Realistic evaluation of fuel enthalpy during reactivity-initiated accidents in PWRs
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:436958
- Kansai Electric Power Co., Osaka (Japan)
- Mitsubishi Heavy Industries, Ltd., Yokohama (Japan)
In recent years, reactivity-initiated accident (RIA) simulation experiments using preirradiated fuels have been widely conducted in the NSRR in Japan and the CABRI reactor in France. Although the dependency of fuel failure on burnup has not been clearly determined so far, it is suggested that the failure threshold of irradiated fuel may be decreased compared with that of fresh fuel. The objective of this study is to confirm the conservatism in the current safety analysis and to evaluate the effect of the decrease in the threshold. The current safety analysis for a rod ejection accident for a pwr reactor at the end-of-cycle hot zero power (HZP) is summarized.
- OSTI ID:
- 436958
- Report Number(s):
- CONF-9606116-; ISSN 0003-018X; TRN: 96:005275-0195
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 74; Conference: Annual meeting of the American Nuclear Society (ANS), Reno, NV (United States), 16-20 Jun 1996; Other Information: PBD: 1996
- Country of Publication:
- United States
- Language:
- English
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