基于主动干扰抑制控制的一次流发电机控制方法

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2024-10-14 DOI:10.1016/j.nucengdes.2024.113635

Muping Li, Aodi Sun, Peiwei Sun, Xinyu Wei

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引用次数: 0

摘要

采用池式冷却的小型铅铋快堆（SLBFR）具有固有的安全特性，适合移动核电站和远程供电等多种应用。为确保 SLBFR 在汽轮机主导模式下的安全运行，必须为一次通过式蒸汽发生器（OTSG）提供新的控制方法。此外，增强负荷跟随能力对满足运行要求也至关重要。在 MATLAB/Simulink 软件中建立了 SLBFR 模型，以研究 OTSG 在汽轮机主导模式下的运行特性。蒸汽压力控制系统采用主动干扰抑制控制。通过能量平衡修正的负载前馈控制改善了核心功率的负载跟随特性。仿真结果表明，所采用的控制方法增强了 OTSG 的负载跟随能力。本文为设计 SLBFR 的 OTSG 控制系统提供了有价值的参考，有助于其在各种环境下安全高效地运行。

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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Control method of once-through stream generator based on active disturbance rejection control

Small lead–bismuth fast reactor(SLBFR) with pool cooling offers inherent safety features, making it suitable for diverse applications such as mobile nuclear power plants and remote power supplies However, conventional control methods often struggle to meet the demands of frequent load adjustments. To ensure the safe operation of SLBFR in the turbine-leading mode, a new control method for the once-through steam generator (OTSG) is imperative. Moreover, enhancing load-following capabilities is essential to meet operational requirements. The model of SLBFR is established in MATLAB/Simulink software to study the characteristics of OTSG operating in the turbine-leading mode. The control system of steam pressure is built by active disturbance rejection control. The load-following characteristic of core power is improved by load feedforward control modified by energy balance. Simulation results demonstrate that the adopted control method enhances the load-following capability of the OTSG. This paper serves as a valuable reference for designing the OTSG control system of SLBFR, contributing to its safe and efficient operation in various settings.

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来源期刊

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.