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The building fragilities are for the Zion Unit 1 reactor which was the specific plant used for development of methodology in the program. more » Both building and component fragilities are covered. This report describes the development of the required fragility relations and the data sources and data reduction techniques upon which they are based. These calculations require a knowledge of the probability of failure (fragility) of safety-related components in the reactor system which actively participate in the hypothesized accident scenarios. As part of this program, calculations of the seismic risk from a typical commercial nuclear reactor are being made. The Seismic Safety Margins Research Program is an NRC-funded program directed towards estimating the conservatism in the NRC Standard Review Plan seismic safety requirements with the ultimate goal of developing improved requirements. Some of the component fragilities are site-specific also, but most would be usable for other sites as well.Īuthors: Cover, L E Bohn, M P Campbell, R D Wesley, D A Publication Date: Research Org.: Lawrence Livermore National Lab., CA (USA) OSTI Identifier: 5313138 Report Number(s): NUREG/CR-3558 UCRL-53455 ON: DE84007790 DOE Contract Number: W-7405-ENG-48 Resource Type: Technical Report Resource Relation: Other Information: Portions are illegible in microfiche products Country of Publication: United States Language: English Subject: 22 GENERAL STUDIES OF NUCLEAR REACTORS 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS BWR TYPE REACTORS CONTAINMENT BUILDINGS REACTOR COMPONENTS SEISMIC EFFECTS STRESS ANALYSIS NUCLEAR POWER PLANTS PWR TYPE REACTORS FISSION PRODUCT RELEASE RISK ASSESSMENT DAMAGE ENGINEERED SAFETY SYSTEMS FAILURES REACTOR SAFETY BUILDINGS CONTAINMENT NUCLEAR FACILITIES POWER PLANTS REACTORS SAFETY THERMAL POWER PLANTS WATER COOLED REACTORS WATER MODERATED REACTORS 220900* - Nuclear Reactor Technology- Reactor Safety 210100 - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water = , Both building and component fragilities are covered.
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These calculations required a knowledge of the probability of failure (fragility) of safety-related components in the reactor system which actively participate in the hypothesized accident scenarios. As part of this program, calculations of the seismic risk from a typical commercial nuclear reactor were made. The Seismic Safety Margins Research Program (SSMRP) has a gola to develop a complete fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant.