节点文献
蒸汽稳压器控制系统的仿真研究
Simulation Study of Control System for Nuclear Steam Pressurizer
【摘要】 介绍了核蒸汽稳压器的动力学模型,分析其在负荷扰动,温度扰动下的动态特性,研究工程实时控制策略,优化控制系统各部件参数.仿真试验表明此控制系统性能完全能满足工程设计要求
【Abstract】 This paper introduces a dynamics model of nuclear steam pressurizer and analyzes its dynamic characteristic under some load and temperature disturbance.Also engineering control algorithm and optimal control parameters for all system packs are determined.Result of simulation tests show that the performances of this control system are satisfactory to engineering design.
【关键词】 压水堆;
核蒸汽发生器;
压力安全系统;
【Key words】 PWR type reactors; nuclear steam generator; pressure safety system;
【Key words】 PWR type reactors; nuclear steam generator; pressure safety system;
- 【文献出处】 哈尔滨船舶工程学院学报 , 编辑部邮箱 ,1992年01期
- 【分类号】TL421.1
- 【被引频次】6
- 【下载频次】175