Conventional Controller Design for the Reactor Power Control System of the Advanced Small Pressurized Water Reactor
Conventional Controller Design for the Reactor Power Control System of the Advanced Small Pressurized Water Reactor
复制标题
DOI：
10.1080/00295450.2017.1292822
复制
发表时间：
2017-04
影响因子：
1.5
通讯作者：
Jiashuang Wan;Pengfei Wang;Shifa Wu;F. Zhao
中科院分区：
文献类型：
--
作者：
Jiashuang Wan;Pengfei Wang;Shifa Wu;F. Zhao
本文的目的是为采用恒定平均冷却剂温度和二次侧蒸汽压力方案的先进小型压水堆设计一套反应堆功率控制系统。基于单群延迟中子堆芯非线性模型和简化的非线性直流蒸汽发生器模型，建立了两输入两输出的线性核蒸汽供应系统(NSSS)模型。然后利用解析法和二阶逼近法在Bode图上提出并设计了三种类型的控制系统。对三种控制系统的控制性能和鲁棒性进行了比较，结果表明，同时具有功率反馈和温度反馈的双反馈控制(DFC)对因控制棒差值变化引起的参数不确定性的反应堆功率和平均冷却剂温度具有最好的控制性能。基于高阶非线性NSSS模型的仿真结果也表明了DFC系统的良好性能。
Abstract The objective of this paper is to design a reactor power control system for the advanced small pressurized water reactor that adopts a constant average coolant temperature and a secondary-side steam pressure program. Based on the nonlinear core model with the one-group delayed neutron and simplified nonlinear once-through steam generator model, a two-input and two-output linear nuclear steam supply system (NSSS) model is obtained. Three types of control systems are then proposed and designed on a Bode diagram using analytical methods and second-order approximation. The comparison of the control performance and robustness of the three control systems shows that the double feedback control (DFC) with both power feedback and temperature feedback provides the best performance for reactor power and average coolant temperature with parameter uncertainty due to control rod differential worth variation. The simulations based on the high-order nonlinear NSSS model also show good performance of the DFC system.