摘要
采用一体化事故分析程序建立了包括主冷却剂系统、专设安全设施、安全壳系统和非能动安全壳冷却系统(PCS)的海阳核电一期工程核电厂模型,对核电厂压力容器直接注射(DVI)管线破裂、冷段双端断裂、自动卸压系统(ADS)误启动、热段2英寸破口等严重事故序列进行了模拟计算,分析反应堆系统的热工水力行为。并通过安全壳系统的压力和温度响应,分析了非能动安全壳冷却系统在严重事故工况下的冷却能力。计算表明,对于分析的严重事故工况,在72h内,PCS的冷却能力能够保持安全壳内压力和温度处于较低水平,可以保障安全壳完整性。分别针对PCS水膜覆盖率以及环境温度对PCS冷却效果进行了敏感性分析,表明水膜覆盖率降低和环境温度升高均会使PCS冷却能力降低,安全壳内压力升高,但均未超出其设计压力。
With integrated analysis code,a model of Haiyang nuclear power plant including the reactor coolant system（RCS）,engineered safety features（ESFs）,containment system and passive containment cooling system（PCS）has been built.To analyze the cooling ability of PCS under severe accidents,four sequences of DVI break accident,double ended cold leg LOCA,ADS4 spuriously open accident and hot leg 2-inch LOCA are simulated.The thermal-hydraulic characteristics of RCS are analyzed and the heat removal capacity of PCS is investigated based on the containment pressure and temperature response.The results show that the containment pressure and temperature are relatively low within 72 hours,and the containment integrity is maintained.The factors of film coverage and environment temperature influenced on the PCS heat removal capacity is implemented,which shows that with the reduced film coverage or increased environment temperature can reduce the PCS cooling capacity,causing a higher containment pressure,which is still lower than the containment design pressure.
出处
《核科学与工程》
CSCD
北大核心
2014年第4期530-536,共7页
Nuclear Science and Engineering
关键词
严重事故
非能动安全壳冷却系统
敏感性分析
severe accident
passive containment cooling system
sensitivity analysis
