Aareadme_acte.txt Prepared by A.B.Pashchenko Rev.4 by A.B.Pashchenko and H.Wienke, February 1996. FENDL/PA Neutron Activation Cross-Section Data Library for Fusion Applications Version 1.1 of April 1993 1.Summary of Contents The subdirectory [FENDL.ACTIVATION.FENDLA] contains the FENDL/PA library, version 1.1 of April 1993, of pointwise cross section data, selected from different available sources for stable and unstable target nuclides with half-lives longer than 1/2 day. This library includes 636 target nuclides with about 11.000 reactions with non-zero cross sections below 20 MeV. It should be emphasized that in assembling this library, no additional evaluation work was performed in order to improve evaluations; only existing evaluations were considered for inclusion. Therefore, in many cases the data given are theoretical estimates without experimental verification so that the data uncertainty may be significantly lower than for those evolved from careful evaluation. 2. Format The format of the FENDL/PA file is essentially that of an MF-3 file of ENDF-6 format with the following deviations: (a) If a reaction produces isomers the cross sections for the ground- and isomer-state are given separately. (b) The material number MAT consists of Z and two last digits of A. To describe metastable targets MAT has been increased by 50 or 70 (m1 or m2, respectively). For example, for stable and m1 metastable target nucleus 67-Ho-166 the material numbers are MAT=6766 and MAT=6816, respectively. For stable and m2 metastable target nucleus 65-Tb-156 the material numbers are MAT=6556 and 6626, respectively. Consequently, the order of the target nuclides (according to increasing MAT numbers) is not always in accordance with the increasing Z and A. (c) The reaction nomenclature is that of ENDF format, except that reaction numbers leading to metastable states have been increased by 300 and 600 (for m1 and m2, respectively). In case the isomer production data are included the standard ENDF format notation for the same reaction gives cross sections for production of the ground state (not total 'm+g' but simply 'g'). The MT numbers which occur are listed below. MT Reaction*) MT Reaction 4 = (n,n) 304 = (n,n)* 1st isomer production 16 = (n,2n) 316 = (n,2n)* 1t isomer production 616 = (n,2n)# 2nd isomer production 17 = (n,3n) 317 = (n,3n)* 1st isomer production 22 = (n,na) 322 = (n,na)* 1st isomer production 622 = (n,na)# 2nd isomer production 28 = (n,np) 328 = (n,np)* 1st isomer production 628 = (n,np)# 2nd isomer production 32 = (n,nd) 33 = (n,nt) 34 = (n,nHe3) 102 = (n,g) 402 = (n,g)* 1st isomer production 702 = (n,g)# 2nd isomer production 103 = (n,p) 403 = (n,p)* 1st isomer production 703 = (n,p)# 2nd isomer production 104 = (n,d) 404 = (n,d)* 1st isomer production 704 = (n,d)# 2nd isomer production 105 = (n,t) 106 = (n,He3) 107 = (n,a) 407 = (n,a)* 1st isomer production 707 = (n,a)# 2nd isomer production 111 = (n,2p) *) The MT numbers in the left side column identify the total cross sections of indicated reactions in case when the isomer production data are not included, or the ground state production cross sections in case of residual nuclides with isomer(s). The cross sections for one material number are ordered according to increasing MT numbers; 3. Data files The target nuclides included are given in FENDLA.INDEX file. Because of the huge size of the library the file was divided into 9 subfiles of a convenient size adequate for FTP transfer : FENDLA1.DAT Isotopes of 1-H-1 to 26-Fe-56 FENDLA2.DAT Isotopes of 26-Fe-57 to 31-Ga-66 FENDLA3.DAT Isotopes of 31-Ga-67 to 42-Mo-97 FENDLA4.DAT Isotopes of 42-Mo-98 to 50-Sn-113 FENDLA5.DAT Isotopes of 50-Sn-114 to 54-Xe-133 FENDLA6.DAT Isotopes of 54-Xe-134 to 63-Eu-152 FENDLA7.DAT Isotopes of 63-Eu-153 to 70-Yb-171 FENDLA8.DAT Isotopes of 70-Yb-172 to 76-Os-190 FENDLA9.DAT Isotopes of 76-Os-191 to 84-Po-210 The basic pointwise data library has a size of 75 Megabytes, i.e. 146265 blocks (1 block = 512 bytes). 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 *******************************************************************************