Comparative study of ENDF/B-VI and JENDL-3 for LWR design application

Conference · Wed Jan 01 04:00:00 EST 1992 · Transactions of the American Nuclear Society; (United States)

OSTI ID:6662607

Imamura, Y; Jigami, T; Ikeda, K ^[1]

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1. Shikoku Denryoku Corp., Kagawa (Japan)

Aiming at self-consistent core management in the design of reload cores and in the planning of refueling schemes, we have developed a code system, SENTAS, in which the group constants of most nuclides were generated from ENDF/B-IV and those of a few nuclides (americium, curium, etc.) were from a part of ENDF/B-V and JENDL-2 as supplements. In 1989 and 1990, the latest versions of the evaluated nuclear data files JENDL-3 and ENDF/B-VI were released, but few articles are now available to judge which file is better for thermal reactor core calculations. Before incorporating these files into SENTAS, we examined characteristics of both files by benchmark calculations, based on experimental results of the Japan Atomic Energy Research Institute (JAERI) TCA geometry and a Babcock Wilcox (B W) critical facility.

• OSTI ID: 6662607
• Report Number(s): CONF-921102--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 66
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Light-Water Moderated
Nonboiling Water Cooled
CALCULATION METHODS
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REACTORS
S CODES
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