基于主导极点的 HPR1000 平均冷却剂温度状态反馈控制

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Ziqi Fan, Xianshan Zhang, Kaiyang Zheng, Peiwei Sun, Xinyu Wei
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引用次数: 0

摘要

核电站的控制仍基于传统的 PID 控制系统,在大范围负荷变化过程中难以获得较高的控制质量。为了有效利用系统的可测量信息并考虑约束条件,针对 HPR1000 的平均冷却剂温度控制,提出了基于显极法的状态反馈控制。控制系统分为两部分:一部分是反馈支路,利用包括堆芯入口温度、堆芯出口温度和反应堆功率在内的可测量系统状态量实现状态反馈,同时引入积分环节以减小稳态误差;另一部分是前馈支路,利用额定负荷变化进行前馈补偿,以提高负荷跟踪的控制性能。同时,采用粒子群优化(PSO)方法对控制器参数进行优化,得到了符合要求的主导极点。在 HPR1000 模型上验证了不同工况下的控制性能。试验结果表明,状态反馈控制能有效提高设定点跟踪能力和抗干扰能力。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
State feedback control of HPR1000 average coolant temperature based on dominant pole

Control of nuclear power plant is still based on the traditional PID control system, which is difficult to obtain high control quality in the process of a wide range of load changes. To effectively use the measurable information of the system and consider the constraints, state feedback control based on the dominant pole method is proposed for the average coolant temperature control of HPR1000. The control system is divided into two parts: one part is a feedback branch, which realizes the state feedback by using the measurable system state quantity including the core inlet temperature, the core outlet temperature and the reactor power, and at the same time introduces the integral link to reduce the steady-state error; the other part is a feedforward branch, which uses the nominal load change to make feedforward compensation to improve the control performance of load tracking. At the same time, Particle Swarm Optimization (PSO) method is used to optimize the controller parameters, and the dominant pole meeting the requirements is obtained. The control performance under different working conditions is verified on the HPR1000 model. The test results show that the state feedback control can effectively improve the setpoint tracking ability and anti-disturbance ability.

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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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