1. NAME AND TITLE OF DATA LIBRARY

COVERX: Compilation of Multigroup Cross-Section Covariance Matrices in COVERX Format for Several Important Materials.

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

No retrieval program is included in the package.

3. CONTRIBUTOR

Oak Ridge National Laboratory, Oak Ridge, Tennessee.

4. HISTORICAL BACKGROUND AND INFORMATION

Only recently have standard formats and procedures been established within the ENDF/B system for the processing of evaluated and correlated energy-dependent uncertainty information into a multigroup covariance matrix formulation. The covariance matrices were established to permit systematic sensitivity investigations to propagate uncertainties in radiation transport calculations and thereby to determine, in a credible fashion, what cross-section measurements, evaluations, or processing methods most need further refinement for specific applications.

5. APPLICATION OF THE DATA

DLC-44/COVERX contains the COVERT program and multigroup cross-section covariance matrices for several important materials. COVERT performs the necessary task of converting the data in the COVERX package to binary format so that it can then be used by modules of the PSR-129/FORSS Sensitivity and Uncertainty Analysis Code System. In addition, it can be used for partial or complete editing of a COVERX file. The edit provides the user with input parameters needed by FORSS modules to perform selected manipulations with COVERX files.

6. SOURCE AND SCOPE OF DATA

COVERX presents multigroup cross-section covariance matrices for fission in ²³⁵U, ²³⁸U, ²³⁹Pu, and ²⁴¹Pu; capture in ²³⁵U, ²³⁸U, ²³⁹Pu, ²⁴⁰Pu, and ²⁴¹Pu; fission neutron yield for ²³⁵U, ²³⁸U, ²³⁹Pu, and ²⁴⁰Pu; elastic scattering for Na and Fe; non-elastic reactions for Na and Fe, first-level inelastic scattering for 238U; and all reactions provided in the ENDF/B-IV covariance description of N, O, and C.

The report presents the multigroup data in six, ten, and fifteen energy group forms corresponding to weighting of the covariance data with fission (GODIVA), LFMBR (ZPR-6/7) and 1/E spectra, respectively. The data are illustrated and tabulated in an edited form for convenience.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

Not applicable.

8. DATA FORMAT AND COMPUTER

EBCDIC card images; IBM 360/91.

9. TYPICAL RUNNING TIME

Not applicable.

10. REFERENCES

D. K. Olsen and G. de Saussure, "238U Inelastic Scattering Covariance Matrix," ORNL Memo (Feb. 16, 1978).

J. D. Drischler, "ORNL 26 Group Fast Reactor Benchmark Covariance Matrix Library," ORNL Memo (May 1, 1979).

J. D. Drischler and C. R. Weisbin, "Compilation of Multigroup Cross-Section Covariance Matrices for Several Important Reactor Materials," ORNL-5318 (ENDF-235) (October 1977).

J. D. Drischler, "The COVERX Service Module of the FORSS System," ORNL/TM-7181 (ENDF-291) (April 1980).

11. CONTENTS OF LIBRARY

Included are the referenced documents and one (1.2MB) DOS diskette which contains a fission spectrum covariance matrix library, a LMFBR core physics covariance matrix library, a LMFBR shielding covariance matrix library, a fast reactor covariance matrix library, the source program, and JCL plus input and output for the sample problem.

12. DATE OF ABSTRACT

December 1984, revised December 1989.