典型车载兆瓦级热管冷却堆动力系统特性分析

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

Annals of Nuclear Energy Pub Date : 2025-04-23 DOI:10.1016/j.anucene.2025.111467

Henglong Lin , Zeguang Li , Kan Wang , Weilin Zhuge , Ganglin Yu , Hongsheng Jiang , Jingkang Li , Jun Yang , Zilin Su , Huifu Wang

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引用次数: 0

摘要

热管冷却堆（HPR）具有体积小、安全性高的特点，可用于车载机动等特殊应用场景。本文选取设计发电量为1MWe的基于HPR的移动核电系统MNPS-1000进行研究分析。根据设计，建立了整个系统模型，包括反应器模型、高温热管模型、热管换热器模型和能量转换系统模型等。利用MATLAB/SIMULINK搭建了适用于该核电系统的分析平台。在此平台上，对系统的稳态和暂态性能进行了表征。稳态分析中，模型关键节点的模拟值与参数匹配的计算值基本吻合，最大相对误差不超过6%。验证了基于所建平台进行特性分析的有效性。在暂态分析中，分别对典型的反应堆系统事故和能量转换系统事故进行了模拟分析。这些事故中燃料组件的最高温度不超过1550k，低于所选材料温度安全限值。讨论了系统的固有安全特性。

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Characteristics analysis of the typical vehicle-mounted megawatt-scale heat pipe cooled reactor power system

Heat pipe cooled reactor (HPR) has the characteristics of small size and high safety, and can be used in special application scenarios such as vehicle-mounted mobility. In this paper, the Mobile Nuclear Power System based on HPR named MNPS-1000, which is designed to generate 1MWe, is selected for research and analysis. According to the design, a whole system model is established, which includes the reactor model, high-temperature heat pipe model, heat pipe heat exchanger model and energy conversion system model, etc. Using MATLAB/SIMULINK, the analysis platform suitable for this nuclear power system is built. Based on this platform, the steady state and transient performance of the system are characterized. In the steady state analysis, the simulated values of key nodes of the model are in general agreement with the calculated values of parameter matching, and the maximum relative error does not exceed 6 %. The effectiveness of characteristic analysis based on the built platform is verified. In the transient analysis, typical reactor system accidents and energy conversion system accident are simulated and analyzed respectively. The maximum temperature of the fuel assemblies in these accidents does not exceed 1550 K, which is lower than the selected material temperature safety limit. The inherent safety feature of the system is discussed.

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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.