Probabilistic assessment of ex-vessel fuel/coolant interaction energetics for light water reactors
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:89353
During postulated core meltdown accidents in light water reactors, there is a likelihood for an energetic ex-vessel fuel-coolant interaction (FCI). The impact of the dynamic pressures on the surrounding structures could ultimately lead to the failure of the structures. The objective of the current work is to investigate the potential impulsive loads following an energetic FCI using a probabilistic approach.
- OSTI ID:
- 89353
- Report Number(s):
- CONF-941102--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 71; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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