摘要
选择失去主给水、失去厂外电和正常运行情况下控制棒失控提升3个典型的导致未能紧急停堆的预期瞬变(ATWS)的初因事故,采用自行研制的基于SCDAP/RELAP5/MOD3.1的核反应堆严重事故分析平台,对秦山一期核电站ATWS初因导致堆芯熔化严重事故进程进行了分析研究,对防止ATWS导致堆芯熔化进程的缓解措施的有效性进行了验证。计算分析结果表明,二回路补水和一回路卸压的事故缓解措施能有效地阻止堆芯熔化进程。
By using a simulator based on SCDAP/RELAP5/MOD3.1 computer code, the core damage progression and the effectiveness of preventive and mitigation measures are analyzed with the anticipated transients without scram (ATWS) sequences caused by the loss of main feed water (LOFW), the loss of off-site power (LOOP) and uncontrolled rod cluster control assembly (RCCA) bank withdrawal, combined with the failure of reactor control and protection system in Qinshan Nuclear Power Plant (NPP) unit1.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2005年第3期209-213,218,共6页
Nuclear Power Engineering
