摘要
目前大型的压水堆核电站堆芯控制系统均设计有堆芯平均温度控制系统,该系统是一个闭环的控制系统,以稳定堆芯的平均温度为目标。该控制系统的正常运行,是保证反应堆安全稳定运行的前提和基础。作为被控对象,反应堆冷却剂平均温度的波动情况不仅是衡量该控制系统优劣的首要指标,同时也是直接影响控制系统稳定性的关键因素。总结众多压水堆核电站的运行经验,发现反应堆热管段温度的波动对反应堆平均温度控制系统影响巨大,有些甚至对反应堆的安全稳定运行造成严重影响。本文通过对具体工程案例的深入剖析、论证,归纳出热管段温度波动对堆芯平均温度控制系统影响的具体原理,为后续自主设计三代核电技术中的平均温度控制系统提供经验反馈。
At present,the average temperature control system is widely designed in the control system of pressurized water reactor.It is a closed-loop control system,and the main objective is to stabilize the average core temperature.The normal operation of this system is the premise and foundation for safe and operation of the reactor.As the control object,the average temperature fluctuation of the reactor coolant is not only the primary criterion for measuring the quality of the control system,but also the key factor that directly affects the stability of the control system.After summing up the operation experience of many PWR nuclear power plants,it is found that the hot leg temperature fluctuation has a great influence on the average temperature control system,and some even have a serious influence on the safe and stable operation of the reactor.Through the detailed analysis and study of real engineering cases,the specific mechanism of the serious influence of hot leg temperature on the average temperature control system is given,which provides empirical feedback for the subsequent independent design of three generations of nuclear power plants.
作者
商静
田亚杰
张云波
吕智宏
李天友
SHANG Jing;TIAN Yajie;ZHANG Yunbo;LV Zhihong;LI Tianyou(China Nuclear Power Design Company LTD.(Shen zhen),Shenzhen of Guangdong Prov.518026,China;Nuclear and Radiation Safety Center,Beijing 100082,China)
出处
《核科学与工程》
CAS
CSCD
北大核心
2019年第6期1061-1067,共7页
Nuclear Science and Engineering
关键词
反应堆堆芯功率控制
温度波动
平均温度控制系统
滤波时间常数
Reactor power control
Temperature fluctuation
Average temperature control system
Filter time constant