摘要
停堆功率水平对主蒸汽管道破口质能释放速率和释放总量影响较大,因此有必要研究分析主蒸汽管道破裂事故工况下停堆功率对安全壳完整性影响,以得到安全壳失效的安全裕度。应用非能动安全壳分析程序,建立了大功率非能动反应堆非能动安全壳冷却系统的热工水力模型,并以主蒸汽管道断裂事故为基准研究对象,研究了不同停堆功率水平下安全壳的响应。分析结果表明,保持设计液膜覆盖率,停堆功率为30%额定功率时安全壳内压力峰值最高;随着壳外液膜覆盖率降低,停堆功率为0%额定功率对应的安全壳内压力峰值增高但安全壳不会失效;干壳时,停堆功率为0%额定功率时安全壳超压失效。
The Scram power level has significant influence on the steam rate and amount released from the break in main steam pipeline.In order to figure out the safety margin of the containment failure in accident conditions,it is necessary to research and analyze the effects of scram power level on the containment integrity.The thermal-hydraulic model of Passive Containment Cooling System has been built with passive containment analysis code in Large Power Passive Reactor.Based on the basis accident of Main Steam Line Break(MSLB),the containment responses to the different scram power level have been carried out.The analysis results show that:(1)the containment pressure is highest when scram power level is 30%of Fission Power(FP)under keeping the design water film coverage;(2)with decrease of water film coverage,the containment does not fail as a result of overpressure,although the pressure is highest on the scram power level 0%FP;(3)the containment failure could occur without cooling water outside the containment surface on the power level 0%FP.
作者
石兴伟
胡健
雷蕾
乔雪冬
温丽晶
刘福东
SHI Xing-wei;HU Jian;LEI Lei;QIAO Xue-dong;WEN Li-jing;LIU Fu-dong(Nuclear and Radiation Safety Center,MEP,Beijing 100082,China)
出处
《核科学与工程》
CAS
CSCD
北大核心
2018年第5期850-854,共5页
Nuclear Science and Engineering
基金
国家科技重大专项项目资助(2015ZX06002007)
