Review of the Seabrook Station Probabilistic Safety Assessment: Containment Failure Modes and Radiological Source Terms.

摘要

A technical review and evaluation of the Seabrook Station Probabilistic Safety Assessment has been performed. It is determined that (1) containment response to severe core melt accidents is judged to be an important factor in mitigating the consequences, (2) failure during the first few hours after core melt is also unlikely and the timing of overpressure failure is very long compared to WASH-1400, (3) the point-estimate radiological releases are comparable in magnitude to those used in WASH-1400, and (4) the energy of release is somewhat higher than for the previously reviewed studies.