摘要
针对示范快堆每个环路设置多个直流式蒸汽发生器模块的特点,提出集中控制环路给水流量和单独控制环路内各模块给水流量的控制方案,并搭建了给水控制系统的仿真模型;分别对2种给水控制方案进行仿真研究,分析在2种给水控制方案下各模块蒸发器出口钠温和蒸汽过热度的变化规律。研究结果表明:集中控制环路给水流量的控制方案更有利于保证蒸发器出口蒸汽过热度的安全限值,而单独控制环路内各模块给水流量的控制方案更有利于蒸发器出口钠温的控制。
Demonstration Fast Reactor sets up eight once-through steam generators in each circuit, and based on that, two designs of feed water control system are proposed. The first is to control the total water in each circuit, and the second is to control the water of each module. The simulation models of the two feed water systems are built, and the process of sodium temperature and steam superheat at evaporator outlet is analyzed. The results show that the first design scheme helps to stabilize the steam superheat at evaporator outlet, and the second scheme facilitates the control of the sodium temperature at evaporator outlet.
作者
毕德瑞
段天英
张厚明
贾玉文
刘勇
Bi Derui;Duan Tianying;Zhang Houming;Jia Yuwen;Liu Yong(China Institute of Atomic Energy,Beijing,102413,China;North Regional Office of Nuclear and Radiation Safety Inspection,National Nuclear Safety Administration,Beijing,100191,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2020年第3期158-163,共6页
Nuclear Power Engineering
关键词
钠冷快堆
多模块
直流式蒸汽发生器
给水控制
Sodium-cooled fast breeder reactor
Multi-module
Once-through steam generator
Feed water control