Thermal-hydraulic calculations using MARS code applied to low power and shutdown probabilistic safety assessment in a PWR |
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Authors: | Young-Seok Son Jee-Young Shin Ho-Gon Lim Jin-Hee Park Seung-Cheol Jang |
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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 |
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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. |
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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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