热管堆动态模型构建与控制方法研究

Research on Dynamic Modeling and Control Method of Heat Pipe Reactor

为了开展热管堆的核功率控制方法研究,本文建立了MegaPower热管堆的轻量化动态模型,并基于此对设计的控制器进行了仿真验证。基于集总参数方法,研究了堆芯到热管再到换热器的传热模型,并建立了Simulink仿真模型。针对热管堆的控制方法,首先确定了以负荷跟踪和换热器出口温度不变为控制目标,然后设计了并联比例-积分-微分(PID)和串级PID两种控制器,并对比分析了两者的控制效果。结果表明:模型方面,模型的稳态误差不超过0.05%,其在无控制情况下的参数响应趋势与理论分析一致,且仿真速度较快;控制方面,2种控制器均能够达成控制目标,核功率和换热器出口温度的调节时间小于150 s,且波动幅值较小。因此,本文建立的热管堆的动态模型可以用于热管堆控制方法的仿真验证,基于PID设计的两种控制器具有较好的控制效果,且串级PID控制器的控制性能更好。

In order to study the nuclear power control method of heat pipe reactor(HPR),the lightweight dynamic model of MegaPower HPR is constructed,and then the designed controller is verified by simulation.Based on lumped parameter method,a heat transfer model from core to heat pipe and then to heat exchanger is studied,and Simulink model is established.Aiming at the control method design of HPR,the control objectives of load tracking and keeping the heat exchanger outlet temperature constant are determined.Then,two controllers,the parallel proportional-integral-derivative(PID)and the cascade PID,are designed,and their control effects are compared and analyzed.The results show that the steady-state error of the model is less than 0.05%,and the parameter response trend of the model without control is consistent with the theoretical analysis,and the simulation speed is faster.In terms of control,the two controllers can achieve the control objectives,and the adjustment time of nuclear power and heat exchanger outlet temperature is less than 150 s with small fluctuation amplitude.Therefore,the dynamic model of HPR established in this paper can be used to verify the control method,and the two controllers based on PID design have great control effect,and the cascade PID controller has better control performance.