钠热管中间歇泉沸腾的成核特征

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

Annals of Nuclear Energy Pub Date : 2024-10-29 DOI:10.1016/j.anucene.2024.111010

Zaiyong Ma , Qi Wu , Yugao Ma , Simiao Tang , Luteng Zhang , Changwen Liu , Liangming Pan

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引用次数: 0

摘要

关于液态金属热管中的间歇泉沸腾现象已经进行了很多研究，但大多数都是现象学研究。考虑到成核应是间歇泉沸腾的诱因，因此应通过研究相关的成核特征来预测间歇泉沸腾的发生。本文获得并分析了成核过热度的实验值。结果表明，影响钠热管成核过热度的主要参数是加热功率和压力，而灯芯目数、倾角、充液比等参数的影响不大。通过将实验数据与热通量和壁腔蒸汽压进行拟合，提出了一种能够很好预测数据的相关关系。进一步的研究表明，壁腔中可能存在润湿性能较差的材料，其表面热物理性能受温度影响较大，导致成核接触角随壁温升高而减小。

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The nucleation characteristics of geyser boiling in sodium heat pipes

Many studies have been carried out on the geyser boiling phenomenon in liquid metal heat pipes, but most of them are phenomenological. Considering that nucleation should be the trigger of geyser boiling, occurrence of geyser boiling should be predicted by studying related nucleation characteristics. In this paper, the experimental value of nucleation superheat were gained and analyzed. The results showed that the main parameters affecting the nucleation superheat of sodium heat pipe were heating power and pressure, and the influences of wick mesh number, inclination angle, liquid filling ratio etc. were not important. By fitting the experimental data with heat flux and wall cavity vapor pressure, a correlation which could predict the data well was proposed. Further investigation showed that there may be materials with bad wetting properties in the wall cavities, whose surface thermo-physical properties could be greatly affected by temperature, resulting in the decrease of nucleation contact angle with increase in wall temperature.

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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.