Risk evaluation of accident management strategies

Conference · Wed Jan 01 04:00:00 EST 1992

OSTI ID:7022689

Dingman, S; Camp, A

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.

• Research Organization: Sandia National Labs., Albuquerque, NM (United States)
• Sponsoring Organization: NRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 7022689
• Report Number(s): SAND-92-0978C; CONF-930116--6; ON: DE93002463
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLACKOUTS
CONTROL EQUIPMENT
COOLING SYSTEMS
DECISION MAKING
ECCS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
EQUIPMENT
FAILURE MODE ANALYSIS
FAILURES
FLOW REGULATORS
HIGH PRESSURE COOLANT INJECTION
MANAGEMENT
POWER REACTORS
PRESSURIZATION
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTORS
RISK ASSESSMENT
SURRY-1 REACTOR
SURRY-2 REACTOR
SURRY-3 REACTOR
SURRY-4 REACTOR
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL REACTORS
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS