Temperature fluctuation mitigation of heat pipe cooled reactor with closed Brayton cycle during load-following dynamic power regulation

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-10-22 DOI:10.1016/j.anucene.2024.110986

Jingkang Li , Zunyan Hu , Zeguang Li , Liangfei Xu , Jianqiu Li

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Abstract

Heat pipe cooled reactors (HPRs) offer the potential to achieve load-following control without the need for control rods or drums, thereby simplifying the control system. However, during load-following operation, HPRs experience fluctuations in temperature, which can impact safety. Limited research has focused on mitigating temperature fluctuations of HPRs during dynamic power regulation leveraging their inherent load-following capabilities. This study examines the characteristics of an HPR with closed Brayton Cycle (CBC), and develops a load-following control algorithm. A simplified CBC model is proposed to facilitate control strategy analysis. Model predictive control (MPC) is employed to suppress temperature fluctuations, revealing that the dynamic response of output power under MPC resembles that of a first-order inertial system. Consequently, a power control algorithm based on first-order inertial feedforward control is introduced. Simulation results demonstrate that the proposed algorithm, with a time constant ranging between 500 and 1000 s, significantly mitigates temperature and power fluctuations in HPRs during load-following dynamic power regulation.

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采用封闭式布雷顿循环的热管冷却反应堆在负载跟随动态功率调节期间的温度波动缓解问题

热管冷却反应堆（HPR）提供了无需控制棒或转鼓即可实现负荷跟踪控制的可能性，从而简化了控制系统。然而，在负载跟随运行期间，HPRs 会出现温度波动，这可能会影响安全。利用 HPR 固有的负载跟随能力，在动态功率调节期间缓解 HPR 温度波动的研究十分有限。本研究探讨了具有封闭式布雷顿循环（CBC）的 HPR 的特性，并开发了一种负载跟随控制算法。为便于进行控制策略分析，提出了一个简化的 CBC 模型。研究采用模型预测控制（MPC）来抑制温度波动，结果表明，MPC 下输出功率的动态响应类似于一阶惯性系统的动态响应。因此，引入了一种基于一阶惯性前馈控制的功率控制算法。仿真结果表明，所提算法的时间常数介于 500 秒和 1000 秒之间，在负载跟随动态功率调节过程中，能显著缓解 HPR 的温度和功率波动。

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来源期刊

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

期刊介绍： Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.