Numerical modeling of alkali metal heat pipes

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
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引用次数: 0

Abstract

Heat pipe cooled reactors passively transfer heat from the core to the energy conversion system through alkali metal heat pipes. Further studies of the heat transfer characteristics of alkali metal heat pipes are needed to develop heat pipe cooled reactors. This work used a two-dimensional heat and mass transfer model of an alkali metal heat pipe. The flow field was validated against CFD predictions which showed that the model has less than 10 % errors in the velocity distribution and less than 5 % errors in the pressure distribution. A comparison of the predictions with experimental data in the literature indicated that the predicted wall temperature error was within 30 °C. This model was then used to analyze four factors that affect heat transfer in sodium heat pipes. The simulations show that higher heat fluxes shorten the startup time by approximately 70 % but significantly increase the operating temperature. The heat flux distribution significantly affects the evaporator temperature distribution. The heat transfer boundary condition on the condenser’s outer surface mainly affects the operating temperature and startup time. Increasing the heat pipe length-to-diameter ratio with a fixed heat flux increases the operating temperature with the increase proportional to the heat flux. This model provides accurate simulations of sodium heat pipes for various heat transfer boundary conditions. The simulations provide a reference for the selection of working conditions for heat pipe operation instability experiments.

碱金属热管的数值建模
热管冷却反应堆通过碱金属热管被动地将热量从堆芯传递到能量转换系统。需要进一步研究碱金属热管的传热特性,以开发热管冷却反应堆。这项研究使用了碱金属热管的二维传热和传质模型。根据 CFD 预测对流场进行了验证,结果表明该模型在速度分布方面的误差小于 10%,在压力分布方面的误差小于 5%。将预测结果与文献中的实验数据进行比较后发现,预测的管壁温度误差在 30 °C 以内。然后,利用该模型分析了影响钠热管传热的四个因素。模拟结果表明,较高的热通量可将启动时间缩短约 70%,但会显著提高工作温度。热通量分布对蒸发器温度分布有很大影响。冷凝器外表面的传热边界条件主要影响运行温度和启动时间。在热通量固定的情况下,增加热管的长径比会提高运行温度,提高的幅度与热通量成正比。该模型对各种传热边界条件下的钠热管进行了精确模拟。模拟结果为选择热管运行不稳定实验的工作条件提供了参考。
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来源期刊
Annals of Nuclear Energy
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.
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