Large break frequency for the SRS (Savannah River Site) production reactor process water system
- 1. Westinghouse Savannah River Co., Aiken, SC (USA)
- 2. Review and Synthesis Associates, Richland, WA (USA)
Description
The objective of this paper is to present the results and conclusions of an evaluation of the large break frequency for the process water system (primary coolant system), including the piping, reactor tank, heat exchangers, expansion joints and other process water system components. This evaluation was performed to support the ongoing PRA effort and to complement deterministic analyses addressing the credibility of a double-ended guillotine break. This evaluation encompasses three specific areas: the failure probability of large process water piping directly from imposed loads, the indirect failure probability of piping caused by the seismic-induced failure of surrounding structures, and the failure of all other process water components. The first two of these areas are discussed in detail in other papers. This paper primarily addresses the failure frequency of components other than piping, and includes the other two areas as contributions to the overall process water system break frequency
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Additional details
Publishing Information
- Imprint Title
- Second DOE natural phenomena hazards mitigation conference
- Imprint Pagination
- 436 p.
- Journal Page Range
- p. 375-380.
- Report number
- CONF-8910192--
Conference
- Title
- 2. DOE natural phenomena hazards mitigation conference.
- Dates
- 3-5 Oct 1989.
- Place
- Knoxville, TN (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23008472
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ISOTOPE PRODUCTION REACTORS; MITIGATION; PIPES; PRIMARY COOLANT CIRCUITS; RISK ASSESSMENT; SAVANNAH RIVER PLANT; SEISMIC EFFECTS; SYSTEM FAILURE ANALYSIS
- Descriptors DEC
- COOLING SYSTEMS; IRRADIATION REACTORS; NATIONAL ORGANIZATIONS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SYSTEMS ANALYSIS; US AEC; US DOE; US ERDA; US ORGANIZATIONS