首页|基于APROS的核电系统建模与控制方法研究

基于APROS的核电系统建模与控制方法研究

Research on Nuclear Power System Modeling and Control Methods Based on APROS

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随着核电系统建模日益朝着准确化、精细化方向发展,对三维堆芯与热工水力模型耦合的研究也逐渐增多,这为控制系统的设计提供了更好的模型基础.本研究采用APROS软件对VVER-1000反应堆进行了三维堆芯与热工水力耦合建模,并设计了基于模型预测控制(MPC)的负荷跟踪控制系统和其他控制系统;随后利用稳态和瞬态仿真结果对该模型进行了验证,结果表明该模型仿真效果良好;利用三维堆芯可视化的优点,进一步验证了MPC负荷跟踪控制器的性能和安全性.这一研究不仅为核电系统研究提供了模型基础,也为先进功率控制系统的安全性分析提供了实践经验.
As nuclear power system modeling increasingly moves towards greater accuracy and refinement,research on the coupling of three-dimensional core and thermal-hydraulic models has also grown,which provides a better model foundation for the design of control systems.In this study,the APROS software was used to model the coupling of a three-dimensional core and thermal hydraulics for VVER-1000.A load-following control system based on model predictive control(MPC)and other control systems were designed.The model was then verified using steady-state and transient simulation results,which showed that the model simulated effectively.Taking advantage of the three-dimensional core visualization,the performance and safety of the MPC load-following controller were further validated.This research not only provides a model foundation for studies on nuclear power systems but also offers practical experience for the safety analysis of advanced power control systems.

Nuclear power system modelingThree-dimensional coreMPCLoad-following control systemAPROS

谢澳达、杨婷

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上海电力大学自动化工程学院,上海,200090

上海市电站自动化技术重点实验室,上海,200090

核电系统建模 三维堆芯 模型预测控制(MPC) 负荷跟踪控制系统 APROS

国家自然科学基金项目

51906133

2024

核动力工程
中国核动力研究设计院

核动力工程

CSTPCD北大核心
影响因子:0.3
ISSN:0258-0926
年,卷(期):2024.45(5)