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本文用自动控制理论中的根轨迹法,分析了压水型核反应堆双温度反应性反馈回路的自稳定性能。从而得出以核燃料温度反应性系数α_f和主载热剂温度反应性系数α_w为参数的稳定域。其中不考虑堆输出热功率变化影响的稳定域,文献[1]中用频率法亦得到完全相同的结果。压水型核反应堆双温度反应性反馈回路的稳定域,对核反应堆控制设计和运行具有一定的使用意义。尤其是考虑了核反应堆热功率输出变化影响之稳定域,同核反应堆的运行状态有着密切关系。因此,对核反应堆的运行更具有重要的使用意义。
In this paper, the autoregressive theory of root locus method is used to analyze the self-stability of the dual temperature feedback loop of pressurized water nuclear reactor. So we can get the stable domain which takes the nuclear reactor temperature reactivity coefficient α_f and the main heat carrier temperature reactivity coefficient α_w as parameters. Which does not consider the stability of the output power thermal output changes in the stability of the field, the literature [1] also obtained exactly the same frequency results. The stability of the dual-temperature reactive feedback loop of pressurized water reactors has some significance for the design and operation of nuclear reactor control. In particular, the stability of the field affected by the variation of thermal power output of nuclear reactors is considered, which is closely related to the operating status of nuclear reactors. Therefore, the operation of the nuclear reactor is more important and meaningful.