基于状态空间模型的压水堆控制棒仿真实验
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摘要
为了让学生能更好地理解控制棒在反应堆堆芯中的作用,设计了压水堆控制棒仿真实验。基于集总参数法和状态空间模型,建立堆芯控制棒仿真模型,并利用Matlab/simulink软件搭建堆芯控制棒仿真系统,在不同功率水平下,压水堆堆芯控制棒上移或下插等棒位变化进行仿真。仿真结果表明,堆芯功率水平越低,移动控制棒对堆芯功率的影响越大,堆芯功率稳定所需的时间越长。该实验涵盖了多个知识点,有利于培养学生的思维能力,提高学生运用知识的能力。
In order to enable students to understand the role of the control rod in the reactor core better,a simulation experiment of the PWR(pressurized water reactor)control rod is designed.Based on the lumped parameter method and state-space model,the simulation model of the core control rod is established,and the simulation system of the core control rod is built by using Matlab/simulink software.At different power levels,the position change of the PWR core control rod such as upward movement or downward insertion are simulated.The simulation results show that the lower the core power level,the greater the influence of moving control rod on core power and the longer the time required for core power stability.This experiment covers many knowledge points,which is helpful to cultivate students' ability of thinking and improve their ability to use knowledge.
In order to enable students to understand the role of the control rod in the reactor core better,a simulation experiment of the PWR(pressurized water reactor)control rod is designed.Based on the lumped parameter method and state-space model,the simulation model of the core control rod is established,and the simulation system of the core control rod is built by using Matlab/simulink software.At different power levels,the position change of the PWR core control rod such as upward movement or downward insertion are simulated.The simulation results show that the lower the core power level,the greater the influence of moving control rod on core power and the longer the time required for core power stability.This experiment covers many knowledge points,which is helpful to cultivate students' ability of thinking and improve their ability to use knowledge.
引文
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[2]曾文杰,谢金森,程品晶,等.高校核专业虚拟仿真实验教学建设探索:问题与对策[J].教育教学论坛,2017(25):273-274.
[3]李罡,赵福宇,刘洋.压水堆堆芯非线性系统的全局稳定性分析[J].原子能科学技术,2013,47(2):271-276.
[4]谢仲生,吴宏春,张少泓.核反应堆物理分析[M].西安:西安交通大学出版社,2004.
[5]于平安,朱瑞安,喻真烷,等.核反应堆热工分析[M].上海:上海交通大学出版社,2002.
[6]朱继洲,单建强,张斌.压水堆核电厂的运行[M].北京:原子能出版社,2008.
[7]袁建东.一体化压水堆功率控制系统建模与控制方法研究[D].哈尔滨:哈尔滨工程大学,2004.
[8]张建民,姜晶.核反应堆控制[M].北京:原子能出版社,2009.
[9]王乔,黎浩峰,陈文振,等.基于Simulink输入阶跃反应性时有温度和毒物反馈的反应堆动态响应仿真[J].原子能科学技术,2009,43(9):823-827.
[10]王正林,王胜开,陈国顺.MATLAB/Simulink与控制系统仿真[M].北京:电子工业出版社,2005.
[11]薛定宇,陈阳泉.基于MATLAB/Simulink的系统仿真技术与应用[M].北京:清华大学出版社,2002.
[12]KHAJAVI M N,MENHAJ M B,SURATGAR A A.A neural network controller for load following operation of nuclear reactors[J].Annals of Nuclear Energy,2002,29:751-760.
[13]SIMA S K,MEHRDAD B,CARO L.Emotional learning based intelligent controller for a PWR nuclear reactor core during load following operation[J].Annals of Nuclear Energy,2008,35:2051-2058.