钠冷快堆换料系统可靠性研究

由于中子通量以及冷却剂运行温度高，钠冷快中子反应堆（简称钠冷快堆）的换料周期较一般轻水反应堆短。同时，换料过程中隔绝空气的要求以及换料设备本身的复杂性，钠冷快堆只能逐根进行换料，使得总的换料时间较轻水反应堆长。本文采用失效模式与影响分析、故障树分析等方法对典型钠冷快堆换料系统各部分的可靠性进行评价，获得了换料系统每次换料期间的失效概率。基于换料系统各部分失效的影响、失效概率以及恢复时间，分析了换料系统不同失效模式对反应堆运行效率的影响。

Refueling System Reliability Research about Sodium-cooled Fast Reactor

The refueling period of sodium-cooled fast reactor is shorter than that of general light water reactor due to the high neutron flux and high coolant operating temperature. At the same time, sodium-cooled fast reactor can only be refueled root by root due to the requirement of air isolation in the refueling process and the complexity of the refueling system itself, which makes the total refueling time longer than the light water reactor. The reliability of each part of the refueling system of a typical sodium-coolant fast reactor by failure mode and effects analysis, fault tree analysis and other methods were evaluated in this study. At finally, the failure probability of the refueling system during each refueling was obtained, and the reactor operation availability influence by the refueling system failure was also assessed, through analysing the failure probability and recovery time of different failure modes.