INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR DATA SERVICES DOCUMENTATION SERIES OF THE IAEA NUCLEAR DATA SECTION IAEA-NDS-128 Rev. 0, February 1994 FENDL/E Evaluated nuclear data library of neutron nuclear interaction cross-sections and photon production cross-sections and photon-atom interaction cross sections for fusion applications Version 1.0 of February 1994 Prepared by S. Ganesan and P.K. McLaughlin Abstract: This document presents the description of a physical tape or diskette containing the basic evaluated nuclear data library of neutron nuclear interaction cross-sections and photon production cross-sections and photon-atom interaction cross-sections for fusion applications. It is part of FENDL, the evaluated nuclear data library for fusion applications. The nuclear data are available cost-free for distribution to interested scientists upon request. The data can also be retrieved by the user via online access through international computer networks. Nuclear Data Section e-mail: RNDS@IAEA1, BITNET International Atomic Energy Agency fax: (43-1) 234564 P.O. Box 100 cable: INATOM VIENNA A-1400 Vienna telex: 1-12645 atom a Austria telephone: (43-1) 2360-1709 NDIS online, TELNET: IAEAND.IAEA.OR.AT username: IAEANDS FENDL/E Evaluated nuclear data library of neutron nuclear interaction cross-sections and photon production cross-sections and photon-atom interaction cross-sections for fusion applications Version 1.0 of February 1994 FENDL/E is sub-library of FENDL, the evaluated nuclear data library for fusion applications. This note presents a documentation of a physical tape or diskette containing the FENDL/E-1.0 materials library i.e., FENDL/E library,Version 1.0 of February 1994 following the recommendation of an IAEA Advisory Group Meeting "Review of Uncertainty Files and Improved Multigroup Cross Section Files for FENDL," held in cooperation with the Japan Atomic Energy Research Institute, Tokai Research Establishment, JAERI, Japan, 8-12 November 1993, report INDC(NDS)-297 (Ref. 1) A brief account of the background information on FENDL is presented in the appendix to this document. The selection criteria, following Ref. 1, for consideration for inclusion of a basic evaluated data file in FENDL/E are also presented in the appendix. The nuclear data comprising FENDL/E described in this documentation are in the form of basic evaluated data files with resonance parameters etc., where appropriate. The processing of the data files into multigroup cross sections and into point files compatible with Monte Carlo codes are being carried out by R.E. MacFarlane and will be made available by the NDS separately. The FENDL/E-1.0 Evaluations for photon-atom interaction are all taken from ENDF/B-VI photon-atom interaction Library, see report IAEA-NDS-58 Rev.2 (Ref. 2). Table 1 List of FENDL/E-1.0 Evaluations for neutron interaction and photon production MATERIAL LIBRARY MAT Number Number of records H-1 ENDF/B-VI.1 125 2117 H-2 BROND-2 102 Not yet released H-3 ENDF/B-VI.0 131 732 Li-6 ENDF/B-VI.1 325 2621 Li-7 ENDF/B-VI.0 328 4945 Be-9 ENDF/B-VI.0 425 13909 B-10 ENDF/B-VI.1 525 4594 B-11 ENDF/B-VI.0 528 8531 C-Nat ENDF/B-VI.1 600 3518 N-14 BROND-2 710 Not yet released N-15 BROND-2 720 4295 O-16 ENDF/B-VI.0 825 8539 F-19 ENDF/B-VI.0 925 9485 Na-23 JENDL-3.1 3111 4711 Mg-Nat JENDL-3.1 3120 4254 Al-27 JENDL-3.1 3131 4984 Si-Nat BROND-2 1402 6780 P-31 ENDF/B-VI.0 1525 848 S-Nat ENDF/B-VI.0 1600 4594 Cl-Nat ENDF/B-VI.0 1700 4269 K-Nat ENDF/B-VI.0 1900 3727 Ca-Nat JENDL-3.1 3200 5260 Ti-Nat JENDL-3.1 3220 5243 V-Nat ENDF/B-VI.0 2300 6542 Cr-50 ENDF/B-VI.1 2425 6807 Cr-52 ENDF/B-VI.1 2431 8492 Cr-53 ENDF/B-VI.1 2434 8520 Cr-54 ENDF/B-VI.1 2437 5513 Mn-55 ENDF/B-VI.0 2525 17970 (JENDL-3.1) 3251 20463 Fe-54 ENDF/B-VI.1 2625 7992 Fe-56 ENDF/B-VI.1 2631 16865 Fe-57 ENDF/B-VI.1 2634 11156 Fe-58 ENDF/B-VI.1 2637 7404 Co-59 ENDF/B-VI.2 2725 7878 Ni-58 ENDF/B-VI.1 2825 9956 Ni-60 ENDF/B-VI.1 2831 6716 Ni-61 ENDF/B-VI.0 2834 6984 Ni-62 ENDF/B-VI.1 2837 5739 Table 1 List of FENDL/E-1.0 Evaluations (continued) MATERIAL LIBRARY MAT Number Number of records Ni-64 ENDF/B-VI.1 2843 5100 Cu-63 ENDF/B-VI.2 2925 9460 Cu-65 ENDF/B-VI.2 2931 7943 Zr-90 BROND-2 4090 Not yet released Zr-91 BROND-2 4091 Not yet released Zr-92 BROND-2 4092 Not yet released Zr-94 BROND-2 4094 Not yet released Zr-96 BROND-2 4096 Not yet released Nb-93 BROND-2 4193 Not yet released Mo-Nat JENDL-3.1 3420 8918 Sn-Nat BROND-2 5000 Not yet released Ba-134 ENDF/B-VI.0 5637 Not yet released Ba-135 ENDF/B-VI.0 5640 Not yet released Ba-136 ENDF/B-VI.0 5643 Not yet released Ba-137 ENDF/B-VI.0 5646 Not yet released Ba-138 ENDF/B-VI.0 5649 Not yet released Ta-181 JENDL-3.1 3731 4617 W-182 ENDF/B-VI.0 7431 4595 W-183 ENDF/B-VI.0 7434 4553 W-184 ENDF/B-VI.0 7437 4487 W-186 ENDF/B-VI.0 7443 4693 Pb-206 ENDF/B-VI.0 8231 8050 Pb-207 ENDF/B-VI.1 8234 8046 Pb-208 ENDF/B-VI.0 8237 5520 Bi-209 JENDL-3.1 3831 4227 Explanations for Table 1: Evaluated nuclear data files: BROND-2: BROND file version 2 contributed by the Russian Federation, see document IAEA-NDS-90 Rev. 7. (Ref. 3) ENDF/B-VI.x: ENDF/B file version VI, revision x contributed by the U.S.A. see document IAEA-NDS-100 Rev. 5. (Ref. 4). Note that revison x is the revision number of the given material, not of the library. JENDL-3.1: JENDL file version 3.1 contributed by Japan. see document IAEA-NDS-110 Rev. 4. (Ref. 5) BROND-2 and ENDF/B-VI are in ENDF-6 format. See document IAEA-NDS-76 Rev. 4. (Ref 6) JENDL-3.1 is in ENDF/B-5 format. See document IAEA-NDS-75 Rev. 1. (Ref. 7) Table 2 List of FENDL/E-1.0 Evaluations for photon-atom interaction taken from ENDF/B-VI photon-atom interaction Library Material Mat.No No.Records AL000 1300 1610 B000 500 1277 BA000 5600 2311 BE000 400 883 BI000 8300 2836 C000 600 1198 CA000 2000 1629 CL000 1700 1599 CO000 2700 1904 CR000 2400 1838 CU000 2900 1737 F000 900 1263 FE000 2600 1845 H000 125 670 K000 1900 1635 LI000 300 911 MG000 1200 1309 MN000 2500 1882 MO000 4200 2118 N000 700 1292 NA000 1100 1368 NB000 4100 2184 NI000 2800 1870 O000 800 1207 P000 1500 1576 PB000 8200 2840 S000 1600 1573 SI000 1400 1607 SN000 5000 2327 TA000 7300 2652 TI000 2200 1882 V000 2300 1882 W000 7400 2668 ZR000 4000 2190 The data can be accessed by the user via online access through international computer networks as described below. In the NDS open area 'FENDL', a subdirectory "FENDLE" has been created. This open area has been set exclusively for FENDL and will be independent of the presently available open area 'SCR' of the NDS. In the subdirectory FENDLE, nuclear data files of each of the isotopes/elements have been identified individually with names such as: "Bi209j3.dat" for the data of Bi-209 from JENDL-3.1 "SnNatBR.dat" for the data of Sn-Nat from BROND-2. "Ba134e6.dat" for the data of Ba-134 from ENDF/B-VI.0, etc. All the photon-atom interaction cross section files are drawn from a single source, ENDF/B-VI and are available in one single file in FENDLE subdirectory with the name FENDLEP.dat". FILE TRANSFER via INTERNET ========================== FTP (File Transfer Protocol) for foreign hosts: TYPE: ftp IAEAND.IAEA.OR.AT OR ftp 161.5.2.2 GIVES PROMPT: FOR UNIX - name (source-host-ip-address: username at host site): ======== TO WHICH YOU ANSWER: FENDL YOU ARE NOW IN THE OPEN AREA 'FENDL' THE FENDL/E-1.0 DATA ARE IN SUBDIRECTORY "FENDLE" TO ACCESS THE FILES TYPE: set def [.SUB DIRECTORY NAME] i.e. [FENDLE] TO LIST FILES TYPE: 1s -1 TO COPY FILES, TYPE mget *.datTHIS IS A MULTIPLE COPY COMMAND WHICH WILL PROMPT FOR EACH FILE TO BE COPIED (Y/N) TO END SESSION, TYPE "bye" FOR MULTINET IAEAND.IAEA.OR.AT> =============================== TO WHICH YOU ANSWER: login FENDL OR user FENDL YOU ARE NOW IN THE OPEN AREA THE FENDLE DATA ARE IN SUBDIRECTORY [FENDLE] TO ACCESS THE FILES TYPE: set def [.SUB DIRECTORY NAME] i.e. [FENDLE] TO LIST FILES IN THE OPEN AREA, TYPE: dir OR ls TO COPY FILES, TYPE mget *.datTHIS IS A MULTIPLE COPY COMMAND WHICH WILL PROMPT FOR EACH FILE TO BE COPIED (Y/N) TO END SESSION, TYPE "bye" Appendix: Background information The IAEA Nuclear Data Section, in co-operation with several national nuclear data centers and research groups, is creating an internationally available Fusion Evaluated Nuclear Data Library (FENDL), which will serve as a comprehensive source of processed and tested nuclear data tailored to the requirements of the Engineering and Development Activities (EDA) of the International Thermonuclear Experimental Reactor (ITER) Project and other fusion-related development projects. The FENDL project of the International Atomic Energy Agency has the task of coordination with the goal of assembling, processing and testing a comprehensive, fusion-relevant Fusion Evaluated Nuclear Data Library with unrestricted international distribution. The IAEA sponsored international comparison of benchmark measurements and calculations in the subject of fusion neutronics is a sub-task of the FENDL activity. The working nuclear data libraries for neutron and photon transport in processed form for use by the ITER team in the early phase of ITER EDA are being derived by R.E. MacFarlane, Los Alamos National Laboratory, USA by processing the basic data libraries of the first version of FENDL, FENDL-1 using the NJOY code system. The integral validation of FENDL-1 based on analysis of IAEA benchmarks which assumes high priority will be discussed at the planned Advisory Group Meeting in Garching in September 1994. The plans and initiation of selections of basic nuclear data evaluations for FENDL-2 which will be a significant improvement over FENDL-1 will also be performed at the meeting in Garching. The well tested and validated nuclear data libraries in processed form are expected to be ready by mid 1996 for use by the ITER team in the final phase of ITER EDA, after iterative feedback to the evaluators through extensive benchmarking and integral validation studies of FENDL-2 in 1994-96 period. This document describes the contents of the FENDL/E-1.0 library. The requirements and procedures for the FENDL/E-2.0 evaluations which will be a significant improvement over FENDL/E-1.0 are as follows: The following information is required for all candidate files: Gamma-ray production Neutron and charged-particle emission in File 6 format File 1 descriptive information Recoil distributions in File 6 format for major structural materials Energy balance must be better than 2% at all energies The following additional recommendations are made: Simplified File 6 recoil distributions are recommended for other materials. Inclusion of uncertainty information is strongly encouraged. Use of Standard Reference Data such as IRDF 90.2 dosimetry cross sections in candidate files is highly recommended. It is recommended that single isotopic evaluations within a given material be replaced only if the combination is shown to be consistent with the natural element experimental data for the material. Following recommendations presented in Ref. 1, adopted are the following nomenclature for naming the various FENDL nuclear data libraries, in order to avoid confusion and allow precise reference to the various libraries: FENDL/E General Purpose Evaluation Library (This report) FENDL/A Activation Library (Ref.9) FENDL/DS Dosimetry Library (Ref. 8) FENDL/D Decay Data Library (Ref.9) FENDL/C Incident Charged-Particle Library (Ref. 10) FENDL/MC Processed Monte Carlo Library (Ref. 11) FENDL/MG Processed Multigroup Library (Ref .11) FENDL/U Processed Uncertainty Library (Not available at present) References: 1. S. Ganesan (Compiler) "Review of Uncertainty Files and Improved Multigroup Cross Section Files for FENDL," Summary report of an IAEA Advisory Group Meeting held in cooperation with the Japan Atomic Energy Research Institute, Tokai Research Establishment, JAERI, Japan, 8-12 November 1993, INDC(NDS)-297 (January 1994). 2. D.E. Cullen et al., "Tables of Graphs of Photon-Interaction Cross Sections from 10 eV to 100 GeV derived from the LLNL Evaluated Photon Data Library (EDPL)," UCRL-50400, Vol. 6, Parts A & B, Rev. 4, October 1989, Lawrence Livermore National Laboratory. See also the IAEA documentation for distribution of this data: H.D. Lemmel, "ENDF/B-6 Photon Atomic Interaction Data Library," IAEA-NDS-58, Rev.2, September 1990. 3. V.N. Manokhin et al.,"BROND-2.2 Russian Evaluated Neutron Reaction Data Library Summary documentation, H.D. Lemmel and P.K. McLaughlin, IAEA- NDS-90 Rev. 8. (January 1994) 4. P.F. Rose (Editor), "ENDF-6 summary documentation," 4th Edition of BNL- NCS-17541(=ENDF-201) ( October 1991). US National Nuclear Data Center, Brookhaven National Laboratory, Upton, Newyork, USA, The IAEA documentation is presented in "ENDF-6 The U.S. Evaluated Nuclear data Library for Neutron Reaction data by the US National Nuclear Data Center-including revisions up to June 1993," IAEA-NDS-100, Rev. 5 (November 1993) 5. K. Shibata et al., "Japanese Evaluated Nuclear Data Library, Version 3, JENDL-3, JAERI-1319 (1990), IAEA Nuclear Data Services documentation, IAEA-NDS-110, Rev. 4. (June 1992) 6. P.F. Rose and C. L. Dunford, ENDF-102, Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6," US National Nuclear Data Center, Brookhaven National Laboratory, Upton, Newyork, USA, BNL-NCS- 44945( October 1991). The IAEA documentation is presented in "ENDF-6 Formats manual," IAEA-NDS-76, Rev .4 (January 1992) 7. R. Kinsey and B.A. Magurno, "ENDF-5 Formats manual," (1984) IAEA nuclear dataservices documentation, IAEA-NDS-75, Rev. 1 (September 1986) 8. N.P. Kocherov and P.K. McLaughlin (Compilers), "The International Reactor Dosimetry File (IRDF-90 Version 2), IAEA-ND-141, Rev. 2, October 1993. 9. A.B. Pashchenko and P.K. McLaughlin (Compilers), "JONACS, Joint Neutron Activation Cross sections Data Library," IAEA-NDS- note under preparation. 10. A.B. Pashchenko (Compiler), "Summary report of the IAEA Consultants Meeting on "Charged Particle and Photonuclear Data Libraries for FENDL," Report INDC(NDS)-268 (January 1993) 11. R.E. MacFarlane, Private communication. The multigroup cross section files are being generated by R.E. MacFarlane by processing the FENDL/E- 1.0 library using the NJOY code system. As recommended at the IAEA AGM on "Review of Uncertainty Files and Improved Multigroup Cross Section Files for FENDL," (Ref. 1), the evaluations should be cleared by the standard ENDF checking codes and subsequently processable in a physically consistent manner by the NJOY code system providing a check at a higherphysics level. Following this criterion, at this time of writing this document, the Zr isotopes of BROND are under revision (A. BLOKHIN, Private Communication). The Obninsk team has indicated that the following isotopes of BROND are under revision. H-2, N-14, Zr-90, 91, 92, 94, 96 and Nb-93. The isotopes of Barium, viz. Ba-134, 135, 136, 137, 138 from ENDF/B-VI, adopted for FENDL/E-1 again need re- examination as they are available as fission product data without photon production cross sections except for Ba-138.