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Author Fredin, B. ♦ Decher, U. ♦ Jonsson, A. ♦ Ferri, A. ♦ Stamm`ler, R. J. J.
Source United States Department of Energy Office of Scientific and Technical Information
Content type Text
Language English
Subject Keyword NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS ♦ PWR TYPE REACTORS ♦ PERFORMANCE ♦ NUCLEAR DATA COLLECTIONS ♦ TESTING ♦ CROSS SECTIONS ♦ FISSION PRODUCTS ♦ POWER COEFFICIENT ♦ CONTROL ROD WORTHS ♦ CRITICALITY
Abstract We have processed ENDF/B-VI through Mod.3 using NJOY 91 through update 105 augmented by an extended version of RABBLE capable of reading the PENDF files. In this version, RABBLE works as a module of NJOY. A master multigroup-averaged data library with 190 energy groups and 216 nuclides has been created and tested extensively. Condensed libraries in 89 energy groups are available for use in the DIT, HELIOS, and PHOENIX codes. This paper describes some of the results of data testing for critical experiments and a companion paper describes the results of data testing on pressurized water reactors (PWRs).
ISSN 0003018X
Educational Use Research
Learning Resource Type Article
Publisher Date 1995-12-31
Publisher Place United States
Journal Transactions of the American Nuclear Society
Volume Number 73
Technical Publication No. CONF-951006-


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