Overview of methodology used for NUREG-1150 risk analyses
Conference
·
OSTI ID:6416491
Five probabilistic risk assessment (PRAs) form the basis for the conclusions in the recent Nuclear Regulatory Commission's report ''Severe Accident Risks: An Assessment for Five US Nuclear Power Plants'' (NUREG-1150). Four of the five PRAs were conducted at Sandia National Laboratories (SNL); the fifth was conducted at Idaho National Engineering Laboratory and Brookhaven National Laboratory. The analysis methods used for the risk analyses were developed at SNL. This paper describes those methods and how they differ from methods used in other PRAs. 16 refs., 2 figs., 1 tab.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6416491
- Report Number(s):
- SAND-88-2100C; CONF-890405-19; ON: DE89007421; TRN: 89-008357
- Resource Relation:
- Conference: International topical meeting on probability, reliability and safety assessment, Pittsburgh, PA, USA, 2 Apr 1989; Other Information: Paper copy only, copy does not permit microfiche production
- Country of Publication:
- United States
- Language:
- English
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· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6416491
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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GRAND GULF-2 REACTOR
PEACH BOTTOM-1 REACTOR
PEACH BOTTOM-2 REACTOR
PEACH BOTTOM-3 REACTOR
SEQUOYAH-1 REACTOR
SEQUOYAH-2 REACTOR
SURRY-1 REACTOR
SURRY-2 REACTOR
SURRY-3 REACTOR
SURRY-4 REACTOR
ZION-1 REACTOR
ZION-2 REACTOR
DATA COVARIANCES
REACTOR ACCIDENTS
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SYSTEMS ANALYSIS
ACCIDENTS
BWR TYPE REACTORS
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
POWER REACTORS
PWR TYPE REACTORS
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SAFETY
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
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Light-Water Moderated
Boiling Water Cooled
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