Thermal reactor benchmark integral results for JEF-1 ENDF/B-V, and ENDF/B-VI nuclear data

Conference · Mon Jan 01 04:00:00 EST 1990 · Transactions of the American Nuclear Society; (United States)

OSTI ID:7091275

Kamboj, B K; Abdel-Khalik, S I ^[1]; Paratte, J M; Kallfelz, J M

---

1. Georgia Inst. of Tech., Atlanta (United States)

The fifth version of the Evaluated Nuclear Data File (ENDF/B-V) was released in 1979, with a significant updating in 1981. This file was limited to users in the US and with Atomic Energy of Canada Limited. The first version of the Joint Evaluated File (JEF-1), created by collaboration among laboratories in Europe and Japan and the Nuclear Energy Agency Data Bank, was released in 1986; this file was not available in the US. The sixth version of ENDF/B is in preparation (ENDF/B-VI). This file will be available to all requestors. From comparisons of various calculated and measured values, it appears that the ENDF/B-V library constitutes a very good data base for LWR analysis. Thus, there is considerable interest in a comparison of thermal lattice integral parameters calculated with JEF-1 and ENDF/B-V; such comparisons have been made. However, in all such comparisons known to the authors, the calculations with the two data sets were performed at two different US and European laboratories with different codes. Such comparisons have a degree of uncertainty concerning the performance of the two evaluated files. In the joint investigations at the Georgia Institute of Technology and the Paul Scherrer Institute, such uncertainty in the comparison discussed above was eliminated by using the same cross-section processing codes and cell codes of the PSI light water reactor (LWR) code system ELCOS and identical code input at both installations. An additional features of this study is an investigation of the influence on calculated LWR parameters of the ENDF/B-VI modifications to the data for H[sub 2]O constituents.

• OSTI ID: 7091275
• Report Number(s): CONF-901101--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 62
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACTINIDE ISO
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
ATOMIC ENERGY OF CANADA LTD
BENCHMARKS
BWR TYPE REACTORS
CANADIAN ORGANIZATIONS
CHALK RIVER NUCLEAR LABS
COMPUTER CODES
CROSS SECTIONS
DATA BASE MANAGEMENT
E CODES
EDUCATIONAL FACILITIES
ENRICHED URANIUM REACTORS
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
HEAVY NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
INTERNATIONAL ORGANIZATIONS
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
MANAGEMENT
MINUTES LIVING RADIOISOTOPES
NATIONAL ORGANIZATIONS
NEA
NUCLEAR DATA COLLECTIONS
NUCLEI
OECD
P CODES
PHYSICS
POWER REACTORS
PWR TYPE REACTORS
RADIOISOTOPES
REACTOR PHYSICS
REACTORS
RESEARCH PROGRAMS
SELF-SHIELDING
SHIELDING
SPONTANEOUS FISSION RADIOISOTOPES
THERMAL REACTORS
URANIUM 235
URANIUM 238
URANIUM ISOTOPES
WATER COOLED REACTORS
WATER MODERATED REACTORS
YEARS LIVING RADIOISOTOPES