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MARS-KS를 이용한 APR1400 노형의 저온과압보호 성능 평가
장원준(Won Jun Chang),정애주(Ae Ju Jeong),신병수(Byung Soo Shin) 대한기계학회 2015 대한기계학회 춘추학술대회 Vol.2015 No.11
This study is to assess the performance of low temperature overpressure protection for APR1400 nuclear power plant. The most severe possible transients for mass addition and energy addition are coolant injection by sudden startup of four safety injection pump and one charging pump and heat transfer from secondary side of steam generator by startup of one reactor coolant pump. The transients was analyzed using MARS-KS, 1-dimensional thermal hydraulic code. The initial condition was determined as the possible lowest temperature condition in order to maximize the expansion ratio of coolant. The modeling for numerical analysis was also conservative. From the analysis results, it was concluded that the design parameters of relief valve for LTOP was determined appropriately to maintain the peak pressure of reactor coolant system under the design envelope.
환기가 제한된 세 개 격실에서 Pool Fire에 대한 FDS 검증분석
배용범(Bae, Young-Bum),이상규(Lee, Sang-Kyu),신병수(Shin, Byung-Soo),김남석(Kim, Nam-Seok),금오현(Keum, O-Hyun),박종석(Park, Jong-Seok) 한국화재소방학회 2011 한국화재소방학회 학술대회 논문집 Vol.2011 No.춘계
This study aims to validate predictive capabilities of FDS for the pool fire in three rooms connected to ventilation network. The three rooms in real scale fire test facility are configured to be similar to that of nuclear power plant in size, ventilation condition, construction material, etc. Basically three rooms are confined to the other area except two open doors and two ventilation duct in each room. The real scale fire test was conducted with these conditions and the predictive capabilities of FDS will be validated by comparing FDS simulation results with experimental data from the temperature, heat flux, and concentration point of view. This study concludes that temperature from FDS is about 25 % lower deviation from the experiment, and heat flux from FDS is about 5% deviation.