CFD simulation on flow boiling in full scale 5 × 5 rod bundle

IF 0.4 4区 工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY Kerntechnik Pub Date : 2022-09-30 DOI:10.1515/kern-2022-0031
Bing Ren, F. Gan, Ping Yang
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Abstract

Abstract The paper presents a Computational Fluid Dynamics (CFD) methodology to model gas-liquid boiling flow in a full scale 5 × 5 rod bundle with spacer grid typical in Pressurized Water Reactor (PWR) fuel rod bundle. The CFD modeling method is developed based on the STAR-CCM+ CFD code, including the Eulerian-Eulerian two-fluid model and the improved wall heat partitioning model. The OECD/NRC PWR Sub-channel and Bundle Tests (PSBT) are used as a numerical benchmark to assess the simulation quantitatively. The simulated geometry is a full scale of 5 × 5 fuel rod bundle with 17 spacers, including 7 mixing vane spacers (MV), 8 simple spacers (SS) and 2 non-mixing vane spacers (NMV). The present simulated results are in good agreement with the experimental results, the average error of the simulated cross-section void fraction is less than 20%. Based on the simulations, the axial distributions of second flow intensity, the rod surface temperature, bulk fluid temperature, and the void fraction are discussed. The results show that the spacer grid structures, especially the mixing vane, play an essential part in spreading the bubbles, reducing the void fraction and the rod surface temperature.
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全尺寸5 × 5棒束流动沸腾的CFD模拟
摘要本文采用计算流体力学(CFD)方法对压水堆(PWR)燃料棒束中典型的带间隔栅的全尺寸5 × 5棒束内气液沸腾流动进行了模拟。基于STAR-CCM+ CFD代码开发了CFD建模方法,包括欧拉-欧拉双流体模型和改进的壁面热分配模型。OECD/NRC压水堆子通道和束试验(PSBT)被用作定量评估模拟的数值基准。模拟的几何形状是全尺寸的5 × 5燃料棒束,其中有17个间隔片,包括7个混合叶片间隔片(MV), 8个简单间隔片(SS)和2个非混合叶片间隔片(NMV)。本文的模拟结果与实验结果吻合较好,模拟截面孔隙率的平均误差小于20%。在此基础上,讨论了二次流强度、抽油杆表面温度、总体流体温度和空隙率的轴向分布。结果表明,间隔栅结构,特别是混合叶片,对气泡的扩散、空隙率的降低和棒表面温度的降低起着至关重要的作用。
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
Kerntechnik
Kerntechnik 工程技术-核科学技术
CiteScore
0.90
自引率
20.00%
发文量
72
审稿时长
6-12 weeks
期刊介绍: Kerntechnik is an independent journal for nuclear engineering (including design, operation, safety and economics of nuclear power stations, research reactors and simulators), energy systems, radiation (ionizing radiation in industry, medicine and research) and radiological protection (biological effects of ionizing radiation, the system of protection for occupational, medical and public exposures, the assessment of doses, operational protection and safety programs, management of radioactive wastes, decommissioning and regulatory requirements).
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