Boiling critical characteristics in narrow rectangular channel under local heat flux concentration conditions

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-11-26 DOI:10.1016/j.anucene.2024.111077

Kepiao Li , Kui Zhang , Tianyi Qi , Ronghua Chen , Wenxi Tian , Suizheng Qiu

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Abstract

For the establishment of predicting method of local concentrated critical heat flux (CHF) in narrow rectangular channels, and also technical support for the preparation of long-life and high-performance dispersive plate fuel, this work simulates Dry-out type CHF under local concentration of heat flux condition by using Eulerian multiphase model and Enhanced near-wall treatment. The distribution of near-wall temperature and void fraction under different heat flux was calculated by Computational Fluid Dynamics (CFD) method. Dry-out CHF was predicted based on highly and quickly wall temperature rise. The influence of system pressure, mass flow rate and inlet subcooling degree were discussed on Dry-out CHF. Compared with uniform heating, the predicted average heat flux on CHF is lower under local heat flux concentration, and location of CHF is related to the position of heat flux concentration area. This work’s research method in Ansys Fluent could be applied to forecast Dry-out CHF in narrow rectangular channel under local concentration of heat flux condition.

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局部热流集中条件下窄矩形水道的沸腾临界特性

为建立窄矩形通道局部集中临界热通量（CHF）的预测方法，同时为制备长寿命、高性能的分散板状燃料提供技术支持，本研究采用欧拉多相模型和增强近壁处理，模拟了局部集中热通量条件下的干馏型CHF。通过计算流体动力学（CFD）方法计算了不同热通量下的近壁温度和空隙率分布。根据高度和快速的壁面温升预测了干化 CHF。讨论了系统压力、质量流量和入口过冷度对干化 CHF 的影响。与均匀加热相比，在局部热通量集中的情况下，CHF 的预测平均热通量较低，且 CHF 的位置与热通量集中区域的位置有关。这项工作在 Ansys Fluent 中的研究方法可用于预测局部热通量集中条件下窄矩形通道中的干化 CHF。

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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.