Computer Programs
DLC-0006 ZZ-GAMLIB.
last modified: 01-DEC-1972 | catalog | categories | new | search |

DLC-0006 ZZ-GAMLIB.

ZZ GAMLIB, 99-Group Cross-Section Library by SUPERTOG Calculation from ENDF/B

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1. NAME

ZZ-GAMLIB.

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2. COMPUTERS
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Program name Package id Status Status date
ZZ-GAMLIB DLC-0006/01 Tested 01-DEC-1972

Machines used:

Package ID Orig. computer Test computer
DLC-0006/01 Many Computers Many Computers
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3. DESCRIPTION

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
FORMAT: GGC multigroup cross section codes.

 

NUMBER OF GROUPS: 99 energy bands covering the energy range from 14.92 MeV to 0.414 eV.

 

NUCLIDES: 2H, He, 6Li, 7Li, 9Be, 10B, 12C, 14N, 16O, 23Na, Mg, 27Al, Ti, V, Cr, 55Mn, Fe, Ni, Cu, 63Cu, 65Cu, 81Br, 82Kr, 83Kr, 84Kr, 85Kr, 86Kr, Rb, 88Sr, 90Sr, 93Nb, Mo, 100Ru, 105Rh, 104Pd, 126Te, 132Xe, 133Xe, 134Xe, 135Xe, 134Cs, 134Ba, 139La, 140Ce, 142Ce, 144Nd, 148Sm, 149Sm, 151Eu, 153Eu, Gd, 164Dy, 175Lu, 176Lu, 181Ta, 182W, 183W, 184W, 186W, 185Re, 187Re, 197Au, 207Pb, 232Th, 233U, 234U, 235U, 236U, 238U, 237Np, 238Pu, 239Pu, 240Pu, 241Pu, 242Pu, 241Am, 243Am, 244Cm, and for non saturating and slowly saturating fission product pseudo elements.

 

ORIGIN: ENDF/B

 

WEIGHTING SPECTRUM: 1/E

 

%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
GAMLIB is intended to be a source of neutron multigroup data for the fast (GAM) portion of the GGC multigroup cross section codes. It supplements the library available in the GGC-4 code package.

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4. METHODS

GAMLIB is a multigroup library, meaning, in this case, that detailed cross section data has been averaged with 1/e weighting to yield average cross sections over 99 energy bands covering the energy range from 14.92 MeV to 0.414 eV. In addition, the GAM program accepts resonance cross section data in the form of single level Breit-Wigner parameters to perform resonance self-shielding calculations. Some of the data is presented in this form. In general, where resonance data is available, two data sets will be present, one containing the resonance parameters and the other, the group averaged values of the unshielded resonance cross sections. Elastic and inelastic scattering are represented by group to group transfer matrices, the elastic data having P3 scattering arrays.

 

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6. TYPICAL RUNNING TIME

CONVERSION: to convert GAMLIB from a single unformated tape to 9 formatted tapes required 10 minutes on the IBM 360/91.
MERGE: no running time estimate available.

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8. RELATED OR AUXILIARY PROGRAMS

CONVERSION has two functions: It was used to copy the master tape (unformatted) onto several tapes (formatted). The program can also be used to recreate a single master tape (unformated). The resulting tape can then be used with the GGC code.

MERGE merges selected nuclides from two existing library tapes onto a new library tape which can be used with GGC.

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9. STATUS
Package ID Status date Status
DLC-0006/01 01-DEC-1972 Tested at NEADB
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10. REFERENCES
DLC-0006/01, included references:
- J. L. Lucius, J. D. Jenkins, and R. Q. Wright, "The INDEX Data System: An
Index of Nuclear Data Libraries Available at ORNL," ORNL-TM-3334 (1971) 35-37.
- J. L. Lucius, "The Computer Programs CONVERSION and MERGE, Aids in Exchange
and Use of ORNL GAM II Cross Section Libraries," Informal notes (1971).
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. NAME AND ESTABLISHMENT OF AUTHORS

Oak Ridge National Laboratory
Oak Ridge, Tennessee, U. S. A.

 

and

 

General Atomics
San Diego, California, U. S. A.

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16. MATERIAL AVAILABLE
DLC-0006/01
File name File description Records
DLC0006_01.001 INFORMATION 143
DLC0006_01.002 DATA FILE 1 20079
DLC0006_01.003 DATA FILE 2 21274
DLC0006_01.004 DATA FILE 3 20939
DLC0006_01.005 DATA FILE 4 15747
DLC0006_01.006 DATA FILE 5 20876
DLC0006_01.007 DATA FILE 6 21741
DLC0006_01.008 DATA FILE 7 20521
DLC0006_01.009 DATA FILE 8 22867
DLC0006_01.010 DATA FILE 9 17160
DLC0006_01.011 CONVERSION SOURCE 438
DLC0006_01.012 MERGE SOURCE 373
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17. CATEGORIES
  • Z. Data

Keywords: Breit-Wigner formula, ENDF/B, cross sections, data, elastic scattering, fission products, inelastic scattering, multigroup.