摘要：
Space nuclear power reactors have the advantages of small size, long service lives and high-power densities. As these characteristics, space nuclear power reactors can meet the high-power demands of spacecraft. To safely and reliably perform tasks in space with a space nuclear reactor, the control technology of the space nuclear reactor is significant. To study the core power control of a space nuclear reactor, a nonlinear model for the TOPAZ-II core is established by the lumped parameter method and principle of point reactor modeling. Then, directly based on the core nonlinear model, a fuzzy-PID controller is used to control the core power. Finally, the core power control system is built, and dynamic simulations are carried out with multiple transient conditions. The results show that the fuzzy-PID controller can realize core power control well, and its control effect is better than that of PID controller.
期刊：
Nuclear Engineering and Design,2020年360:110513 ISSN：0029-5493
通讯作者：
Yu, Tao
作者机构：
[Zhu, Weicong; Hui, Tianyu; Zeng, Wenjie; Xie, Jinsen; Chen, Lezhi; Yu, Tao] Univ South China, Dept Nucl Sci & Technol, Hengyang City 421001, Peoples R China.
通讯机构：
[Yu, Tao] U;Univ South China, Dept Nucl Sci & Technol, Hengyang City 421001, Peoples R China.
关键词：
Core power control;IMC-PID controller;MSBR;Particle Swarm Optimization algorithm
摘要：
Internal Model Control (IMC) is a control strategy based on process mathematical model for controller design. The design idea of IMC is to parallelize the object model with the actual object, approximate the dynamic inversion of the model by the controller, and take the inverse of the minimum phase part of the model for a single variable system, and add it to the system. As the advantages of simple structure, intuitive design, no need for accurate object model, less on-line adjustment parameters in IMC design process, to explore the application of IMC in the field of nuclear reactor control, taking the core power control of Molten Salt Breeder Reactor (MSBR) as an example, a linear model of MSBR core system is established. The IMC technology was adopted and the IMC-PID controller with Particle Swarm Optimization (PSO) algorithm was designed to control the core power. The core power control of liquid molten salt reactor under step reactivity disturbance and load tracking is studied. The results show that the IMC-PID controller can control the core power well.
期刊：
Progress in Nuclear Energy,2020年121:103214 ISSN：0149-1970
通讯作者：
Yu, Tao
作者机构：
[Jiang, Qingfeng; Zeng, Wenjie; Xie, Jinsen; Yu, Tao] Univ South China, Dept Nucl Sci & Technol, Hengyang City 421001, Peoples R China.
通讯机构：
[Yu, Tao] U;Univ South China, Dept Nucl Sci & Technol, Hengyang City 421001, Peoples R China.
关键词：
Core outlet fuel temperature;Liquid molten salt reactor;Fuzzy PID controller;Load following operation
摘要：
As the molten salt fuel flows in the primary loop system of Liquid Molten Salt Reactor (LMSR), the core outlet fuel temperature can effectively characterize the core operation state. In this paper, a control strategy of the core outlet fuel temperature is designed based on the load power required. First, a nonlinear model of LMSR core is built by the lumped parameter method. Then, according to the relationship between the core outlet fuel temperature and the load power required, the control strategy of LMSR core outlet fuel temperature is established. The PID controller and the fuzzy PID controller are respectively used to design the core outlet fuel temperature control system. The simulation system is directly established by using the core nonlinear model. The simulation of LMSR core load following is carried out. The results show that the core outlet fuel temperature can be controlled well by using either PID controller or fuzzy PID controller.
作者机构：
[陈珍平; 于涛; 张震宇; 马辉强; 谢金森] School of Nuclear Science and Technology, University of South China, Hengyang;421001, China;[郭倩] School of Resource Environment and Safety Engineering, University of South China, Hengyang;Hunan Engineering and Technology Research Center for Virtual Nuclear Reactor, Hengyang;[陈珍平; 郭倩; 于涛; 张震宇; 马辉强; 谢金森] 421001, China<&wdkj&>Hunan Engineering and Technology Research Center for Virtual Nuclear Reactor, Hengyang
通讯机构：
School of Resource Environment and Safety Engineering, University of South China, Hengyang, China
通讯机构：
[Yu, T.] S;School of Nuclear Science and Technology, China
关键词：
环形燃料芯块;温度场;稳态导热
摘要：
环形燃料芯块(Annular Fuel Pellets)具有较低的运行温度,能够实现更高的功率密度,已成为先进核反应堆燃料元件的发展方向之一。由于双面冷却环形元件存在流量分配和热量分配问题,实心圆柱燃料芯块的温度场求解方法无法求解环形燃料芯块温度场。建立了环形燃料芯块一维稳态温度场计算模型,开发了环形燃料芯块温度场计算程序PTFA(Program of Temperature Field of Annular Fuel Pellets),并计算了不同功率密度、不同芯块厚度下的绝热面位置、最高温度以及芯块的温度场分布。最后用有限元程序COMSOL5.4验证了不同芯块厚度下不同功率密度的环形燃料芯块的绝热面位置、最高温度以及芯块温度场分布。结果表明:环形燃料芯块一维稳态温度场计算模型计算的结果与有限元方法计算的结果吻合很好,相对偏差小于0.2%,该模型可以用于环形燃料元件的热工水力计算分析。
作者机构：
[赵鹏程; 刘紫静; 于涛; 刘佩琪; 谢金森; 陈珍平] School of Nuclear Science and Technology, University of South China, Hengyang;421001, China;Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu;610213, China;Cooperative Innovation Center for Nuclear Fuel Cycle Technology and Equipment, University of South China, Hengyang
作者机构：
[曹奇锋; 张震宇; 陈珍平; 马辉强; 于涛] School of Nuclear Science and Technology, University of South China, Hengyang;Hunan;421001, China;Hunan Engineering and Technology Research Center for Virtual Nuclear Reactor, Hengyang;[曹奇锋; 张震宇; 陈珍平; 马辉强; 于涛] Hunan
作者机构：
[杜尚勉; Zeng, Wenjie; 于涛; 陈乐至; 谢金森] School of Nuclear Science and Technology, University of South China, Hengyang;Hunan;421001, China;[杜尚勉; Zeng, Wenjie; 于涛; 陈乐至; 谢金森] Hunan;[杜尚勉; Zeng, Wenjie; 于涛; 陈乐至; 谢金森] 421001, China
