To submit a request, click below on the link of the version you wish to order. Rules for end-users are available here.
Program name | Package id | Status | Status date |
---|---|---|---|
ZZ-IRAN-LIB | IAEA1215/01 | Tested | 11-JAN-1991 |
Machines used:
Package ID | Orig. computer | Test computer |
---|---|---|
IAEA1215/01 | IBM PC | IBM PC |
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
FORMAT: ANISN/PC
NUMBER OF GROUPS: IRAN1.LIB (22 neutrons, 18 gammas);
IRAN2.LIB (17 neutrons, 18 gammas);
IRAN3.LIB (7 neutrons, 18 gammas);
IRAN4.LIB (7 neutrons, 6 gammas);
IRAN5.LIB (5 neutrons, 4 gammas);
IRAN6.LIB (2 neutrons, 4 gammas).
NUCLIDES: 1H, 2H, 6Li, 7Li, 9Be, 10B, 12C, 14N, 16O, Na, Mg, 27Al, Si, K, V, Cr, 55Mn, Fe, Ni, 93Nb, Pb, 235U, 238U, 239PU, 134Ba, 135Ba, 136Ba, 137Ba, 140Ba, 209Bi, natCa, natZr, natCd.
ORIGIN: VITAMIN-4C; ENDF/B-IV and V, and JENDL-3.
WEIGHTING SPECTRUM:
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
IRAN.LIB's data (microscopic cross sections) is suitable for neutron, gamma and coupled neutron- gamma transport calculation (shielding). It is intended for use by the multigroup discrete ordinates code ANISN/PC (CCC-0514) using anisotropic scattering by Legendre expansion up to order P-3. IRAN.LIB is a collection of libraries for elements (1H, 2H, 6Li, 7Li, 9Be, 10B, 12C, 14N, 16O, Na, Mg, 27Al, Si, K, V, Cr, 55Mn, Fe, Ni, 93Nb, Pb, 235U, 238U, 239PU, 134Ba, 135Ba, 136Ba, 137Ba, 140Ba, 209Bi, natCa, natZr, natCd) in ISOTXS format with a different group structure for each library, that is, IRAN1.LIB (22 neutrons, 18 gammas); IRAN2.LIB (17 neutrons, 18 gammas); IRAN3.LIB (7 neutrons, 18 gammas); IRAN4.LIB (7 neutrons, 6 gammas); IRAN5.LIB (5 neutrons, 4 gammas); IRAN6.LIB (2 neutrons, 4 gammas).
The basic data sources were VITAMIN-4C; ENDF/B-IV and V and JENDL-3. Most of the data were taken from VITAMIN-4C (1H, 2H, 6Li, 7Li, 9Be, 10B, 12C, 14N, 16O, Na, Mg, 27Al, Si, K, V, Cr, 55Mn, Fe, Ni, 93Nb, Pb, 235U, 238U, 239PU) and collapsing them using AMPX-II modules. The AJAX module extracts the neutron cross sections of desired elements from VITAMIN-4C. CHOX module combines master neutron, gamma production and gamma interaction libraries into a coupled neutron-gamma library. MALOCS module collapses the cross sections into given energy groups and NITAWL module writes the collapsed cross sections in ANISN format. A computer program, CONVERT, was written to convert the cross sections from ANISN format to ISOTXS format, and control parameters. Some elements, not present in VITAMIN-4C were taken from ENDF/B-IV (Cd-nat, no gamma production data); ENDF/B-V fission product file (134Ba, 135Ba, 136Ba, 137Ba, 140Ba); JENDL-3 (209Bi, natCa, natZr) using NJOY code and collapsed using AMPX-II.
The retrieval program, LMOD (distributed in CCC-0514-ANISN/PC package) must be used to read microscopic multigroup, P-3 cross section data from IRAN.LIB to create a file in a CCC.ASC II ISOTXS format suitable to be used by ANISN/PC (ANISN.EXE) in the file ANISNC4.LIB (array 13$).
J.R. Maiorino: Computer Code ANISN Multiplying Media and Shielding Calculation Workshop on Reactor Physics Calculation for Application in Nuclear Technology, International Center for Theoretical Physics, Triest, Italy (1990).
If one uses ANISN/PC the use of IRAN.LIB is restricted to IRAN3.LIB (25 groups); IRAN4.LIB (13 groups); IRAN5.LIB (9 groups) and IRAN6.LIB (6 groups). However, one can modify the ANISN.FOR to increase the dimension of energy dependent variables in ANISN/PC to 40 groups (subroutine S966 must be modified) and then compile it again using the recommended compiler/linker in CCC-0514/02. In any case if, however, the size of a problem is larger than memory available on the RAM, IDAT1 automatically is changed to 1, that is, (Winchester) hard disk is used to store the data. Due to the limitation in the dimension of the SCAT matrix in the ANISN/PC (CCC-0514/02) the last group does not give correct results. It is recommended to use modified ANISN/PC.
M.K. Marashi
Neutron Physics Dept.
Nuclear Research Center
Atomic Energy Organization of Iran (AEOI)
P.O. Box 11365/8684
Teheran, Iran
J.R. Maiorino, A.G. Mendonca, A. Santos
Reactor Physics Division
Instituto de Pesquisas Energeticas e Nucleares
Comissao Nacional de Energia Nuclear
Caixa Postal 11049 (Pinheiros)
05499- Sao Paulo/SP, Brazil
File name | File description | Records |
---|---|---|
IAEA1215_01.001 | Information file | 67 |
IAEA1215_01.002 | ANISN/PC 40-group library | 0 |
IAEA1215_01.003 | ANISN/PC 35-group library | 0 |
IAEA1215_01.004 | ANISN/PC 25-group library | 0 |
IAEA1215_01.005 | ANISN/PC 13-group library | 0 |
IAEA1215_01.006 | ANISN/PC 9-group library | 0 |
IAEA1215_01.007 | ANISN/PC 6-group library | 0 |
IAEA1215_01.008 | ANISN/PC test case input SAMPL140.INP | 83 |
IAEA1215_01.009 | ANISN/PC test case input SAMPL240.INP | 66 |
IAEA1215_01.010 | ANISN/PC test case input SAMPL125.INP | 75 |
IAEA1215_01.011 | ANISN/PC test case input SAMPL225.INP | 59 |
IAEA1215_01.012 | ANISN/PC test case output SAMPL140.OUT | 1276 |
IAEA1215_01.013 | ANISN/PC test case output SAMPL240.OUT | 1310 |
IAEA1215_01.014 | ANISN/PC test case output SAMPL125.OUT | 2223 |
IAEA1215_01.015 | ANISN/PC test case output SAMPL225.OUT | 999 |
IAEA1215_01.016 | File compression program PKZIP.EXE | 0 |
IAEA1215_01.017 | File compression program PKZ090.EXE | 0 |
IAEA1215_01.018 | File unpacking program PKUNZIP.EXE | 0 |
IAEA1215_01.019 | DOS file-names | 18 |
Keywords: anisotropic, cross sections, data library, gamma radiation, multigroup, neutron, transport theory.