CAJ | 학술논문

为了验证CPR1000核电站冷却剂失流事故（LOCA）下堆芯冷却监测系统（CCMS）压力容器水位（L VSL ）测量的有效性，对LOCA后影响动压和静压测量的物理现象，以及顶盖的特殊现象对 L VSL测量引入的误差进行了量化计算。结果表明，顶盖的特殊现象和冷管段或热管段破口流量对L VSL测量引入的误差在破口发生几分钟后可忽略，压力容器顶部破口流量以及控制棒导向管内水的滞留对L VSL测量引入很大的高估误差，结合状态导向事故处理程序SOP的分析表明，该高估误差不会阻碍事故处理安全重要操作的执行。
위료험증CPR1000핵전참냉각제실류사고（LOCA）하퇴심냉각감측계통（CCMS）압력용기수위（L VSL ）측량적유효성，대LOCA후영향동압화정압측량적물리현상，이급정개적특수현상대 L VSL측량인입적오차진행료양화계산。결과표명，정개적특수현상화랭관단혹열관단파구류량대L VSL측량인입적오차재파구발생궤분종후가홀략，압력용기정부파구류량이급공제봉도향관내수적체류대L VSL측량인입흔대적고고오차，결합상태도향사고처리정서SOP적분석표명，해고고오차불회조애사고처리안전중요조작적집행。
To assess the validity of the L VSL (vessel water level ) measurement of the CCMS (core cooling and monitoring system ) in CPR1000 nuclear power plants under condition of LOCA (loss of coolant accident ) ,the error of the L VSL measurement due to the post‐LOCA physical phenomenon w hich may have impact on the measurement of dynamic and static pressures ,and the special phenomenon in vessel‐head was quantita‐tively calculated . The analysis results show that several minutes after discharging through the break ,the error of the L VSL measurement induced by the special phenom‐enon in vessel‐head and cold‐leg or hot‐leg break flow rate can be ignored .The flow rate of the break on the vessel‐head and the stagnant water in the control rod guide tube will induce a significant over‐estimated error to the L VSL measurement .The analysis com‐bined with SOP (state oriented procedure) shows that the over‐estimated error will not hinder the implementation of the safety important actions for accident management .