Accident management then and now: Progress since Di Salvo's work

Conference · Tue Jan 01 00:00:00 EST 1991 · Transactions of the American Nuclear Society; (United States)

OSTI ID:7022298

Shotkin, L M

The nuclear industry is now initiating a serious effort to define the elements of an accident management program at each utility with an operating reactor, which is a significant change in conditions from those in 1985, when the work of Di Salvo et al. was published. Each utility is now conducting an individual plant examination (IPE) to uncover plant vulnerabilities to severe accidents. In conjunction with the IPE program, the Nuclear Utility Management and Resources committee, the Electric Power Research Institute, and owners' groups are developing an accident management program. This program is emphasizing the management program. This program is emphasizing the management of severe accidents (i.e., accidents that proceed to significant core melt) including strategies for managing ex-vessel events. Attention is also being paid to interfacing any severe accident management strategies with existing emergency operating procedures already in place at utilities. The industry program is addressing the five elements define by the US Nuclear Regulatory Commission (NRC): (1) strategies; (2) instrumentation; (3) guidance and computational aids; (4) organization and decision making; and (5) training. It will also be able to accept new information as it becomes available from ongoing efforts to better understand severe accidents and how to manage them effectively.

• OSTI ID: 7022298
• Report Number(s): CONF-911107-; CODEN: TANSA; TRN: 92-030820
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 63; Conference: 1991 Winter meeting of the American Nuclear Society (ANS) session on fundamentals of fusion reactor thermal hydraulics, San Francisco, CA (United States), 10-15 Nov 1991; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR ACCIDENTS
PWR TYPE REACTORS
MITIGATION
CONTAINMENT SPRAY SYSTEMS
CONTAINMENT SYSTEMS
DECISION MAKING
ELECTRIC UTILITIES
EMERGENCY PLANS
EPRI
HUMAN FACTORS
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NUCLEAR POWER
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
REACTOR CORE DISRUPTION
REACTOR INSTRUMENTATION
REACTOR OPERATION
REACTOR OPERATORS
RESEARCH PROGRAMS
RISK ASSESSMENT
RUPTURES
STEAM GENERATORS
TRAINING
TUBES
US NRC
ACCIDENTS
ANIMALS
BOILERS
CONTAINERS
CONTAINMENT
COOLING SYSTEMS
EDUCATION
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURES
MAMMALS
MAN
NATIONAL ORGANIZATIONS
OPERATION
PERSONNEL
POWER
POWER REACTORS
PRIMATES
PUBLIC UTILITIES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
THERMAL REACTORS
US ORGANIZATIONS
VAPOR GENERATORS
VERTEBRATES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
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Light-Water Moderated
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210200 - Power Reactors
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