last modified: 11-JAN-1991 | catalog | categories | new | search |

IAEA1215 ZZ-IRAN-LIB.

ZZ IRAN-LIB, Multigroup Neutron Gamma Cross-Section Library for 33 Elements in ANISN Format

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-IRAN-LIB.
IRAN1.LIB (40 groups); IRAN2.LIB (35 groups); IRAN3.LIB (25 groups); IRAN4.LIB (13 groups); IRAN5 (9 groups) and IRAN6.LIB (6 groups).
IRAN.LIB (Improved Range of ANISN/PC Library) are P-3 coupled multi- group neutron-gamma cross section libraries for 33 elements.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters 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
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3. DESCRIPTION OF PROGRAM OR FUNCTION


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  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: H-1, H-2, Li-6, Li-7, Be-9, B-10, C-12, N-14, O-16, Na, Mg, Al-27, Si, K, V, Cr, Mn-55, Fe, Ni, Nb-93, Pb, U-235, U-238, PU-239, Ba-134, Ba-135, Ba-136, Ba-137, Ba-140, Bi-209, Ca-nat, Zr-nat, Cd-nat.

  ORIGIN: VITAMIN-4C; ENDF/B-IV and V, and JENDL-3.

  WEIGHTING SPECTRUM:

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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 (H-1; H-2; Li-6; Li-7; Be-9; B-10; C-12; N-14; O-16; Na; Mg; Al-27; Si; K; V; Cr; Mn-55; Fe; Ni; Nb-93; Pb; U-235; U-238; PU-239; Ba-134; Ba-135; Ba-136; Ba-137; Ba-140; Bi-209;  Ca-nat;  Zr-nat; Cd-nat) 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).
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4. METHOD OF SOLUTION

The basic data sources were VITAMIN-4C; ENDF/B-IV and V and JENDL-3. Most of the data were taken from VITAMIN-4C (H-1, H-2, Li-6, Li-7, Be-9, B-10, C-12, N-14, O-16, Na,  Mg, Al-27, Si, K, V, Cr, Mn-55, Fe, Ni, Nb-93, Pb, U-235, U-238, Pu-239) 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 (Ba-134, Ba-135, Ba-136, Ba-137, Ba-140); JENDL-3 (Bi-209, Ca-nat, Zr-nat) using NJOY code and collapsed using AMPX-II.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  Problem size is limited only by machine size.
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6. TYPICAL RUNNING TIME

The time required for creating a H-1 library  from IRAN1.LIB is about 30 seconds. Creating a library for U-235 from the same library takes 135 seconds.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

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$).
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9. STATUS
Package ID Status date Status
IAEA1215/01 11-JAN-1991 Screened
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10. REFERENCES

- 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).
IAEA1215/01, included references:
- M.K. Marashi et al.:
  IRAN-LIB (Improved Range of ANISN/PC Library)
  A P-3 Coupled Neutron-Gamma Cross-Section Libraries in ISOTXS
  Format to be Used by ANISN/PC (CCC-0514/02)
- NEA Data Bank:
  NDB/90/1713 Note to Recipients of ZZ-IRAN-LIB (26 November 1990)
- M.K. Marashi et al.:
  IRAN.LIB (Improved Range of ANISN/PC Library): A P-3 Coupled
  Neutron-Gamma Cross-Section Library in ISOTXS Format to be used by
  ANISN/PC (CCC-0514/02)
  Reprint: Ann. Nucl. Energy, Vol. 18, No. 10 pp. 597-602 (1991)
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11. MACHINE REQUIREMENTS:  Personal microcomputer (IBM PC).
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA1215/01 FORTRAN
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  DOS 3.3 (or equivalent).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

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 modi-  fied ANISN/PC.
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15. NAME AND ESTABLISHMENT OF AUTHORS

          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
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16. MATERIAL AVAILABLE
IAEA1215/01
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
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17. CATEGORIES
  • B. Spectrum Calculations, Generation of Group Constants and Cell Problems
  • Z. Data.

Keywords: anisotropic, cross sections, data library, gamma radiation, multigroup, neutron, transport theory.