1. NAME AND TITLE OF DATA LIBRARY

LIB-IV: Library of Group Constants Based on ENDF/B-IV in CCCC Interface Formats for Nuclear Reactor Calculations.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

No retrieval program is included in the package.

3. CONTRIBUTOR

Los Alamos Scientific Laboratory, Los Alamos, New Mexico.

4. HISTORICAL BACKGROUND AND INFORMATION

LIB-IV is a rather complete and tested multigroup library based on the latest version of the Evaluated Nuclear Data Files (ENDF/B-IV) and generated using the MINX nuclear cross-section processing code. It was issued in the CCCC-III interface format and was intended for use by the nuclear community for fast-reactor design calculations.

The ENDF/B-IV data files are the latest result of a continuing major effort to compile, evaluate, test, and update a computer-readable repository of basic nuclear data. Because of the scope of this effort and the intensive testing of the data, these files are rapidly becoming the authoritative source of data for the preparation of multigroup constants.

5. APPLICATION OF THE DATA

The MINX (Multigroup Interpretation of Nuclear Cross Sections) code is a new advanced computer program for processing ENDF/B data. It is a designer-oriented code producing pseudo-composition-independent libraries of group cross sections, self-shielding factors, and group-to-group transfer matrices in the CCCC interface format.

LIB-IV contains three CCCC-III files: ISOTXS (isotope constants, cross sections, and matrices), BRKOXS (self-shielding factors), and DLAYXS (delayed neutron yields and spectra by time group).

6. SOURCE AND SCOPE OF DATA

The library was generated using a "thermal + 1/E + fission" weight function. The P0, P1, P2, and P3 Legendre components of the matrices were generated whenever the ENDF/B data permitted.

The 101-BRKOXS 50-Group Library, generated with MINX from ENDF/B-IV is as follows:

H, 2H, 3H, 3He, 4He, 6Li, 7Li, 9Be, 10B, 11B, 12C, 14N, 16O, F, 23Na, Mg, 27Al, Si, Cl, K, Ca, Ti, V, Cr, 55Mn, Fe, 59Co, Ni, Cu, 63Cu, 65Cu, 78Kr, 80Kr, 82Kr, 83Kr, 84Kr, 86Kr, 2Zirc, 92Nb, Mo, 103Rh, 107Ag, 109Ag, Cd, 113Cd, 124Xe, 126Xe, 127Xe, 128Xe, 130Xe, 131Xe, 132Xe, 134Xe, 135Xe, 136Xe, 133Cs, 149Sm, 151Eu, 152Eu, 153Eu, 154Eu, Gd, 164Dy, 175Lu, 176Lu, 181Ta, 182Ta, 182W, 183W, 184W, 186W, 185Re, 187Re, 197Au, Pb, 232Th, 233Pa, 233U, 234U, 235U, 236U, 238U, 237Np, 238Pu, 239Pu, 240Pu, 241Pu, 242Pu, 241Am, 243Am, 244Cm, 233NFp, 233SFp, 233RFp, 235NFp, 235SFp, 235RFp, 239NFp, 239SFp, 239RFp.

The DLAYXS Library is a follows:

232Th, 233U, 236U, 238U, 239Pu, 240Pu, 241Pu.

The 101-ISOTXS 50-Group Library, also generated with MINX from ENDF/B-14, contains the same material as was found in 101-BRKOXS.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

Not applicable.

8. DATA FORMAT AND COMPUTER

9. TYPICAL RUNNING TIME

Not applicable.

10. REFERENCES

R. B. Kidman and R. E. MacFarlane, LIB-IV, A Library of Group Constants for Nuclear Reactor Calculations, LA-6260-MS (March 1976).

John E. White and Robert W. Roussin, "IBM-360 Versions of the BINX, LINX, and CINX Utility Codes," Informal Notes (March 1977).

R. B. Kidman and R. E. MacFarlane, CINX, Collapsed Interpretation of Nuclear X Sections, LA-6287- MS (April 1976).

R. E. MacFarlane and R. B. Kidman, LINX and BINX: CCCC Utility Codes for the MINX Multigroup Processing Code, LA-6219-MS (January 1976).

R. B. Kidman, ENDF/B-IV, LIB-IV, and the CSEWG Benchmarks, LA-7355-MS (June 1978).

11. CONTENTS OF LIBRARY

Included are the referenced documents and a reel of magnetic tape containing the libraries; total records 192,173.

12. DATE OF ABSTRACT

December 1984.