Probabilistic safety analysis V. Interim report. [PWR; BWR]
The development of probabilistic risk assessment methods and their application within the industry is described. Two risk assessment workshops is described. A summary of a recent EPRI report comparing the Lewis Committee review of the Reactor Safety Study with earlier EPRI reviews reveals general agreement. Progress in fault tree methodology and code development is summarized. Two analyses related to anticipated transients without scram are reported. Sensitivity studies to determine the economic and risk reduction value of LWR safety features are documented. Two new consequence codes, one to predict time-dependent post-LOCA containment conditions and one to calculate radiation doses to internal organs, are described. The status report of the EPRI fuel cycle risk assessment is summarized. Progress in establishing earthquake strong motion are described. Finally, rapid response efforts following the accident at Three Mile Island are reported.
- Research Organization:
- Science Applications, Inc., Palo Alto, CA (USA)
- OSTI ID:
- 5652273
- Report Number(s):
- EPRI-NP-1275
- Country of Publication:
- United States
- Language:
- English
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ATWS
BWR TYPE REACTORS
FAULT TREE ANALYSIS
FUEL CYCLE
PROBABILITY
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RISK ASSESSMENT
SAFETY
SEISMIC EFFECTS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS