacFarlane and D W Muir NJOY87 A Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF B Evaluated Nuclear Data PSR 171 Novem ber 1987 SCALE 3 1 A modular Code System for Performing Standardized Computer Analyses for Licensing and Evaluation CCC 466 March 1985 July 1986 SCALIAS 3 1 Selected FORTRAN 77 Modules from SCALE 3 1 CCC 475 Octo ber 1986 Greene et al AMPX A Modular Code System for Generating Coupled Multigroup Neutron Gamma libraries from ENDF B March 1976 Revised to level of AMPX Il ORNL TM 3706 December 1978 GC Panini MILER Master Interface Library makER abstract NEA 1198 July 1988 Greene private communication November 1988 Appendix A Input data XLACSR The XLACS 24 input data can be used with the following comments Data block 3 is not used 2 array IDTAP no meaning 3 array
12. determine the effective c value The iteration starts with the infinite dilution values of the total cross sections of the nu clides With the NSLINK code system a nuclide may contain both Bondarenko self shielding parameters and Nordheim resonance parameters If Nordheim resonance parameters are available the total cross sections MT 1 cannot be used in the itera tive process because these cross sections are adapted for the Nordheim resonance treatment to be performed later Before correction UNITABR copies the infinite dilution values of the total cross sections and Bondarenko factors MT 1 to MT 2000 If the total cross sections MT 2000 are used instead of MT 1 this will be flagged in the printed output of BONAMI If no Nordheim resonance parameters are available the original iterative method is not affected Some revised subroutines are available which replace the original ones in BONAMI to take into account the treatment of the total cross sections in the case of Nordheim resonance parameters There are no changes in the BONAMI input description The presence of the Nordheim resonance parameters in the AMPX master library will be detected by the BONAMI code The original input files for BONAMI can be used 7 Sample Problems Two sample problems are designed to demonstrate the options in the module and codes of NSLINK 1 Example 1 In this example cross sections for hydrogen in water are generated In particular the gen
13. ding parameters and Nordheim resonance parameters the input stream for XLACSR must define the same group structure as for the GROUPR module in NJOY Also the same base first temperature must be selected A value of 10 infinite dilution for c is used 4 MILER The MILER code converts a GENDF data library from NJOY to an AMPX 2 master format Input instructions and definitions used to compute quantities in accordance with the definitions found in AMPX 2 are included as comment lines in the source code of MILER The code is revised extensively and some additions have been made The most important revisions and additions are listed below The use of MT 18 or MT 19 fission reaction type has been included Revisions for the thermal scattering matrices If thermal scattering matrices are available MT 201 230 or 221 236 all elastic scattering matrix elements MT 2 in the thermal range are set to zero because the elastic and thermal scattering matrices are added up in NITAWL The thermal scattering matrices contain some upscattering elements which ex press upscattering to the energy range above thermal This will cause problems in MALOCS and NITAWL The upscattering elements are deleted and the ther mal scattering matrices are renormalized it was found that after running NJOY the resulting library sometimes contains zero cross sections and all zero scattering matrix elements for some MT numbers This causes problems t
14. dix e M 23 Command file VAX VMS to run MILER eH 23 E m M n 23 MILER input file for sample problems 1 2 23 Appendix 24 Command file VAX VMS to run UNITABR 24 Appendix H E 24 UNITABR input file for sample problem 2 24 Appendix em CEDE 25 Contents of tape Figures Figure 1 Flow diagram VPE spe ence pedet ai has 5 1 Introduction The AMPX master library is organized into one and two dimensional arrays by reac tion type scattering expansion order and energy groups Also Bondarenko selfshield ing parameters and Nordheim resonance parameters can be included in the library The master library can be generated with the XLACS and XLACS 2 codes However the fine group cross sections generation code NJOY can treat different ENDF formats such as 4 5 and 6 The code includes more advanced options is well maintained and internationally accepted In order to generate fine group cross sections with the code and to put them in AMPX master library format a set of computer codes named NSLINK NJOY SCALE LINK has been developed In the AMPX master library data is included for further processing according to the Nordheim resonance treatment Bondarenko selfshieldin
15. e NJOY87 including XLACSR Sample problem 1 output file MILER Sample problem 2 output file MILER Sample problem 2 output file UNITABR Sample problem 1 and 2 command file NJOY87 including XLACSR Sample problem 1 and 2 command file MILER Sample problem 2 command file UNITABR CATEGORY B M KEYWORDS cross sections Nordheim resonance treatment data processing libraries multigroup A D Contents Introd cti N s ood cad sat er ey dap x E 4 General remarks spat eed nln iR CI du donee 6 P ecc 7 MLER 8 ENITADEU Iveco hdi opi beo E Ete reb ue eiue OE 11 BONAM MUR ean eee k asas etus pu ene eee 13 Sample Problems oeste dendo ella cea vapeur er eat as 14 References EAE 15 POPC IOP M 16 Input data XLACSR neto etr petu de essais ied eee o REL UH dva Eines 16 Appendix B Mr andes 17 Command file VAX VMS to run NJOY including XLACSR 17 Appendix MM 18 NJOY input file for sample problem 1 hydrogen in water different temperaturas scsi inatenbatianedoetdensderans pan pe NA iut rd 18 Appendix D aoo reddidi ase ER SM REA REO DAP BANK IRE LIN sa d teats 20 NJOY input file for sample problem 2 295U different temperatures and o VIP Ice TH HER 20 Appen
16. ed in the appropriate 1 D cross section arrays The ouput file has AMPX 2 master format The original NJOY code is used to calculate all other data The XLACSR module is included in the NJOY code MILER This code converts NJOY output GENDF format to AMPX 2 master format The code is an extensively revised version of the original MILER code In addition the treatment of thermal scattering matrices at different temperatures is included UNITABR This code is a revised version of the UNITAB code It merges the output of XLACSR and MILER in such a way that contributions from the bodies of the 0 res onances in the resolved energy range calculated by XLACSR are subtracted from the 1 D group cross section arrays for fission MT 18 and neutron capture MT 102 The 1 0 resonance parameters and the contributions from the bodies of these resonances are added separately MT 1023 1022 and 1021 The total cross section MT 1 the ab sorption cross section MT 27 and the neutron disappearance cross section MT 101 values are adjusted In the case of Bondarenko data the infinite dilution values of the cross sections MT 1 18 and 102 are changed in the same way as the 1 D cross sections The output file of UNITABR is in 2 master format and includes Nordheim parameters or Bondarenko and Nordheim parameters for the resonance treatment in BONAMI and or NITAWL which are codes of the SCALE system BONAMI In order to take into account
17. eration of thermal scattering cross sections and matrices is demonstrated at three different temperatures The GROUPR module of NJOY has to be run twice first to generate all temperature independent data and secondly to generate all temperature dependent data The two output files from NJOY GENDF format are input for the temperature independent and temperature dependent part of MILER The command and input files NJOY MILER are shown in Appendix B C E and F respectively MILER will generate a file in AMPX master format including thermal scattering matrices at three different temperatures Example 2 In this example cross sections for 2350 are generated In particular the genera tion of Bondarenko selfshielding parameters is demonstrated with three different values of o and at three different temperatures Thermal scattering cross sections and matrices at three different temperatures are generated as well The tempera ture used in the XLACSR input is equal to the first base temperature as used in the other input of NJOY In both NJOY and XLACSR the energy group structure has to be the same As in example 1 the GROUPR module of NJOY has to be run twice first to generate all temperature independent data and secondly to generate all temperature dependent data The two output files from NJOY in GENDF format are input for the temperature independent and temperature dependent part of MILER The output of MILER and XLACSR is input for the U
18. evel Breit Wigner resonance parameters The group cross sections are stored in the appropriate 1 D cross section arrays MT 1 2 18 102 and the bodies of the reso nances 1021 1022 and 1023 The output file has AMPX 2 master format The original NJOY code is used to calculate all the data The use of XLACSR does not affect the input to NJOY In fact if one does not want to use the Nordheim resonance treatment the present NJOY version can still be used with MILER to convert the out put library of NJOY to the AMPX 2 master format The XLACSR module is included in the NJOY code The module can be used by including the string XLACSR version 87 89 or XLACSR version 89 in the input stream of NJOY The XLACSR input can be put anywhere in the NJOY input stream The XLACS 2 input description see Appendix A can be used for XLACSR Some input parameters have no meaning in the input stream for XLACSR thermal treatment scattering matrices etc The ENDF 4 5 and 6 formats can be used XLACSR uses logical unit numbers in the range 90 thru 99 other logical unit numbers are reserved for other modules in NJOY The JEF or ENDF B input library will be cop ied because of the read write access in FORTRAN 77 After execution this copy will be deleted see Appendix B command file to run NJOY In Appendix D a sample input file for NJOY including the XLACSR input is shown In the case of generating data for a nuclide with Bondarenko selfshiel
19. g parameters can be generated as well Resonance calculations can be done with the Bondarenko Nordheim or Bondarenko and Nordheim resonance treatment using the BONAMI and or NITAWL codes from the SCALE 3 code package The following module and codes are included in the NSLINK package e XLACSR This module part of the NJOY code is a stripped down version of the XLACS 2 code The necessary data for the Nordheim resonance treatment is gen erated by XLACSR MILER This code is an extensively revised version of the original MILER code MILER converts output from NJOY GENDF format to AMPX 2 master format UNITABR This code is an adapted version of the UNITAB code It merges the output of XLACSR and MILER e BONAMI In order to combine Bondarenko and Nordheim resonance treatment some revised subroutines of the BONAMI code are included which replace the original ones NSLINK is part of the INAS IRI NJOY AMPX SCALE computer code package The flow diagram of NSLINK is shown in figure 1 The Netherlands Energy Research Foundation ECN in Petten The Netherlands contributed to the revision of MILER and tested the module and codes as well They make use of NSLINK in the PASC PETTEN AMPX SCALE computer code package Figure 1 Flow diagram of NSLINK Bold indicates NSLINK XLACSR UNITABR AMPX MASTER 2 General remarks The source code of NSLINK is written in FORTRAN 77 some system dependent code i
20. nput output precision of real values etc has been flagged CVAX CIBM etc Changes in the source code made by IRI are flagged CIRI changes made by ECN are flagged CVE or CECN The ENDF 4 5 and 6 formats can be used The NJOY87 or NJOY89 code can be used as well Only one nuclide can be processed per run The AMPX master library is generated in AMPX 2 master format and can only be used by AMPX 2 and SCALE 3 codes NOT SCALE 4 In some codes of AMPX and SCALE the sequence of the treatment of Bondarenko selfshielding parameters and Nordheim resonance parameters is wrong if both are pre sent In the definition of the AMPX master format the Bondarenko selfshielding pa rameters precede the Nordheim resonance parameters In the AMPX utility codes AJAX AIM COMET DIAL MALOCS RADE and UNITAB the treatment of the Nord heim resonance parameters has to be done after the Bondarenko selfshielding pa rameters treatment In most cases this can be easily accomplished by editing the FILE2 subroutine in these codes 3 XLACSR XLACSR is a stripped down version of the XLACS 2 code The module is included to generate the necessary data for the Nordheim resonance treatment in NITAWL XLACSR passes all 0 resonance parameters as well as the contributions from all other resonances to the group cross sections the contribution from the wings of the 0 resonances the background cross sections and possible interference for multi l
21. o the unmodified MILER The modified MILER deletes all the MT numbers with zero cross sections and zero scattering matrix elements The Bondarenko resonance treatment has been corrected The initial setting of the directory for Bondarenko data in the AMPX 2 master is MT is the identifier of the process NF is the number of the first energy group for which parameters are given set to one NL is the last group for which parameters are given set to NMAX the maximum number of groups Ain co operation with the Netherlands Energy Research Foundation in Petten The Netherlands ORDER is used to specify the order of the elastic scattering matrix MT 2 if it is to be self shielded derived from input library OFF is the offset from the magic word in the elastic scattering matrix set to one NZis presently unused and has a value of zero The use of the direct access data file has been changed In the records used all the data is set to zero IBM mainframe computers initialize all the data in the re cords to zero Thermal scattering matrices at different temperatures as defined in the AMPX 2 master format can be included in the AMPX master library Two additional scratch units 15 and 16 are used in this case All these modifications are mainly in subroutines FILE3 FILEST and FILE6 The sub routine FILE6T has been included The gamma production and or photon interaction data conversion from GENDF format
22. output SET DEF LOC DISK local scratch disk SET NOON RUN DKA2 RFCODE UTILJUNITABR DELETE FORO DAT temporary files Appendix H UNITABR input file for sample problem 2 1 12 6 200 880 T 2 92235 23 922350 5555 9223524 49251111 T is a parameter which can be used in the VAX VMS operating system is used to create the name of a file 24 Appendix Contents of tape Characteristics density 6250 bpi ascii nolabel recordformat fixed blocked re cordsize 80 blocksize 3200 output recordsize 133 blocksize 5320 1 2 8 9 NJOY87 main source FORTRAN XLACSR source FORTRAN MILER extensively revised source FORTRAN UNITABR source FORTRAN BONAMI subroutines BFEDIT CAPY MAST and SELECT source FORTRAN Sample problem 1 input file NJOY87 Sample problem 2 input file NJOY87 including XLACSR Sample problem 1 and 2 input file MILER Sample problem 2 input file UNITABR 10 Sample problem 1 output file NJOY87 11 Sample problem 2 output file NJOY87 including XLACSR 12 Sample problem 1 output file MILER 13 Sample problem 2 output file MILER 14 Sample problem 2 output file UNITABR 15 Sample problem 1 and 2 command file NJOY87 including XLACSR 16 Sample problem 1 and 2 command file MILER 17 Sample problem 2 command file UNITABR 25
23. the combination of Bondarenko and Nordheim resonance treatment certain subroutines are included in the package which replace some subroutines in the BONAMI code 10 11 12 13 14 RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM TYPICAL RUNNING TIME A sample problem 2820 with 187 neutron groups and Legendre polynomial order 3 requires on a DEC VAXstation 3100 model 30 for XLACSR 8 minutes MILER 80 seconds and UNITABR 8 seconds UNUSUAL FEATURES OF THE PROGRAM The present version of the code package is designed for the NJOY87 code It can be used with the NJOY89 code as well by a minor change of the main routine of NJOY89 add 5 statements RELATED AND AUXILIARY PROGRAMS AMPX II modules RADE DIAL CHOX AIM etc can be used to check edit couple convert etc the output files Standard AMPX II and NJOY subroutines and functions are widely used in NSLINK STATUS REFERENCES R E MacFarlane and D W Muir NJOY87 A Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF B Evaluated Nuclear Data PSR 171 November 1987 Greene et al A Modular Code System for Generating Coupled Multigroup Neutron Gamma Libraries from ENDF B March 1976 Revised to level of ORNL TM 3706 December 1978 SCALE 3 1 A modular Code System for Performing Standardized Computer Analyses for Licensing and Evaluation
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