中国示范快堆安全壳热工设计参数分析及研究

The Containment Thermal Parameters Design and Study on China Demonstration Fast Reactor

核电厂安全壳是防止放射性物质泄漏的最后一道实体屏障,对缓解或降低严重事故的放射性后果起到关键作用。中国示范快堆的安全壳采用具有隔离功能和密封性功能等设计特点的厂房结构,合适地确定其设计基准是安全壳设计的首要问题。本文分析比较了世界钠冷快堆在安全壳设计时的内部机械载荷设计基准,提出示范快堆安全壳的设计应考虑假想堆芯解体事故(HCDA)及后续钠泄漏对安全壳的温度压力载荷影响。结合示范快堆的设计,确定了HCDA下安全壳内的事故情景。使用钠火分析软件对事故情景进行了热工计算,并对部分关键参数进行了敏感性分析。通过分析计算,得到示范快堆安全壳的热工设计参数。

The containment of nuclear power plant is the final physical barrier preventing the release of radioactive material.It plays a key role in mitigating the radioactive consequences during severe accidents.The containment of China demonstration fast reactor adopts a concept of concrete structure with the function of isolating and sealing.The first question of containment design is how to determine the design basis reasonably.This paper compares the inner mechanical load design basis of sodium cooled fast reactor containment in the world,and proposes that the pressure and temperature consequence of hypothetic core disrupture accident(HCDA)and subsequent sodium leakage to the containment should be considered.Combining the design of China demonstration fast reactor,the accident scenario in the containment is determined.Sodium fire analysis software is used for the calculation of the accident scenario,and sensitivity analysis is carried out for some key parameters.Based on the calculation and analysis,the thermal parameters of China demonstration fast reactor are determined.