CSNI Workshop on PSA Applications and Limitations

Conference · Tue Sep 04 00:00:00 EDT 1990

OSTI ID:6179180

Molina, Toni ^[1]

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1. Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

This report contains the full papers submitted to the Committee on the Safety of Nuclear Installations (CSNI) Workshop on Probabilistic Safety Assessment (PSA) Applications and Limitations held in Santa Fe, New Mexico, USA, on September 4 through 6, 1990. The purpose of the Workshop was to provide an avenue for discussions in the following areas: (1) current PSA result, (2) current uses of PSA, (3) views on current limitations, (4) expert opinion, and (5) low probability numbers. The papers contained herein address these issues, along with several other related topics.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States); Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 6179180
• Report Number(s): NUREG/CP-0115; SAND-90-2797; CONF-9009346-; ON: TI91008351; TRN: 91-009371
• Resource Relation: Conference: Committee on the Safety of Nuclear Installations (CSNI) on Probabilistic Safety Assessment (PSA) Applications and Limitations, Santa Fe, NM (United States), 4-6 Sep 1990
• Country of Publication: United States
• Language: English

Related Subjects

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
RISK ASSESSMENT
PWR TYPE REACTORS
MEETINGS
AFTER-HEAT REMOVAL
BLACKOUTS
CONTAINMENT SYSTEMS
CORIUM
DECISION MAKING
DESIGN
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EMERGENCY PLANS
FAILURE MODE ANALYSIS
FAILURES
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HEAT TRANSFER
HUMAN FACTORS
HYDRAULICS
IAEA
INFORMATION NEEDS
JAERI
LEADING ABSTRACT
LOSS OF COOLANT
MELTDOWN
MOLTEN METAL-WATER REACTIONS
NATURAL CONVECTION
NETHERLANDS
OCCUPATIONAL EXPOSURE
PRIMARY COOLANT CIRCUITS
PROBABILITY
RADIATION DOSES
RADIATION PROTECTION
RADIOACTIVITY TRANSPORT
REACTOR ACCIDENTS
REACTOR CORES
REACTOR KINETICS
REACTOR SAFETY
REACTOR SAFETY EXPERIMENTS
RELIABILITY
RESEARCH PROGRAMS
SEISMIC EFFECTS
SOURCE TERMS
STEAM GENERATORS
ABSTRACTS
ACCIDENTS
BOILERS
CONTAINMENT
CONVECTION
COOLING SYSTEMS
DOCUMENT TYPES
DOSES
ENERGY SYSTEMS
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INTERNATIONAL ORGANIZATIONS
JAPANESE ORGANIZATIONS
KINETICS
MASS TRANSFER
MECHANICS
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REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTORS
REMOVAL
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTERN EUROPE
220900* - Nuclear Reactor Technology- Reactor Safety
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