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냉각기능상실사고 시 사용후핵연료 저장조의 열수력적 거동 특성
전병국(Byong Guk Jeon),김기환(Ki Hwan Kim),김병재(Byung Jae Kim),김종록(Jong Rok Kim),박종국(Jong Kuk Park),문상기(Sang Ki Moon) 대한기계학회 2016 대한기계학회 춘추학술대회 Vol.2016 No.12
After the Fukushima nuclear power plant accident, several efforts have been made to ensure integrity of spent fuel pools as well as nuclear reactors under prolonged station blackout. Regardless of low individual decay heat level, release of radioactive materials from spent fuel pools can be tragic because of a large number of fuel assemblies. In this research, thermal hydraulic behavior and safety of fuel rods inside a subchannel of nuclear fuel under loss of cooling accidents were evaluated through a 5 by 5 heater rods - experiment. We chose three cases representing decay heat at 1 day, 1 week, and 1 month after shutdown, corresponding to 0.38 kW/rod, 0.21 kW/rod, and 0.11 kW/rod, respectively. At higher decay heat level, mixture water level was much escalated because of large void generation while the maximum rod temperature was increased fast. The vessel module, COBRA-TF, in the MARS code was assessed by comparing with the experiment result. The water mixture level as well as the wall temperature profile was not well represented by the code. The models are needed to be further improved.