Reactor Materials Program process water piping indirect failure frequency
Following completion of the probabilistic analyses, the LOCA Definition Project has been subject to various external reviews, and as a result the need for several revisions has arisen. This report updates and summarizes the indirect failure frequency analysis for the process water piping. In this report, a conservatism of the earlier analysis is removed, supporting lower failure frequency estimates. The analysis results are also reinterpreted in light of subsequent review comments.
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035; AC09-76SR00001
- OSTI ID:
- 7189837
- Report Number(s):
- WSRC-RP-89-432; ON: DE93004545
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PIPES
FAILURES
PRODUCTION REACTORS
LOSS OF COOLANT
FAILURE MODE ANALYSIS
PROBABILITY
REACTOR COOLING SYSTEMS
REACTOR SAFETY
SAVANNAH RIVER PLANT
SEISMIC EFFECTS
ACCIDENTS
COOLING SYSTEMS
NATIONAL ORGANIZATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PIPES
FAILURES
PRODUCTION REACTORS
LOSS OF COOLANT
FAILURE MODE ANALYSIS
PROBABILITY
REACTOR COOLING SYSTEMS
REACTOR SAFETY
SAVANNAH RIVER PLANT
SEISMIC EFFECTS
ACCIDENTS
COOLING SYSTEMS
NATIONAL ORGANIZATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors