示范快堆正常余热导出方式优化研究

Study on Optimization of the Normal Waste Heat Export Mode of the Demonstration Fast Rea

基于示范快堆1号机组正常余热导出系统单独设置(非安全级),实现将反应堆停堆检修或换料时用7天时间导出堆芯余热。由于钠冷快堆的特殊性,无法像压水堆那样利用辅助给水、大气释放阀导出堆芯余热,提前释放常规岛水汽和冷源系统检修窗口,为此设计了LBN系统并配置循环冷却塔、热交换器、循环水泵、管道、阀门以及仪表控制设备,以达到堆芯余热导出和提前释放三回路系统检修窗口目的,但经过对三回路系统设计及汽轮发电机组和三回路系统整体停役检修窗口研究分析,借鉴压水堆的经验可以通过循环水泵—凝汽器或循环水泵—闭式冷却水余热导出方式取代正常余热导出系统,从而实现利用已有系统设备实现堆芯余热导出,节省前期投资和后期运维成本,对2号机组设计优化具有借鉴意义。

Based on the normal waste heat export system of Unit 1of the demonstration fast reactor(non-safety level),it is possible to remove the residual heat of the reactor core in 7days of the refueling outage.Due to the particularity of the sodium-cooled fast reactor,it is impossible to use auxiliary feed water and atmospheric release valves to remove the residual heat of the reactor core,release the conventional island water vapor and the maintenance window of the cooling source system in advance,and design the LBN system and configure the cycle cooling towers,heat exchangers,circulating water pumps,pipes,valves,and I&C equipment are used to remove the residual heat of the reactor core and release the inspection window of the three-circuit system in advance.The study and analysis of the overall shutdown and maintenance window of the three-circuit system,drawing on the experience of the pressurized water reactor,the normal residual heat removal system can be replaced by the circulating water pump-condenser or the circulating water pump-closed cooling water residual heat removal method,so as to realize the utilization of the existing residual heat.There are systematic equipment to realize the removal of residual heat of the reactor core,which saves the initial investment and the later operation and maintenance cost,which could serve as reference for the design optimization of Unit 2.