Numerical study on the thermohydraulics of near-critical water in rod bundle with spacer grids

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

Progress in Nuclear Energy Pub Date : 2024-09-07 DOI:10.1016/j.pnucene.2024.105429

Shuo Chen , Rui Zhang , Maolong Liu , Hui Guo , Yao Xiao , Tenglong Cong , Hanyang Gu

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引用次数: 0

Abstract

The supercritical water cooled reactor (SCWR) is stands out among the Generation IV reactors with high safety and economy. Understanding the fluid flow and heat transfer characteristics within rod bundles under near-critical conditions is crucial for ensuring the safety of the SCWR core. In this study, computational models utilizing the SST k-ω turbulence model and boundary-resolved grids were validated against heat transfer data for near-critical water within a rod bundle. Subsequently, the validated model was utilized to examine the impacts of system pressure, fluid temperature at inlet, mass flux, and heat flux on the heat transfer characteristics of rod bundle with spacer grids under subcritical and supercritical conditions. The study revealed that the heat-transfer coefficient under supercritical conditions is significantly larger than that under subcritical conditions. Additionally, the heat transfer coefficient increases with mass flux, while independent from pressure and heat flux.

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带间隔网格的杆束中近临界水的热水力学数值研究

超临界水冷反应堆（SCWR）在第四代反应堆中脱颖而出，具有极高的安全性和经济性。了解近临界条件下棒束内的流体流动和传热特性对于确保超临界水冷堆堆芯的安全至关重要。在这项研究中，利用 SST k-ω 湍流模型和边界解析网格的计算模型与棒束内近临界水的传热数据进行了验证。随后，利用验证模型研究了系统压力、入口流体温度、质量通量和热通量在亚临界和超临界条件下对带有间隔网格的杆束传热特性的影响。研究发现，超临界条件下的传热系数明显大于亚临界条件下的传热系数。此外，传热系数随质量通量的增加而增加，与压力和热通量无关。

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.