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RSIC DATA LIBRARY DLC-006


1. NAME AND TITLE OF DATA LIBRARY

GAMLIB: 99-Group Neutron Cross Sections for Use in the GAM Portion of the GGC Multigroup Cross Section Code.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

CONVERSION: A Program for Converting GAMLIB Cross Sections from Binary to BCD or Vice Versa.

MERGE: A Program for Merging Two Existing GGC Library Tapes onto a New GGC Library Tape.

3. CONTRIBUTORS

Oak Ridge National Laboratory, Oak Ridge, Tennessee.

General Atomic, San Diego, California.

4. HISTORICAL BACKGROUND AND INFORMATION

The original GAM library was obtained from General Atomic in 1964. Since then, much of the data has been revised and improved by individuals at ORNL. In addition, ENDF/B data have been processed through PSR-13/SUPERTOG and the results added to the ORNL GAM library.

The GAM II program has been replaced at ORNL as a principal reactor design tool by CCC-123/XSDRN. The GAM library is still maintained since needs for GAM processing occasionally arise, the library contains a great deal of data not yet converted to XSDRN format, and the production of an XSDRN data set from ENDF/B data now requires a GAM data set as an intermediate step. When these restrictions are overcome, it is anticipated that the library will be quietly retired. However, since much of the current ORNL GAM library is based on ENDF/B, it was felt that it would be useful to make some of the ORNL GAM library generally available.

5. APPLICATION OF THE DATA

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 PSR-12/GGC.

6. SOURCE AND SCOPE OF DATA

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.

GAMLIB I.D. numbers of nuclides on the tape are of the form Z.AAAS where Z is the atomic number and AAA the atomic weight. For the naturally occurring element, AAA = 000. The parameter S is 8 or 9, depending on whether the cross sections are for the infinite dilution form or are given as resonance parameters, respectively. For example, the I.D. numbers for 63Cu are 29.0638 for infinite dilution and 29.0639 for resonance.

The library contains data for:

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, 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*, NSFP***, SSFP***.

Note:

* Two I.D. numbers, one for resonance, one for infinite dilution.

** Resonance nuclide only.

***NSFP Non saturating fission product pseudo element.

***SSFP Slowly saturating fission product pseudo element.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

Two programs, CONVERSION and MERGE, are provided for manipulating the DLC-7/GAMLIB data. These were written for RSIC by J. L. Lucius of the ORNL Computer Sciences Division.

CONVERSION has two functions. It was used to copy the master tape (unformatted) onto several tapes (formatted) in order that the data may be easily transmitted between installations. CONVERSION can then be used at the receiving installation to recreate a single master tape (unformatted). The resulting tape can then be used with a GGC program.

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

8. DATA FORMAT AND COMPUTER

BCD card images; IBM 360/370.

9. TYPICAL RUNNING TIME

To convert GAMLIB from a single unformatted tape to 9 formatted tapes, using CONVERSION, required 10 minutes on the IBM 360/91 computer. No study has been made by RSIC of typical running times for MERGE.

10. 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).

11. CONTENTS OF LIBRARY

Included are the referenced documents and three DS/HD 5.25 (1.2MB) DOS diskettes which contain the entire library plus retrieval programs.

12. DATE OF ABSTRACT

December 1971; reviewed May 1984.

KEYWORDS: GAM 100-GROUP STRUCTURE; MULTIGROUP CROSS SECTIONS; NEUTRON CROSS SECTIONS