摘要
为完善恰希玛核电厂二期工程的概率安全分析模型,在建立事件树模型时需结合电厂的实际情况进行相应的热工水力计算分析,以确定事件树的成功准则要求,并确定操纵员干预事故的允许时间要求。本文应用热工水力系统分析程序RELAP5/MOD3模拟分析论证了在SGTR事故二次侧安全阀卡开、辅助给水系统失效且仅一台高压安注有效工况下,如果操纵员在安注信号触发150min后采取相应措施实施反应堆冷却剂系统降温降压操作的事故过程。分析结果表明,在破损SG一、二次侧压力平衡在一个大气压,终止破口流量的过程中,反应堆堆芯被冷却剂有效淹没。
The Steam Generator Tube Rupture （SGTR） accident has been analyzed with RELAP5/MOD3 thermal hydraulic system analysis code under the conditions that the safety valve of affected SG is stuck open. The AFW is unavailable, and only one HPSI pump is available. It can be mitigated successfully if the operators take actions to cooldown and depressurize RCS within 150 min after the safety injection signal. The results show that the active core is covered by coolant before the break flow is terminated with the balance between primary and secondary side of affected SG at atmospheric pressure.
出处
《核技术》
CAS
CSCD
北大核心
2010年第2期98-100,共3页
Nuclear Techniques
