A critical analysis of correlations for saturated nucleate pool-boiling heat transfer over vertical tubes and tube bundles: Development of improved models

IF 3.2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy Pub Date : 2025-08-18 DOI:10.1016/j.pnucene.2025.105893

Bibhu Bhusan Sha , Rajiva Lochan Mohanty , Mihir Kumar Das

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Abstract

Pool boiling over vertical tubes is vastly experienced in the nuclear industry, where nucleate boiling plays a crucial role in transferring heat. In this context, many experiments have been done in the recent past and developed various correlations for boiling heat transfer. The correlations are influenced by system parameters and the geometrical configuration of the surfaces. Therefore, a wide range of experimental data for saturated pool boiling over vertical tubes and their bundles are taken into consideration to examine the prediction accuracy of various correlations. The prediction errors of various correlations are reported both in tabular and graphical forms. Keeping the most critical parameters in mind, this article proposes two new semi-empirical correlations for predicting the heat transfer coefficient over vertical tubes and their bundles. These developed correlations are able to predict saturated boiling heat transfer coefficients over the tube bundle and single tube data within ±15 % and ±20 %, respectively.

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垂直管和管束上饱和核池沸腾传热相关性的关键分析：改进模型的发展

在核工业中，垂直管道上的池沸腾有着丰富的经验，其中核沸腾在传热中起着至关重要的作用。在这种情况下，在最近的过去已经做了许多实验，并开发了沸腾传热的各种相关性。这种相关性受系统参数和表面几何形状的影响。因此，考虑了垂直管及其管束上饱和池沸腾的大范围实验数据，以检验各种相关系数的预测精度。以表格和图表两种形式报告了各种相关性的预测误差。考虑到最关键的参数，本文提出了两个新的半经验关系式来预测垂直管及其管束的传热系数。这些建立的相关性能够分别在±15%和±20%的范围内预测管束和单管数据上的饱和沸腾传热系数。

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

Progress in Nuclear Energy 工程技术-核科学技术

CiteScore

5.30

自引率

14.80%

发文量

331

审稿时长

3.5 months

期刊介绍： Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.