An analysis of containment venting as a severe accident mitigation strategy for the BWR Mark II containment

Conference · Sun Apr 01 04:00:00 EDT 1990 · IEEE Transactions on Nuclear Science (Institute of Electrical and Electronics Engineers); (USA)

OSTI ID:6892424

Kelly, D L; Galyean, W J ^[1]

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1. Idaho National Engineering Lab., Idaho Falls, ID (USA)

An evaluation of a BWR/4 reactor with a Mark-II containment has identified the effects of containment venting on core damage frequency and containment failure mode, and has performed a limited evaluation of the effects on the off-site consequences. The analysis was founded upon an existing probabilistic risk assessment (PRA) with the addition of a proposed filtered containment venting system, based on the Swedish Filtra system installed at the Barseback nuclear power station in southern Sweden. Three different containment venting strategies were examined for their effects on plant risk. These are discussed.

• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6892424
• Report Number(s): CONF-900143--
• Conference Information: Journal Name: IEEE Transactions on Nuclear Science (Institute of Electrical and Electronics Engineers); (USA) Journal Volume: 37:2
• Country of Publication: United States
• Language: English

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