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第三代AP1000非能动核电厂的主要特征是采用非能动安全原理,使核电厂的系统、设备、构筑物大幅度简化,安全性、可靠性、经济性大幅度提高,以满足美国先进轻水堆业主要求文件的基本要求。本文针对美国业主要求文件(Utility Requirements Document,URD)第三卷第五章《专设安全系统》中对非能动先进轻水堆核电厂反应堆冷却剂系统压力控制功能的要求:在很小的反应堆冷却剂系统(Reactor Coolant System,RCS)净泄漏率(不大于2.27 m3·h-1)条件下,具有足够的系统冷却剂装量及补水能力,以保证在8 h(28 800 s)内不会触发自动降压系统而进行计算分析,本分析采用安全分析报告小破口失水事故(Loss of coolant accident,LOCA)分析采用的NOTRUMP程序,分析结果表明AP1000核电厂可满足上述美国URD要求。
The main features of the third-generation AP1000 passive nuclear power plant are the passive safety principle, which greatly simplifies the system, equipment and structures of the nuclear power plant and greatly improves the safety, reliability and economy so as to meet the needs of the U.S. Advanced Light Water Reactor The owner requests the basic requirements of the document. In this paper, the pressure control function of the reactor coolant system in the passive advanced light water reactor nuclear power plant in Chapter 5 “Specialized Security System” of the US Utility Urged Document (URD) is described. In a very small reactor Reactor Coolant System (RCS) With a net leakage rate (not more than 2.27 m3 · h-1), it has enough system coolant capacity and water replenishment capacity to ensure that within 8 h (28 800 s) Will trigger the automatic depressurization system for calculation and analysis. The analysis uses the NOTRUMP program of the LOCA analysis, which shows that the AP1000 nuclear power plant can meet the above US URD requirements.