中间换热器螺旋波纹管内换热及流动特性实验研究

IF 3.2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Haifeng Liu , Qingxiang Hu , Wei Peng , Ekaterina Sokolova , Khashayar Sadeghi , Qi Sun , Jie Wang
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引用次数: 0

摘要

高温气冷堆(vhtr)中的中间热交换器(IHX)是过程热应用中必不可少的,是中间回路中热能传递的主要部件。本研究以空气为工作流体,在雷诺数为7000 ~ 22000的湍流条件下,实验研究了不同结构参数的光滑圆管和8根螺旋波纹管(hct)的传热和流动特性。结果表明,hct显著增强了管内对流换热,但也导致了流动阻力的增加。随着无量纲波纹高度e/d的增大,hct的Nu和f增大,随着无量纲波纹间距p/d的增大而减小。在实验数据的基础上,以幂函数和无量纲粗糙度函数的形式建立了经验相关性,两者都与测量结果吻合良好。Nu和f的功率相关性的最大误差分别为±11.24%和±15.89%,而阻力和传热的无量纲粗糙度函数相关性的最大误差分别为±15.67%和±15.17%。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Experimental study on heat transfer and flow characteristics inside helically corrugated tubes in intermediate heat exchangers
The intermediate heat exchanger (IHX) in very-high-temperature gas-cooled reactors (VHTRs) is essential for process heat applications, serving as the primary component for thermal energy transfer in the intermediate loop. This study experimentally investigated the heat transfer and flow characteristics of a smooth circular tube and eight helically corrugated tubes (HCTs) with varying structural parameters, using air as working fluid, under turbulent conditions spanning Reynolds number from 7000 to 22000. The results indicate that HCTs significantly enhance convection heat transfer within the tube but also lead to increased flow resistance. The Nu and f of the HCTs increase with higher dimensionless corrugation height e/d, and decrease with larger dimensionless corrugation pitch p/d. Based on the experimental data, empirical correlations were developed in the form of power and dimensionless roughness functions, both demonstrating good agreement with the measurements. The maximum errors of the power correlations for Nu and f were ±11.24 % and ±15.89 %, respectively, while the maximum errors for the dimensionless roughness function correlations for resistance and heat transfer were ±15.67 % and ±15.17 %.
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来源期刊
Progress in Nuclear Energy
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.
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