超高温气冷式反应堆中间热交换器中螺旋波纹管的湍流和传热的大涡流模拟

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy Pub Date : 2024-10-14 DOI:10.1016/j.pnucene.2024.105488

Qingxiang Hu, Haifeng Liu, Qi Sun, Xiaozhong Wang, Jie Wang, Wei Peng

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引用次数: 0

摘要

中间热交换器（IHX）是用于核能热应用（特别是制氢）的超高温气冷堆（VHTR）的重要组成部分。提高 IHX 的热传输能力对于为热过程提供足够的热量至关重要。本研究利用大涡流模拟研究了由光滑圆管和螺旋波纹管组成的 IHX 模型，其中螺旋波纹管有五种不同的几何参数。结果显示了湍流和传热如何取决于几何参数。基于边界层理论、场协同和极端耗散等理论，定量分析了螺旋波纹管中的边界层分离、二次流、湍流传输、场协同和耗散特性。研究还探讨了螺旋波纹管内的强化传热机理，结果表明螺旋波纹管内的强化传热是由于螺旋结构阻碍了流体边界层的形成，加强了二次流和湍流输运的强度，改善了流体速度场和温度梯度之间的协同作用，减少了流体传热过程中的热势能损失。

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Large-eddy simulation of turbulent flow and heat transfer of helically corrugated tubes in the intermediate heat exchanger of a very-high-temperature gas-cooled reactor

The intermediate heat exchanger (IHX) is a vital component of very-high-temperature gas-cooled reactors (VHTRs) utilized for thermal applications of nuclear energy, specifically for hydrogen production. Enhancing the heat transmission capacity of IHXs is essential to provide sufficient heat for thermal processes. This study uses large eddy simulations to investigate IHX models consisting of both a smooth circular tube and helically corrugated tubes with five different geometric parametrizations. The results show how turbulent flow and heat transfer depend on the geometric parameters. Based on theories such as boundary layer theory, field synergy, and extreme dissipation, the characteristics of boundary layer separation, secondary flow, turbulent transport, field synergy, and dissipation characteristics in helically corrugated tubes are quantitatively analyzed. The study also investigates enhanced heat transfer mechanisms within the helically corrugated tubes, and the results attribute the enhanced heat transfer in helically corrugated tubes to the helical structure, which hinders the development of a fluid boundary layer, strengthens the intensity of secondary flow and turbulent transport, improves the synergy between the fluid velocity field and the temperature gradient, and reduces the thermal potential energy loss during the fluid heat transfer.

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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.