Analysis of critical heat flux in vertically upward narrow rectangular channel under high pressure

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-09-04 DOI:10.1016/j.anucene.2025.111850

Chen Jiaqi , Tan Xuefeng , Li Xiangyu , Zhou Jinman , Guo Yun

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Abstract

The investigation of heat flux under which physical burnout of a heat transfer surface occurs is of prime importance for boiling systems with forced circulation. To avoid physical burnout under the various abnormal conditions,the nuclear reactor must be designed to operate within a safety margin. Therefore,it is of great significance to conduct research on the prediction of critical heat flux (CHF). For narrow rectangular channel, heat exchange characteristics are obviously different from those in conventional flow channels. In this research, Euler’s two-fluid model is used to predict the CHF value in a narrow rectangular channel with a vertical upward pressure, and the predicted results are compared to the experimental data obtained at the Betties nuclear power plant, the error between the predicted results and the experimental data is less than 20%, which shows that the model has high accuracy in predicting the CHF of the narrow rectangular channel under high pressure. Besides the above, sensitive analysis of two-phase sub-model, width to diameter ratio of flow channel and various heating length are conducted in this research,which indicates that there are considerable impact on the predicting CHF value.

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高压条件下垂直向上窄矩形通道内临界热流密度分析

研究传热表面发生物理燃尽时的热流密度对强制循环的沸腾系统至关重要。为了避免在各种异常条件下的物理燃尽，核反应堆必须设计成在安全范围内运行。因此，开展临界热流密度（CHF）预测研究具有重要意义。窄矩形流道的换热特性与常规流道的换热特性明显不同。本研究采用欧拉双流体模型对垂直向上压力的窄矩形通道CHF值进行了预测，并将预测结果与Betties核电站的实验数据进行了对比，预测结果与实验数据的误差小于20%，表明该模型对高压下窄矩形通道CHF的预测具有较高的精度。除此之外，本研究还对两相子模型、流道宽径比和不同加热长度进行了敏感性分析，表明它们对CHF值的预测有较大影响。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.