학위논문(박사) - 한국과학기술원 : 원자력및양자공학과, 2014.2, [ vi, 94 p. ]
CANDU-6; 감속재계통고장사고; 병렬연계; 열수력-원자로물리 연계해석; 안전해석 방법론; CANDU-6; Safety Analysis Method; Thermal hydraulics-Reactor PhysicsCoupling Analysis; Parallel Coupling; Moderator System Failure
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