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Accident simulation and control strategy of feedwater system of sodium-cooled fast reactor
Progress in Nuclear Energy ( IF 2.7 ) Pub Date : 2024-04-17 , DOI: 10.1016/j.pnucene.2024.105214
Aodi Sun , Muping Li , Shuhan Yang , Peiwei Sun , Xinyu Wei

Improper operation leading to an emergency shutdown in a nuclear power plant can result in significant energy loss and have a substantial impact on the economy. This study focuses on a sodium-cooled fast reactor (SFR) nuclear power plant, analyzing system characteristics under different accidents through feedwater system simulation and improving control system performance. The results show that the single module accident will affect the whole feedwater system, and the influence of faulty SG on the loop signal should be eliminated. The improved control system reduces sodium temperature fluctuation by 3%–41.5%, shortens adjustment time by 57.9%, and ensures standby pump activation within 10 s after the feedwater pump trips or when the system stabilizes. Although the feedforward of mass flowrate ratio can improve the response of the system to flow disturbance, it resists the temperature feedback. However, considering inlet temperature's impact on feedwater demand, this confrontation can be effectively avoided, and a good control effect can be maintained during accidents.

中文翻译:

钠冷快堆给水系统事故模拟及控制策略

操作不当导致核电站紧急关闭可能会导致大量能源损失,并对经济产生重大影响。本研究以钠冷快堆(SFR)核电站为研究对象,通过给水系统仿真分析不同事故下的系统特性,提高控制系统性能。结果表明,单模块事故会影响整个给水系统,应消除SG故障对回路信号的影响。改进后的控制系统使钠温波动降低3%~41.5%,调节时间缩短57.9%,保证给水泵跳闸或系统稳定后10 s内启动备用泵。质量流量比前馈虽然可以改善系统对流动扰动的响应,但它会抵制温度反馈。但考虑到入口温度对给水需求的影响,可以有效避免这种对抗,并且在事故发生时仍能保持良好的控制效果。
更新日期:2024-04-17
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