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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.