200 MW核供热堆非线性模型的动态分析

为了对已建立的２００ＭＷ核供热堆的非线性模型寻求简化的依据，对该模型进行了动态分析。讨论了在反应性扰动和二回路流量扰动下，堆功率和上气室水温的动态过程。通过比较模型的动态特性曲线，得出结论：一组缓发中子模型满足控制模型所要求的精度；在整个自动功率运行范围内，不能忽略自然循环流量变化对堆芯内燃料与冷却剂之间的传热系数的影响，但可忽略它对主换热器一次侧换热系数的影响、主换热器管内水的热惯性以及堆内各出入口处的容积作用，并可把烟囱和下降管分别用一阶惯性环节近似，对二回路流量扰动下的动态特性影响较明显，而对反应性扰动下的动态特性影响不大。

Dynamic analysis of nonlinear model of 200 MW nuclear heating reactor

In order to carry out model simplification and controller synthesis, the dynamic responses of a nonlinear model of 200MW nuclear heating reactor (NHR) were analyzed under different conditions. The responses of the reactor power and temperature of the coolant in the top tank were studied under those conditions when reactivity and secondary flow rate changed respectively. Some conclusions can be obtained from the simulation results: one group delayed neutrons model is accurate enough for control system analysis; the variation of the heat transfer coefficient between the coolant and the fuel caused by the natural circulation can not be neglected during the whole automatic performance range, while the variation of the heat transfer coefficient of the primary heat exchanger (PHE) shell side caused by the natural circulation can be ignored; the thermal inertia of the coolant in the tubes of PHE can be ignored. Neglecting inlets and outlets of the core and PHE, considering the chimney and the descending flow pipe as first order lag nodes will affect the dynamic process a lot when step secondary flow rate is introduced, but its influence on the step responses of reactivity is small.