Investigation on cross-flow characteristics of two different mixing vane grid in a 5 × 5 rod bundle

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

Annals of Nuclear Energy Pub Date : 2024-09-27 DOI:10.1016/j.anucene.2024.110934

Li Jiang, Jianqiang Shan, Shan Zhou, Yixiang Zou, Junliang Guo, Miao Gui

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Abstract

To comprehend the combined mixing effects downstream two different MVGs installed at same axial height, individual analysis of these MVGs is the precondition. In this paper, an experimental study on the crossflow distribution downstream two different split-type MVGs is presented by PIV in a 5 × 5 rod bundle. The cross flow in the sixteen inner subchannels is obtained at elevation from 1.8 D_h to 25 D_h downstream grids. For both two types of grids, two individual co-rotating vortices are observed near the grid in each subchannel and inter-subchannel cross flow increases before approximate 3 D_h and decays exponentially. The secondary-flow and cross-flow intensity of grid type Ⅰ overweigh the type Ⅱ and the intensities are corelated to horizontal projected area of vane. Based on the experimental results, an improved subchannel mixing grid model is proposed and the predicted cross flow in the gap is in good agreement with measured results.

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研究 5 × 5 杆束中两种不同混合叶栅的横流特性

要理解安装在同一轴向高度的两个不同 MVG 下游的组合混合效应，前提条件是对这些 MVG 进行单独分析。本文通过 PIV 对 5 × 5 杆束中两个不同分体式 MVG 下游的横流分布进行了实验研究。从 1.8 Dh 到 25 Dh 的下游网格海拔高度上获得了 16 个内部子通道中的横流。对于这两种类型的网格，在每个子通道的网格附近都观察到两个单独的共同旋转涡流，子通道间的交叉流在近似 3 Dh 之前增加并呈指数衰减。栅格类型Ⅰ的二次流和交叉流强度大于类型Ⅱ，强度与叶片的水平投影面积成正比。根据实验结果，提出了一种改进的子通道混合网格模型，其预测的间隙交叉流与实测结果非常吻合。

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

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.