First operation of LLMHD loop with electromagnet for R & D MHD experiments

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-08-10 DOI:10.1016/j.fusengdes.2024.114614
A. Patel , S. Verma , A. Saraswat , P. Satyamurthy , S. Malhotra , R. Bhattacharyay , S. Gupta , A. Prajapati , M. Kumar , T.S. Rao , A. Makwana , D. Sharma , A. Jaiswal , D. Mohanta , S.K. Sharma , V. Vasava , H. Tailor , A. Deoghar , S. Sahu , C. Dodiya , S. Ranjith Kumar
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Abstract

The Liquid Lead lithium Magneto Hydro Dynamics (LLMHD) experimental facility has been constructed at Institute for Plasma Research (IPR), Gujarat, India to perform various R & D MHD experiments associated with the flow of electrically conducting liquid metal under strong transverse magnetic field. The electromagnet having C-shaped soft iron core has been designed and developed, to provide a uniform magnetic field of up to 1.4T within its polar volume 1000 mm (H) ×400 mm (W) ×370 mm (L). The magnetic field lines are aligned along the length (L). A relatively large polar volume inside the electromagnet to place the test mock up for MHD experiments is its particularity. It enables the study of MHD flows with complex flow geometries and having longer flow length perpendicular to the magnetic field. We have started running the LLMHD loop and the first MHD experiments with Pb-Li have been performed so far at 320 °C in a test mock-up of a basic circular flow geometry having two 90° bends. So far till now, the isothermal MHD experiments have been conducted in the presence of a uniform transverse magnetic field of 0.62T (Ha ∼ 322) and 1.06T (Ha∼551) for the ranges of Reynolds number 20,000–50,000. During the MHD experiments, flow rates, temperature, pressure, and induced wall electric potential have been recorded. The MHD effects on the pressure drop and flow rate has been noticed. The 3D MHD numerical simulation has also been performed, using add on MHD module of ANSYS FLUENT. Both simulation and experimental results of the induced wall electric potential have been compared.

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带电磁铁的 LLMHD 环路首次运行,用于 MHD 研发实验
印度古吉拉特邦等离子体研究所(IPR)建造了液态铅锂磁流体动力学(LLMHD)实验设施,用于在强横向磁场下进行与导电液态金属流相关的各种研发 MHD 实验。设计和开发的电磁铁具有 C 型软铁芯,可在其 1000 毫米(高)×400 毫米(宽)×370 毫米(长)的极性体积内提供高达 1.4T 的均匀磁场。磁场线沿长度(L)排列。电磁铁内部有一个相对较大的极区,可用于放置 MHD 实验的测试模型,这是它的特点。它可以研究具有复杂流动几何形状和垂直于磁场的较长流动长度的 MHD 流。我们已经开始运行 LLMHD 环路,并在 320 °C 温度下,在具有两个 90° 弯曲的基本圆形流动几何形状的试验模型中进行了首次铅-锂 MHD 实验。迄今为止,在雷诺数为 20,000 至 50,000 的范围内,在 0.62T (Ha ∼ 322)和 1.06T (Ha∼551)的均匀横向磁场存在下进行了等温 MHD 实验。在 MHD 实验中,记录了流速、温度、压力和诱导壁电动势。我们注意到了 MHD 对压降和流速的影响。此外,还使用 ANSYS FLUENT 的附加 MHD 模块进行了三维 MHD 数值模拟。对诱导壁电动势的模拟和实验结果进行了比较。
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来源期刊
Fusion Engineering and Design
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.
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