MHD实验中WCLL TBM模型上的电位作为增殖机组流动分布的指示

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2025-03-01 Epub Date: 2025-02-09 DOI:10.1016/j.fusengdes.2025.114846
L. Bühler, C. Courtessole, C. Koehly, B. Lyu, C. Mistrangelo
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引用次数: 0

摘要

利用卡尔斯鲁厄理工学院(KIT)的MEKKA设备,在磁流体动力学实验中测量了ITER水冷铅锂测试包层模块的比例模型表面的电位分布。电势是一种可以精确记录的物理量。对于强磁场,即对于高哈特曼数,势可以看作是液态金属流动的近似流体动力流函数,通过微分得到核心速度。此外,实验电位数据可以直接与数值模拟进行比较,以验证计算工具和解释测量结果。电位的实验和数值数据证实了从测量压力值得出的预测,即增殖单元内的大部分流量发生在模块两端附近,而在较大的中心区域内,流量几乎可以忽略不计。
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Electric potential on a WCLL TBM mock-up in MHD experiments as indication for flow distribution in breeder units
The distribution of electric potential on the surface of a scaled mock-up of the water-cooled lead lithium test blanket module for ITER has been measured in magnetohydrodynamic experiments using the MEKKA facility at the Karlsruhe Institute of Technology (KIT). The electric potential is a physical quantity that can be recorded with high accuracy. For strong magnetic fields, i.e. for high Hartmann numbers, the potential may be considered as approximate hydrodynamic stream-function of the liquid metal flow, from which the core velocity is obtained by differentiation. Moreover, experimental potential data may be directly compared with numerical simulations for both validation of computational tools and interpretation of measurements. Experimental and numerical data of potential confirm anticipations from measured pressure values that the major fraction of the flow in breeder units occurs near both ends of the module, while in a larger central domain the flow is almost negligible.
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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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