Analysis of ex-vessel debris cooling in the GE simplified boiling water reactor

Conference · Fri Jan 01 04:00:00 EST 1993 · Transactions of the American Nuclear Society; (United States)

OSTI ID:6844264

Sherry, R R ^[1]; Buchholz, C E ^[2]

---

1. Gabor, Kenton Associates Inc., Germantown, MD (United States)
2. General Electric Co., San Jose, CA (United States)

As part of the level II probabilistic risk assessment (PRA) performed for the GE Simplified Boiling Water Reactor (SBWR) an analysis was performed to assess the probability that the debris released from the reactor vessel was in a coolable configuration in the lower drywell and, if not, to assess the type of core/concrete attack that would occur. The coolability of the debris ex-vessel was explicitly evaluated by an event in the SBWR containment event tree (CET). A detailed decomposition event tree (DET) was developed to aid in the quantification of this CET event. The headings in the DET were selected to represent plant physical states (e.g., reactor vessel pressure at the time of vessel failure) and the uncertainties associated with the occurrence of critical physical phenomena (e.g., debris configuration in the lower drywell) considered important to assessing whether the debris was coolable or not coolable ex-vessel.

• OSTI ID: 6844264
• Report Number(s): CONF-931160--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 69
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
CONTAINERS
COOLING
CORIUM
ENRICHED URANIUM REACTORS
FAILURE MODE ANALYSIS
POWER REACTORS
PRESSURE VESSELS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTORS
RISK ASSESSMENT
SAFETY ANALYSIS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS