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Thermal-hydraulic calculations using MARS code applied to low power and shutdown probabilistic safety assessment in a PWR
Authors:Young-Seok Son  Jee-Young Shin  Ho-Gon Lim  Jin-Hee Park  Seung-Cheol Jang
Affiliation:aSchool of Mechanical Engineering, Dong-Eui University, 995 Eomgwangno, Busanjin-Gu, Busan 614-714, South Korea;bKorea Atomic Energy Research Institute, 150 Deokjin-Dong, Yuseong-Gu, Daejeon 305-353, South Korea
Abstract:The methods developed for full-power probabilistic safety assessment, including thermal-hydraulic methods, have been widely applied to low power and shutdown conditions. Experience from current low power and shutdown probabilistic safety assessments, however, indicates that the thermal-hydraulic methods developed for full-power probabilistic safety assessments are not always reliable when applied to low power and shutdown conditions and consequently may yield misleading and inaccurate risk insights. To increase the usefulness of the low power and shutdown risk insights, the current methods and tools used for thermal-hydraulic calculations should be examined to ascertain whether they function effectively for low power and shutdown conditions. In this study, a platform for relatively detailed thermal-hydraulic calculations applied to low power and shutdown conditions in a pressurized water reactor was developed based on the best estimate thermal-hydraulic analysis code, MARS2.1. To confirm the applicability of the MARS platform to low power and shutdown conditions, many thermal-hydraulic analyses were performed for the selected topic, i.e. the loss of shutdown cooling events for various plant operating states at the Korean standard nuclear power plant. The platform developed in this study can deal effectively with low power and shutdown conditions, as well as assist the accident sequence analysis in low power and shutdown probabilistic safety assessments by providing fundamental data. Consequently, the resulting analyses may yield more realistic and accurate low power and shutdown risk insights.
Keywords:Abbreviations: ADV  atmospheric dump valve  ICI  in-core instrumentation  LPSD  low power and shutdown  LTOP  low temperature over pressure  MSIV  main steam isolation valve  POS  plant operating state  PSA  probabilistic safety assessment  RCP  reactor coolant pump  RCS  reactor coolant system  RIR  risk informed regulation  SCS  shutdown cooling system  SG  steam generator
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