CAJ | 학술논문

针对船用压水堆建立反应堆主要系统和堆舱的热工水力计算模型。以主冷却剂管道破口事故为假想事故，利用该模型对事故过程进行仿真计算，重点分析了事故后堆舱压力的响应情况，比较了舱室喷淋、泄压箱和过滤排放3种堆舱泄压措施的效果。分析结果表明：事故发生后如无缓解措施，堆舱压力将很快超出限值，此时采用堆舱喷淋将是一种较为有效的泄压措施。
침대선용압수퇴건립반응퇴주요계통화퇴창적열공수력계산모형。이주냉각제관도파구사고위가상사고，이용해모형대사고과정진행방진계산，중점분석료사고후퇴창압력적향응정황，비교료창실분림、설압상화과려배방3충퇴창설압조시적효과。분석결과표명：사고발생후여무완해조시，퇴창압력장흔쾌초출한치，차시채용퇴창분림장시일충교위유효적설압조시。
According to the characteristics of a marine nuclear power plant,an analysis model is estab-lished to calculate thermal-hydraulic characteristics of main reactor systems and reactor compartment.As-suming that the break loss of coolant accident is the benchmark accident.The accident process is simulated using the established model.This paper focuses on the analysis of pressure response characteristic of reac-tor compartment.Three depressurization measures including spray,depressurization box and filtration dis-charge are compared.The calculation results show that if no effective measures are used after the accident occurs,pressure in reactor compartment will overstep the bounds of safe quickly.At this time,spray is an effective measure to depressurization in reactor compartment.