CAJ | 학술논문

通过对各时期核电厂（二代、二代加和三代）未能紧急停堆的预期瞬态（ATWT）缓解系统进行分析和总结，将三者的ATWT缓解系统AMSAC、DAC和DAS分别从系统功能和系统结构角度进行比较与分析。结果发现它们在系统功能和系统结构上存在明显的差异，AP1000核电厂DAS与AMSAC、DAC相比在系统功能和系统结构上有一定的改进和提升。
통과대각시기핵전엄（이대、이대가화삼대）미능긴급정퇴적예기순태（ATWT）완해계통진행분석화총결，장삼자적ATWT완해계통AMSAC、DAC화DAS분별종계통공능화계통결구각도진행비교여분석。결과발현타문재계통공능화계통결구상존재명현적차이，AP1000핵전엄DAS여AMSAC、DAC상비재계통공능화계통결구상유일정적개진화제승。
ATWT mitigation systems in generation Ⅱ ,Ⅱ plus and Ⅲ nuclear power plants were separately analyzed and summarized ,and then ,from the system functions and system configuration perspective ,AMSAC ,DAC and DAS were separately contras‐ted and analyzed .The results show that there are significant differences among them , and compared with AMSAC and DAC the system function and configuration of AP 1000 nuclear power plant DAS are obviously enhanced .