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Holman, G.S.; Chou, C.K.; Cummings, G.E.
Lawrence Livermore National Lab., CA (USA)1985
Lawrence Livermore National Lab., CA (USA)1985
AbstractAbstract
[en] Current probabilistic risk assessment (PRA) methods for nuclear power plants utilize component fragilities which are for the most part based on a limited data base and engineering judgement. The seismic design of components is based on code limits and NRC requirements that do not reflect the actual capacity of a component to resist failure. In order to improve the present component fragility data base and establish component seismic design margins, the NRC has commissioned a projected three-year program to compile existing fragilities data and at the same time independently perform fragilities tests on selected mechanical and electrical components. This paper presents the planning and technical approach being taken by LLNL in the NRC Component Fragility Program
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1985; 13 p; 8. international conference on structural mechanics in reactor technology; Brussels (Belgium); 19-23 Aug 1985; CONF-850809--30; Available from NTIS, PC A02/MF A01 as TI85008970
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