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--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 74; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
Similar Records
Behavior of High-Burnup PWR Fuels with Low-Tin Zircaloy-4 Cladding Under Reactivity-Initiated-Accident Conditions
Pellet-Cladding Mechanical Interaction Failure Threshold for Reactivity Initiated Accidents for Pressurized Water Reactors and Boiling Water Reactors
High-burnup Experiments in Reactivity Initiated Accidents (HERA)
Journal Article
·
Sun Jan 14 23:00:00 EST 2001
· Nuclear Technology
·
OSTI ID:20822233
Pellet-Cladding Mechanical Interaction Failure Threshold for Reactivity Initiated Accidents for Pressurized Water Reactors and Boiling Water Reactors
Technical Report
·
Sat Jun 01 00:00:00 EDT 2013
·
OSTI ID:1362006
High-burnup Experiments in Reactivity Initiated Accidents (HERA)
Technical Report
·
Wed Jun 01 00:00:00 EDT 2022
·
OSTI ID:1874819