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.
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.