Overview of insights gained and lessons learned from US plant-specific PRA studies
Journal Article
·
· Nucl. Saf.; (United States)
OSTI ID:6134662
Probabilistic risk assessment (PRA) has been under development for over 20 yr, but it reached the level of widespread use only in the aftermath of the Three Mile Island accident. Over 30 PRAs have now been completed in the US. They have been in the mainstream of many licensing decisions because both the Nuclear Regulatory Commission and the nuclear utilities recognize that PRAs provide independent and comprehensive plant safety audits. Although some difficulties have been experienced, they have led to such efforts as interpretive or intercomparison studies. Numerous global and plant-specific insights have been derived. A new application termed risk management is clearly emerging.
- Research Organization:
- NUS Corp., San Diego, CA
- OSTI ID:
- 6134662
- Journal Information:
- Nucl. Saf.; (United States), Vol. 27:1
- Country of Publication:
- United States
- Language:
- English
Similar Records
Use of plant-specific PRA in an EOP scope audit
New insights gained from accident presursor data
Insights from an overview of four PRAs
Conference
·
Tue Jan 01 00:00:00 EST 1991
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:6134662
New insights gained from accident presursor data
Conference
·
Wed Jan 01 00:00:00 EST 1992
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:6134662
Insights from an overview of four PRAs
Conference
·
Wed Jan 01 00:00:00 EST 1986
·
OSTI ID:6134662
+1 more
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR SAFETY
RISK ASSESSMENT
PWR TYPE REACTORS
PROBABILISTIC ESTIMATION
BIG ROCK POINT REACTOR
FISSION PRODUCT RELEASE
INDIAN POINT-2 REACTOR
INDIAN POINT-3 REACTOR
LIMERICK-1 REACTOR
LIMERICK-2 REACTOR
LOSS OF COOLANT
MC GUIRE-1 REACTOR
MC GUIRE-2 REACTOR
MIDLAND-1 REACTOR
MIDLAND-2 REACTOR
MILLSTONE-3 REACTOR
OCONEE-3 REACTOR
PEACH BOTTOM-2 REACTOR
RADIATION HAZARDS
REACTOR CORE DISRUPTION
ROWE YANKEE REACTOR
SEABROOK-1 REACTOR
SEABROOK-2 REACTOR
SHOREHAM REACTOR
SURRY-1 REACTOR
SUSQUEHANNA-1 REACTOR
SUSQUEHANNA-2 REACTOR
THREE MILE ISLAND-2 REACTOR
ZION-1 REACTOR
ZION-2 REACTOR
ACCIDENTS
ENRICHED URANIUM REACTORS
HAZARDS
HEALTH HAZARDS
POWER REACTORS
PROCESS HEAT REACTORS
REACTOR ACCIDENTS
REACTORS
SAFETY
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR SAFETY
RISK ASSESSMENT
PWR TYPE REACTORS
PROBABILISTIC ESTIMATION
BIG ROCK POINT REACTOR
FISSION PRODUCT RELEASE
INDIAN POINT-2 REACTOR
INDIAN POINT-3 REACTOR
LIMERICK-1 REACTOR
LIMERICK-2 REACTOR
LOSS OF COOLANT
MC GUIRE-1 REACTOR
MC GUIRE-2 REACTOR
MIDLAND-1 REACTOR
MIDLAND-2 REACTOR
MILLSTONE-3 REACTOR
OCONEE-3 REACTOR
PEACH BOTTOM-2 REACTOR
RADIATION HAZARDS
REACTOR CORE DISRUPTION
ROWE YANKEE REACTOR
SEABROOK-1 REACTOR
SEABROOK-2 REACTOR
SHOREHAM REACTOR
SURRY-1 REACTOR
SUSQUEHANNA-1 REACTOR
SUSQUEHANNA-2 REACTOR
THREE MILE ISLAND-2 REACTOR
ZION-1 REACTOR
ZION-2 REACTOR
ACCIDENTS
ENRICHED URANIUM REACTORS
HAZARDS
HEALTH HAZARDS
POWER REACTORS
PROCESS HEAT REACTORS
REACTOR ACCIDENTS
REACTORS
SAFETY
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled