耦合S-CO_(2)布雷顿循环的自然循环铅冷快堆控制策略研究

Study on Control Strategy of Natural Circulation Lead-cooled Fast Reactor Coupled with S-CO_(2) Brayton Cycle

自然循环铅冷快堆与超临界二氧化碳(S-CO_(2))布雷顿循环耦合发电系统是未来先进核能系统的发展方向。基于Apros软件搭建了该耦合发电系统的动态模型,并设计了2种反应堆控制方案,一种为参考压水堆堆芯功率控制系统的常规控制方案,另一种为添加控制棒棒位限制的补偿控制方案。研究结果表明,在3%FP/min(FP为满功率)的小变负荷速率下,2种控制方案下的负荷跟随动态偏差皆在-2%~1%之间,但对于堆芯出口冷却剂温度的稳定,补偿控制方案优于常规控制方案;在6%FP/min~18%FP/min的大变负荷速率下,常规控制方案下的堆芯出口温度变化幅度为-40~0℃,而补偿控制方案下的堆芯出口温度的变化幅度为-5~2℃。因此,补偿控制方案可作为自然循环铅冷快堆控制的有效手段。

The coupled power generation system of natural circulation lead cooled fast reactor with supercritical carbon dioxide(S-CO_(2))Brayton cycle is the development trend of advanced nuclear energy systems in the future.Based on the software Apros,a dynamic model of the coupled power generation system was built,and two reactor control schemes were designed,one of which was the conventional control scheme of the reference core power control system of pressurized water reactor,and the other was the compensation control scheme with rod position limit of control rods.The research results showed that under a small variable load rate of 3%FP/min(FP is short for full power),the dynamic deviation of load following under both control schemes was between−2%and 1%,however,for the stability of core outlet coolant temperature,the compensation control scheme was superior to the conventional control scheme;at a large variable load rate of 6%FP/min-18%FP/min,the variation range of core outlet temperature under conventional control was−40℃-0℃,while the variation range of the core outlet temperature under compensation control was−5℃-2℃.Therefore,the compensation control scheme can be used as an effective means for the control of natural circulation lead cooled fast reactor.