Thermal-hydraulic analysis of a 19-rod bundle LBE cooled fuel assembly with non-uniform rods power distribution by numerical simulation

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2025-02-10 DOI:10.1016/j.anucene.2025.111242

Guanwen Luo, Kuo Wang, Gang Tong, Chong Xie, Xiaohang Wu, Huiyong Zhang, Yiliang Xie, Jiayi Chen

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Abstract

The paper performs numerical analysis on a 19-rod bundle LBE cooled fuel assembly, considering non-uniform rods power distribution. Five typical rods power distribution modes are established. The coolant velocity field, temperature distribution characteristics and heat transfer behavior under various modes are explored. The work also compares thermal–hydraulic behaviors of forced circulation with that of natural circulation condition. Results show the rods with high power-rate enhance surrounding coolant flow. Temperature difference is the largest in internal heated mode. When adopting radial increment mode and peripheral heated mode, the PCT is smaller and temperature distributes more evenly. In terms of heat transfer, there are larger local Nu in the subchannels near the high-power rods, and the largest overall Nu occurs in radial increment mode. The thermal–hydraulic characteristics is more susceptible to non-uniform rods heated condition at natural circulation. Eventually, the suggestions for LBE cooled fuel assembly design and operation are proposed.

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采用数值模拟方法对非均匀棒功率分布的19棒束LBE冷却燃料组件进行热水力分析

本文对考虑非均匀棒功率分布的19棒束式LBE冷却燃料组件进行了数值分析。建立了五种典型的棒体功率分配模式。探讨了不同模式下冷却剂的速度场、温度分布特性和换热行为。本文还比较了强制循环和自然循环条件下的热液特性。结果表明，高功率率棒提高了周围冷却剂流动。内部加热时温差最大。采用径向增量方式和外围加热方式时，PCT更小，温度分布更均匀。在传热方面，靠近大功率棒的子通道局部Nu较大，总体Nu在径向增量模式下最大。在自然循环条件下，热液特性更容易受到加热条件不均匀的影响。最后，对LBE冷却燃料组件的设计和运行提出了建议。

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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.