针对 10 MW高温气冷堆 (HTR- 10 )核动力装置堆型新 ,对象动态特性复杂等特点 ,研究了自动控制系统的整体结构 ,结合工程要求设计了相应的协调控制方案。分析并提出控制器参数的工程整定方法 ,通过仿真着重在典型给定值变化或扰动情况下 ,对各方案控制性能进行了深入分析和考查。最终给出“核功率控制热氦温度以及氦流量控制蒸汽温度”的方案作为工程重点 ,可为实际运行操作提供直接参考 ,并为 HTR- 10整体控制策略的深入研究奠定了基础 In view of the characteristics of new and retrograde nuclear reactors of 10 MW high temperature gas cooled reactor (HTR-10) nuclear power plant, the overall structure of the automatic control system is studied, and the corresponding coordinated control scheme is designed according to the engineering requirements. Analyzes and puts forward the engineering setting method of the controller parameters. Through the simulation, it mainly analyzes and examines the control performance of each scheme under the condition of typical setpoint changes or disturbances. The final proposal of “nuclear power control of helium temperature and helium flow rate control steam temperature” as a project priority provides a direct reference for practical operation and lays the foundation for an in-depth study of the HTR-10 overall control strategy