核沸腾条件下 5×5 燃料组件内杂质颗粒迁移和沉积的数值模拟

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2024-11-25 DOI:10.1016/j.anucene.2024.111076

Hongkang Tian , Tenglong Cong , Maolong Liu , Mengke Cai , Zijian Huang , Hanyang Gu

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引用次数: 0

摘要

腐蚀产物沉积在包壳表面会给压水堆带来许多问题，例如 CRUD 引起的功率偏移、局部腐蚀和放射性风险增加。为了深入了解燃料组件内的结垢行为，采用 CFD 方法研究了杂质颗粒的迁移和沉积，其中考虑了欧拉双流体模型、物种迁移模型和结垢沉积模型。研究了污垢沉积速率与热液压参数之间的关系，并分析了污垢厚度沿轴向和圆周方向的分布。结果表明，在一个加油周期内，最大污垢厚度达到 44 µm。与内杆相比，角杆在单相区的污垢厚度较高，而在成核沸腾区的污垢厚度较低。本研究获得的结果可为研究反应堆堆芯内的沉积行为提供参考。

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Numerical simulation of impurity particles migration and deposition within the 5 × 5 fuel assembly under nucleate boiling conditions

Deposition of corrosion products on the cladding surface can cause many problems in PWRs, such as CRUD-induced power shift, localized corrosion, and increased radioactive risk. To gain a deeper understanding of fouling behavior within the fuel assembly, the migration and deposition of impurity particles were investigated with CFD method, where the Eulerian two-fluid model, species transport model, and fouling deposition model are considered. The relationship between fouling deposition rate and thermal–hydraulic parameters was investigated, and the distribution of fouling thickness along both the axial and circumferential directions was analyzed. The results show that the maximum fouling thickness reaches 44 µm in a refueling cycle. Compared with the inner rods, the corner rods have a higher fouling thickness in single-phase region and a lower fouling thickness in nucleate boiling region. The results obtained in this study could provide a reference for the investigation of deposition behavior within the reactor core.

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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.