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Development of linked analysis system for PWR severe accidents utilizing RELAP5 and MAAP4
Authors:Chang-Hwan Park  Ji-Han Chun  Kune-Yull Suh  Goon-Cherl Park  Un-Chul Lee
Affiliation:1. Nuclear Power Plant Safety Research Department, FNC Technology Co. Ltd., Republic of Korea;2. SMART Development Technology Validation, Korea Atomic Energy Research Institute, Republic of Korea;3. Department of Nuclear Engineering, Seoul National University, Republic of Korea
Abstract:The purpose of this study is to develop a severe accident (SA) analysis method that is more reliable thorough transferring the physical status of the plant predicted by RELAP5 computer code to MAAP4 computer code. The methodology of the linkage analysis is developed and the criterion of linkage time is suggested to utilize the RELAP5 thermal–hydraulic calculation to the maximum degree possible and thereby guarantee the continuity of calculation for hydrogen generation. The MAAP4 calculations after data transfer show the physically proper results based on RELAP5 data. Comparison with other code results for TMI-2 accident reveals that the result from the RELAP5–MAAP4 linked analysis lay in the span given by a number of results of TMI calculation from other SA code systems. The results of this study are expected to improve the SA analysis methodology by analyzing an SA scenario with more reliable thermal–hydraulic initial conditions.
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