A reassessment of the potential for an alpha-mode containment failure and a review of the current understanding of broader fuel-coolant interaction issues. Second steam explosion review group workshop

Conference · Thu Aug 01 04:00:00 EDT 1996

OSTI ID:319665

Basu, S ^[1]; Ginsberg, T ^[2]

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1. Nuclear Regulatory Commission, Washington, DC (United States)
2. Brookhaven National Lab., Upton, NY (United States)

This report summarizes the review and evaluation by experts of the current understanding of the molten fuel-coolant interaction (FCI) issues covering the complete spectrum of interactions, i.e., from mild quenching to very energetic interactions including those that could lead to the alpha-mode containment failure. Of the eleven experts polled, all but two concluded that the alpha-mode failure issue was resolved from a risk perspective, meaning that this mode of failure is of very low probability, that it is of little or no significance to the overall risk from a nuclear power plant, and that any further reduction in residual uncertainties is not likely to change the probability in an appreciable manner. To a lesser degree, discussions also took place on the broader FCI issues such as mild quenching of core melt during non-explosive FCI, and shock loading of lower head and ex-vessel support structures arising from explosive localized FCIs. These latter issues are relevant with regard to determining the efficacy of certain accident management strategies for operating reactors as well as for advanced light water reactors. The experts reviewed the status of understanding of the FCI phenomena in the context of these broader issues, identified residual uncertainties in the understanding, and recommended future research (both experimental and analytical) to reduce the uncertainties.

• Research Organization: Nuclear Regulatory Commission, Div. of Systems Technology, Washington, DC (United States); Brookhaven National Lab., Upton, NY (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 319665
• Report Number(s): NUREG--1524; CONF-9506447--Summ.; ON: TI99001657
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
CONTAINMENT SYSTEMS
FAILURE MODE ANALYSIS
FUEL-COOLANT INTERACTIONS
MEETINGS
PROBABILITY
REACTOR SAFETY
RISK ASSESSMENT
WATER COOLED REACTORS