초록

중수형원자로의 안전성평가에 적용된 기술 기준을 검토하고 국내 중수형 원자로 건설이후 발간된 캐나다 기술기준 적용 현황을 확인하였음.
최신 기술기준에 명시된 설계기준초과사고 분석에 관한 요건을 확인하여 설계기준초과사고 분석을 수행함.
설계기준초과사고로 후쿠시마 사고와 같이 모든 전력이 상실되는 사고를 분석하였으며, 분석을 위하여 필요한 모델을 생산하였고 사고 발생 시 피동형 기기만이 작동되는 것으로 가정하여 발전소 거동을 모사하였음. 모사 결과 안전 목표 달성을 위해 필요한 운전원 조치를 검토하였음.

Abstract ▼

Ⅳ RESULTS
Simulated system behavior of Wolsong Unit 1 in the case of loss of all electric powers and heat sink applying best-estimate analysis methodology based on Beyond Deisgn Basis Accident analysis methodology of RD-310. Some analysis models needed for the analysis was developed and accident

Ⅳ RESULTS
Simulated system behavior of Wolsong Unit 1 in the case of loss of all electric powers and heat sink applying best-estimate analysis methodology based on Beyond Deisgn Basis Accident analysis methodology of RD-310. Some analysis models needed for the analysis was developed and accident mitigation strategy to maintain safety function for the prevention of the environmental release of nuclear fission product was suggested.
The cooling of the core is considered through the circulation of primary and secondary coolant system. Among these, more appliable action is to feed the coolant continuously to secondary side of steam generator. In the case of loss of coolant, the emergency water is to be supplied to the primary system.
The water in feedwater storage tank, condensate storage tank, dousing tank, emergency water system is available and the mobile diesel pump car can be used in the long term.