CAJ | 학술논문

反应堆压力容器（RPV）是核反应堆中不可替换的关键设备。田湾核电站在役前检查阶段，发现反应堆压力容器2＃焊缝存在超标缺陷，2＃焊缝处于堆芯筒体段，属强辐照区。为评价该缺陷的可接受性，采用有限元方法对反应堆压力容器2＃焊缝进行了承压热冲击分析，在分析中考虑了小破口失水事故和安全阀误开启这两种最严酷工况。计算结果表明：有限元分析的结果与外国专家推荐方法的计算结果基本吻合，且田湾核电站反应堆压力容器2＃焊缝寿期末的脆性转变温度小于最低容许脆性转变温度，能满足防脆断的设计要求。
반응퇴압력용기（RPV）시핵반응퇴중불가체환적관건설비。전만핵전참재역전검사계단，발현반응퇴압력용기2＃한봉존재초표결함，2＃한봉처우퇴심통체단，속강복조구。위평개해결함적가접수성，채용유한원방법대반응퇴압력용기2＃한봉진행료승압열충격분석，재분석중고필료소파구실수사고화안전벌오개계저량충최엄혹공황。계산결과표명：유한원분석적결과여외국전가추천방법적계산결과기본문합，차전만핵전참반응퇴압력용기2＃한봉수기말적취성전변온도소우최저용허취성전변온도，능만족방취단적설계요구。
The reactor pressure vessel (RPV) is an irreplaceable key equipment in nucle‐ar reactor .It was found that 2 # weld defects of RPV exceeded the standard in the Tianwan Nuclear Power Plant inspection stage .The 2 # weld was located in the core barrel ,which was strong radiation area .To evaluate the acceptability of defects ,the pressurized thermal shock analysis was done for 2 # weld of RPV using the finite element method ,which included small break loss of coolant accident and PRZ‐SV inad‐vertent opening .The calculation results show that the result of finite element analysis is coincided basically with results using foreign expert recommended method . The 2 #weld of RPV ,in which the brittle transition temperature of the final life is lower than that of the minimum allowable ,can be satisfied with the requirement of resistance to brittle fracture .