Design and construction of GaInSn experimental facility for studies of mixed-convection MHD flows

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-09-10 DOI:10.1016/j.fusengdes.2024.114654

Jiandong Zhou , Yuhao Tang , Yanwu Cao , Ze Lyu , Kecheng Jiang , Juancheng Yang , MingJiu Ni

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Abstract

A multifunctional liquid metal loop named MaTHE-XJTU (Magneto-Thermo-Hydrodynamic Experiments-Xi'an Jiaotong University) that utilizes eutectic alloy GaInSn as a working fluid has been designed and constructed. The function of the MaTHE-XJTU facility is to study the magnetohydrodynamic (MHD) flow and mixed convection characteristics under the coupling effect. The main operating parameters of the loop are: the maximum magnetic field intensity is 3T, the effective magnetic field region is 300 mm × 800 mm × 1000 mm, the maximum flow rate of electromagnetic pump (EM pump) is 8 m³/h, the maximum pressure head of EM pump is 0.5 MPa. The paper describes the major components and basic operation procedures of the loop, the related flow diagnostics method, and near-future experiments. This loop could provide a high-parameter experimental platform (Ha∼10⁴, Gr∼10⁹, Re∼10⁴) for investigations that improve the present understanding of magnetohydrodynamic and heat transfer performance in liquid metal blankets.

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设计和建造用于研究混合对流 MHD 流动的 GaInSn 实验设施

我们设计并建造了一个以共晶合金 GaInSn 为工作流体的多功能液态金属环，命名为 MaTHE-XJTU（磁流体力学实验-西安交通大学）。MaTHE-XJTU 设备的功能是研究耦合效应下的磁流体动力学（MHD）流动和混合对流特性。环路的主要运行参数为：最大磁场强度为 3T，有效磁场区域为 300 mm × 800 mm × 1000 mm，电磁泵（EM pump）的最大流量为 8 m3/h，电磁泵的最大压头为 0.5 MPa。本文介绍了环路的主要组成部分和基本操作流程、相关的流量诊断方法以及近期的实验。该回路可提供一个高参数实验平台（Ha∼104、Gr∼109、Re∼104），用于研究提高目前对液态金属毯中磁流体动力学和传热性能的认识。

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来源期刊

Fusion Engineering and Design 工程技术-核科学技术

CiteScore

3.50

自引率

23.50%

发文量

275

审稿时长

3.8 months

期刊介绍： The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.