Identification of seismically risk-sensitive systems and components in nuclear power plants: feasibility study. [PWR; BWR]

Technical Report · Wed Jun 01 00:00:00 EDT 1983

DOI:https://doi.org/10.2172/5935871· OSTI ID:5935871

Azarm, M; Boccio, J; Farahzad, P

An approach for the identification of risk-sensitive components in a nuclear power plant during and after a seismic event is described. Application of the methodology to two hypothetical power plants - a Boiling Water Reactor and a Pressurized Water Reactor - are presented and the results are given in tabular and graphical form. Conclusions drawn and lessons learned through the course of this study, based on the relative importance of various accident scenarios and sensitivity analyses, are discussed. In addition, the areas that may need further investigation are identified.

• Research Organization: Brookhaven National Lab. (BNL), Upton, NY (United States)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5935871
• Report Number(s): NUREG/CR-3357; BNL-NUREG-51683; ON: DE83014631
• Resource Relation: Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

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FAILURES
REACTOR SAFETY
STRESS ANALYSIS
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