Characterization of MHD pressure losses in a mock-up of the WCLL Test Blanket Module

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
C. Courtessole, H.-J. Brinkmann, L. Bühler, C. Koehly, J. Roth
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引用次数: 0

Abstract

Liquid metal magnetohydrodynamic (MHD) flows in a scaled mock-up of the water-cooled lead-lithium test blanket module (TBM) were investigated experimentally in the MEKKA laboratory at the Karlsruhe Institute of Technology. The test section faithfully replicates the complex geometry of the current TBM design where liquid metal is distributed to breeder units (BUs) through long electrically coupled manifolds oriented along the poloidal direction, orthogonally to the magnetic field direction. During the experiments, pressure was recorded at various points of the mock-up for several liquid metal flow rates and magnetic fields. The overall pressure drop of the mock-up was analyzed, along with the diverse contributions to the total pressure loss from different components, based on characteristic flow parameters. A correlation for the total MHD pressure drop in the WCLL TBM was derived.
在WCLL测试包层模块的模型中表征MHD压力损失
在德国卡尔斯鲁厄理工学院的MEKKA实验室中,研究了水冷铅锂测试包层模块(TBM)中液态金属磁流体动力学(MHD)的流动。测试部分忠实地复制了当前TBM设计的复杂几何形状,其中液态金属通过沿极向方向垂直于磁场方向的长电耦合歧管分布到增殖单元(BUs)。在实验过程中,在不同的液态金属流速和磁场下,在模型的不同点上记录了压力。基于特征流动参数,分析了模型的总压降,以及不同部件对总压损失的不同贡献。导出了WCLL TBM中总MHD压降的相关性。
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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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