The use of Probabilistic Risk Assessment (PRA) methods to evaluate accident management strategies in nuclear power plants discussed in this paper. The PRA framework allows an integrated evaluation to be performed to give the full implications of a particular strategy. The methodology is demonstrated for a particular accident management strategy, intentional depressurization of the reactor coolant system to avoid containment pressurization during the ejection of molten debris at vessel breach.
Risk evaluation of accident management strategies
1992
7 pages
Report
Keine Angabe
Englisch
Reactor Engineering & Nuclear Power Plants , Reactor Accidents , Risk Assessment , Blackouts , Decision Making , Failure Mode Analysis , Failures , High Pressure Coolant Injection , Management , Pressurization , Reactor Cooling Systems , Surry-1 Reactor , Surry-2 Reactor , Surry-3 Reactor , Surry-4 Reactor , Valves , Meetings , Probabilistic risk assessment , EDB/220900 , EDB/220200
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