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Park, Soo Yong; Choi, Young; Kim, Dong Ha
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)2004
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)2004
AbstractAbstract
[en] This report contains analysis methodologies and calculation results of loss of offsite sequences for the severe accident analysis database system. The Korean standard nuclear power plant has been selected as a reference plant. Based on the probabilistic safety analysis of the corresponding plant, twelve accident scenarios, which was predicted to have more than 10-10 /ry occurrence frequency, have been analyzed as base cases for the loss of offsite sequence database. The functions of the severe accident analysis database system will be to make a diagnosis of the accident by some input information from the plant symptoms, to search a corresponding scenario, and finally to provide the user phenomenological information based on the pre-analyzed results. The MAAP calculation results of loss of offsite sequence in this report will be utilized as input data of the severe accident analysis database system
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Feb 2004; 84 p; Available from Korea Atomic Energy Research Institute, Taejon (Korea, Republic of); 3 refs, 181 fig, 8 tabs
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