A control strategy for supercritical carbon dioxide direct cooled nuclear power system

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Yunzhi Chai , Jiashuang Wan , Kai Xiao , Zhengxi He , Zhi Chen , Shifa Wu
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引用次数: 0

Abstract

The supercritical carbon dioxide (S-CO2) direct cooled nuclear power system is an energy conversion system that utilizes S-CO2 as the medium to transform nuclear thermal energy into electrical or mechanical power through a direct cycle. It offers advantages such as system simplification, compact structure, high maneuverability, and superior thermal efficiency. However, the system poses significant control challenges due to its characteristics of strong multi-equipment coupling, wide parameter variations, and complex physical processes. To address the coordination of highly variable external load demands, it is important to investigate its control strategy. In this paper, a simulation model of the S-CO2 direct cooled nuclear power system is established on the MATLAB/Simulink. Through dynamic characteristic analysis under typical operational modes, including step transient conditions, linear transient conditions, and load rejection transient conditions, a hybrid throttling-bypass control strategy is proposed. Specifically, the throttling control subsystem is designed to manage step transient conditions and linear transient conditions requirements, while the bypass control subsystem is designed for load rejection transient conditions. Simulation results demonstrate that the proposed control strategy achieves good control performance for the S-CO2 direct cooled nuclear power system. This paper provides valuable reference for the design of control systems in S-CO2 direct cooled nuclear power system.
超临界二氧化碳直冷核电系统的控制策略
超临界二氧化碳(S-CO2)直冷核电系统是以S-CO2为介质,通过直接循环将核热能转化为电能或机械能的一种能量转换系统。它具有系统简化、结构紧凑、机动性强、热效率高等优点。然而,由于该系统具有多设备耦合强、参数变化大、物理过程复杂等特点,给控制带来了重大挑战。为了解决高度可变的外部负载需求的协调问题,研究其控制策略是很重要的。本文利用MATLAB/Simulink建立了S-CO2直冷核电系统的仿真模型。通过对阶跃暂态、线性暂态和甩负荷等典型工况下的动态特性分析,提出了一种节流-旁路混合控制策略。具体而言,节流控制子系统设计用于管理阶跃瞬态条件和线性瞬态条件的要求,而旁路控制子系统设计用于负载拒绝瞬态条件。仿真结果表明,所提出的控制策略对S-CO2直冷核电系统具有良好的控制性能。本文为S-CO2直冷核电系统控制系统的设计提供了有价值的参考。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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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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