Aareadme_trae.txt Prepared by A.B. Pashchenko, H. Wienke and S. Ganesan*), February 1996. *) S. Ganesan, present address: Neutron Physics Division, Bhabha Atomic Research Centre, Trombay, Bombay-400 085 email:ganesan@magnum.barct1.ernet.in 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 1.1, November 1994 The subdirectory [FENDL.TRANSPORT.FENDLE] contains the library FENDL/E-1.1 of basic evaluations of neutron interaction, neutron induced photon production, and photon-atom interaction cross sections for use in neutron- photon transport calculations (Ref. 1). In this subdirectory nuclear data files of each of the isotopes have been identified individually with names such as: "SI000BR.DAT" for the data of Sn-nat from BROND-2, "NI058E6.DAT" for the data of Ni-58 from ENDF/B-VI.x, "BI209J3.DAT" for the data of Bi-209 from JENDL-3.1. The atomic number is always written with three digits, starting with a '0' when it is smaller than 100 and '00' when smaller than 10. Evaluated nuclear data files: BROND-2: BROND library, version 2 contributed by the Russian Federation, in ENDF-6 format, see document IAEA-NDS-90 (Ref. 2). ENDF/B-VI.x: ENDF/B library, version VI, revision x, contributed by the U.S.A, in ENDF-6 format, see document IAEA-NDS-100 (Ref. 3). Note that revision x is the revision number of the given material, not of the library. JENDL-3.1: JENDL library, version 3.1 contributed by Japan, in ENDF-5 format, see document IAEA-NDS-110 (Ref. 4). The list of FENDL/E-1.1 evaluations for neutron interaction cross sections and neutron induced photon production cross sections is given in Appendix 1. All the photon-atom interaction cross section data have been extracted from a single source, ENDF/B-VI, and are available in one single file with the name FENDLEP.DAT". A list of the evaluations is given in Appendix 2. The evaluated cross section data of FENDL/E-1.1 have been processed by R.E. MacFarlane using his nuclear data processing system NJOY, version 91, developed at Los Alamos National Laboratory, USA (ref. 5). The processed data are presented in the sublibraries FENDL/MG-1.1 (ref. 6) and FENDL/MC-1.1 (ref.7). Note: FENDL/E-1.1 was frozen as of the end of March 1995. However the data files fendlep.dat and be009e6.dat, which have been found to be erroneous and incomplete respectively (erroneous h1 data and incomplete Be-9 data reported by Dr. C. Konno, JAERI, Japan) have been corrected ( October 1995) and replaced (November 1995) respectively. Furthermore the following erroneous file names have been corrected ( erroneous data-file names reported by D.W. Muir, LANL USA, August 1995): previous file name corrected file name v055e6.dat ---> v000e6.dat p000e6.dat ---> p031e6.dat The data files n14br.dat, and n15br.dat have been renamed as n014br.dat and n015br.dat, according to the file naming rules, and the previous datafile n015br.dat has been removed as it is superseded. The Zirconium data files also have been renamed according to the file naming rules. References: 1. A.B. Pashchenko, H. Wienke, S. Ganesan and P.K. McLaughlin, "FENDL/E, Evaluated Nuclear Data Library of Neutron Interaction Cross Sections, Photon Production Cross Sections and Photon-Atom Interaction Cross Sections for Fusion Applications, version 1.1 of November 1994", IAEA(NDS)-128, Rev. 3 (February 1996) 2. 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) 3. 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, New York, 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) 4. K. Shibata et al., "Japanese Evaluated Nuclear Data Library", Version 3, JENDL-3, JAERI-1319 (1990), IAEA(NDS)-110, Rev. 4. (June 1992) 5. R.E. MacFarlane, "The NJOY Nuclear Data Processing System, Version 91", Los Alamos National Laboratory report LA-12740-M (1994). 6. R.E. MacFarlane, "FENDL/MG, Library of multigroup cross sections in GENDF and MATXS format for neutron-photon transport calculations, version 1.1 of March 1995". Summary documentation A.B. Pashchenko, H. Wienke and S. Ganesan, report IAEA-NDS-169, Rev. 3 (International Atomic Energy Agency, February 1996). 7. R.E. MacFarlane, "FENDL/MC, Library of cross sections in continuous energy ACE format for neutron-photon transport calculations with the Monte Carlo particle Transport Code system MCNP-4A, version 1.1 of March 1995". Summary documentation A.B. Pashchenko, H. Wienke and S. Ganesan, report IAEA-NDS-169, Rev. 3 (International Atomic Energy Agency, February 1996). New naming conventions of readme files. --------------------------------------- The following conventions are used as substitute for the numerous readme files with the SAME name (aareadme.txt) in the FENDL directory tree. For the record, according to J.White, RSIC, four levels of consideration are used in determining a short extension of 'aareadme' following underscore (aareadme_/*/*/*/*.txt). The levels are: /type of data/primary format description/secondary description/other. The first three characters of the directory name was used to define the data type. About the file extension we have agreed on txt. In an arrangement close to the directory tree blocks, the new name extensions are: ACTIVATION - ACT ACTPMC ACTE ACTPVE ACTP ACTPFL DECAY - DEC DECE DOSIMETRY - DOS DOSE FUSION - FUS FUSE FUSP TRANSPORT - TRA TRAE TRAP TRAPMC TRAPMG ----------------------------------------------------------- LEGEND: E, evaluated data or data in "ENDF-like" format P, processed data ******************************************************************************* For any clarifications/suggestions, please contact A.B.Pashchenko or H.Wienke, Nuclear Data Section, Division of Physical and Chemical Sciences Wagramer Strasse 5, P.O.Box 100, International Atomic Energy Agency, Vienna, A-1400 AUSTRIA (Telex: +43-1-12645; Fax: +43-1-20607; Phone: 0043-1-2060-21708 or 21714 E-Mail: INTERNET: PASHCHENKO@IAEAND.IAEA.OR.AT or WIENKE@IAEAND.IAEA.OR.AT ******************************************************************************* Appendix 1: List of FENDL/E-1.0 Evaluations for neutron interaction and ********** photon production cross sections. MATERIAL LIBRARY MAT Number File name in online system H-1 ENDF/B-VI.1 125 H001E6.DAT H-2 BROND-2 102 not present*) H-3 ENDF/B-VI.0 131 H003E6.DAT Li-6 ENDF/B-VI.1 325 LI006E6.DAT Li-7 ENDF/B-VI.0 328 LI007E6.DAT Be-9 ENDF/B-VI.0 425 BE009E6.DAT B-10 ENDF/B-VI.1 525 BE010E6.DAT B-11 ENDF/B-VI.0 528 BE011E6.DAT C-Nat ENDF/B-VI.1 600 C000E6.DAT N-14 BROND-2 710 N014BR.DAT N-15 BROND-2.1 720 N015BR.DAT O-16 ENDF/B-VI.0 825 O016E6.DAT F-19 ENDF/B-VI.0 925 F019E6.DAT Na-23 JENDL-3.1 3111 NA023J3.DAT Mg-Nat JENDL-3.1 3120 MG000J3.DAT Al-27 JENDL-3.1 3131 AL027J3.DAT Si-Nat BROND-2 1402 SI000BR.DAT P-31 ENDF/B-VI.0 1525 P031E6.DAT S-Nat ENDF/B-VI.0 1600 S000E6.DAT Cl-Nat ENDF/B-VI.0 1700 CL000E6.DAT K-Nat ENDF/B-VI.0 1900 K000E6.DAT Ca-Nat JENDL-3.1 3200 CA000J3.DAT Ti-Nat JENDL-3.1 3220 TI000J3.DAT V-Nat ENDF/B-VI.0 2300 V000E6.DAT Cr-50 ENDF/B-VI.1 2425 CR050E6.DAT Cr-52 ENDF/B-VI.1 2431 CR052E6.DAT Cr-53 ENDF/B-VI.1 2434 CR053E6.DAT Cr-54 ENDF/B-VI.1 2437 CR054E6.DAT Mn-55 ENDF/B-VI.0 2525 MN055E6.DAT (JENDL-3.1) 3251 MN055J3.DAT Fe-54 ENDF/B-VI.1 2625 FE054E6.DAT Fe-56 ENDF/B-VI.1 2631 FE056E6.DAT Fe-57 ENDF/B-VI.1 2634 FE057E6.DAT Fe-58 ENDF/B-VI.1 2637 FE058E6.DAT Co-59 ENDF/B-VI.2 2725 CO059E6.DAT Ni-58 ENDF/B-VI.1 2825 NI058E6.DAT Ni-60 ENDF/B-VI.1 2831 NI060E6.DAT Ni-61 ENDF/B-VI.0 2834 NI061E6.DAT Ni-62 ENDF/B-VI.1 2837 NI062E6.DAT Ni-64 ENDF/B-VI.1 2843 NI064E6.DAT Cu-63 ENDF/B-VI.2 2925 CU-63E6.DAT Cu-65 ENDF/B-VI.2 2931 CU065E6.DAT Zr-90 BROND-2 4090 ZR090BR.DAT Zr-91 BROND-2 4091 ZR091BR.DAT Zr-92 BROND-2 4092 ZR092BR.DAT Zr-94 BROND-2 4094 ZR094BR.DAT Zr-96 BROND-2 4096 ZR096BR.DAT Nb-93 BROND-2 4193 not present Mo-Nat JENDL-3.1 3420 MO000J3.DAT Sn-Nat BROND-2 5000 not present Ba-134 ENDF/B-VI.0 5637 not present**) Ba-135 ENDF/B-VI.0 5640 not present**) Ba-136 ENDF/B-VI.0 5643 not present**) Ba-137 ENDF/B-VI.0 5646 not present**) Ba-138 ENDF/B-VI.0 5649 not present**) Ta-181 JENDL-3.1 3731 TA181J3.DAT W-182 ENDF/B-VI.0 7431 W182E6.DAT W-183 ENDF/B-VI.0 7434 W183E6.DAT W-184 ENDF/B-VI.0 7437 W184E6.DAT W-186 ENDF/B-VI.0 7443 W186E6.DAT Pb-206 ENDF/B-VI.0 8231 PB206E6.DAT Pb-207 ENDF/B-VI.1 8234 PB207E6.DAT Pb-208 ENDF/B-VI.0 8237 PB208E6.DAT Bi-209 JENDL-3.1 3831 BI209J3.DAT *) See p.25 of INDC(NDS)-312 [Ref. 5] and remarks in IAEA-NDS-169 [Ref.6] **) See p.25 of INDC(NDS)-312 [Ref. 5]. Appendix 2: List of FENDL/E-1.0 evaluations for photon-atom interaction. Note, all these evaluations have been drawn from ENDF/B-VI. MATERIAL MAT Number AL 1300 B 500 BA 5600 BE 400 BI 8300 C 600 CA 2000 CL 1700 CO 2700 CR 2400 CU 2900 F 900 FE 2600 H 100 K 1900 LI 300 MG 1200 MN 2500 MO 4200 N 700 NA 1100 NB 4100 NI 2800 O 800 P 1500 PB 8200 S 1600 SI 1400 SN 5000 TA 7300 TI 2200 V 2300 W 7400 ZR 4000