CAJ | 학술논문

为进一步提高核电厂的安全性，并满足法规对严重事故缓解措施的要求，消除事故过程中大量积聚在反应堆压力容器顶部的不可凝结气体对机组安全造成的重大威胁，我国自主研发的百万千瓦级压水式反应堆在压力容器顶部增设了排放阀门，在事故中通过此路径将大量积聚在反应堆顶部的不可凝结气体排出，这个系统即为高位排气系统。该文通过程序模拟，分析了高位排气系统在运行过程中可能经历的压力载荷。计算结果显示在所分析的工况中，高位排气系统可能经历的过程包括气体到气体、气体到液体的排放，但总体压力载荷冲击幅度不大，不会对系统造成额外风险。
위진일보제고핵전엄적안전성，병만족법규대엄중사고완해조시적요구，소제사고과정중대량적취재반응퇴압력용기정부적불가응결기체대궤조안전조성적중대위협，아국자주연발적백만천와급압수식반응퇴재압력용기정부증설료배방벌문，재사고중통과차로경장대량적취재반응퇴정부적불가응결기체배출，저개계통즉위고위배기계통。해문통과정서모의，분석료고위배기계통재운행과정중가능경력적압력재하。계산결과현시재소분석적공황중，고위배기계통가능경력적과정포괄기체도기체、기체도액체적배방，단총체압력재하충격폭도불대，불회대계통조성액외풍험。
For the purpose that improve the safety of Nuclear Power Plant and meet the law request for severe accident mitigation measure,then avoid inadequate core cooling or impaired natural circulation resulting from the accumulation of non-condensable gases in the Reactor vessel head,the High Point Vent System is designed of 1000 MWe Nuclear Power Plant which is independence projected of China.The basic function of this system is to remove non-condensable gases or steam from the reactor vessel head.This paper will discuss the pressure change during of the high point vent system running transient state by code calculate.The results show that the pressure change is not a main risk for this system.