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.
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
8. DATA FORMAT AND COMPUTER
EBCDIC card images; IBM 360/91.
9. TYPICAL RUNNING TIME
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.
KEYWORDS: CCCC INTERFACE FORMAT; COVARIANCE MATRICES