Processing and application of ENDF/B-VI in LWRs: Critical experiments

Journal Article · Sun Dec 31 00:00:00 EST 1995 · Transactions of the American Nuclear Society

OSTI ID:411789

Fredin, B ^[1]; Decher, U; Jonsson, A ^[2]; Ferri, A; Stamm`ler, R J.J. ^[3]

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1. ABB Atom, Vasteras (Sweden)
2. ABB Combustion Engineering Nuclear Power, Inc., Windsor, CT (United States)
3. Scandpower Inc., Gaithersburg, MD (United States)

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).

• OSTI ID: 411789
• Report Number(s): CONF-951006-; ISSN 0003-018X; TRN: 97:001034
• Journal Information: Transactions of the American Nuclear Society, Vol. 73; Conference: Winter meeting of the American Nuclear Society (ANS), San Francisco, CA (United States), 29 Oct - 1 Nov 1995; Other Information: PBD: 1995
• Country of Publication: United States
• Language: English

Related Subjects

21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
PERFORMANCE
NUCLEAR DATA COLLECTIONS
TESTING
CROSS SECTIONS
FISSION PRODUCTS
POWER COEFFICIENT
CONTROL ROD WORTHS
CRITICALITY