强不均匀磁场中导电圆形管道内液态金属流的参数研究

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
S. Molokov , G. Politis
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引用次数: 0

摘要

对液态金属毯出口管道中磁流体动力流动的主要流动特性进行了参数研究。这种管道中的流动发生在非均匀的递减磁场中。管道壁是导电的。管壁导电率 c 和磁场梯度 γ 的变化范围很广,分别为 0.01≤c≤0.5 和 0.3≤γ≤0.8,涵盖了与核聚变有关的大多数情况。研究采用了哈特曼数和相互作用参数高值的渐近方法以及 FLUENT。还开发了压降相关性,这对橡皮布设计非常重要。结果表明,随着壁导比的减小,三维效应显著增加。在 c 值较小的情况下,所有场梯度值的非均匀场区域都会出现一个停滞区,这可能会给氚的去除造成困难。如果出口管道很长,三维压降相对较低,但非均匀磁场对速度曲线的影响很大。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Parametric study of liquid metal flows in conducting circular ducts in a strong nonuniform magnetic field
Parametric study of main flow characteristics in magnetohydrodynamic flow in the exit duct from a liquid metal blanket has been performed. The flow in such a duct occurs in a nonuniform, decreasing magnetic field. The duct wall is electrically conducting. The wall conductance ratio, c, and the gradient of the field, γ, have been varied in a wide range, 0.01c0.5 and 0.3γ0.8 covering most of the cases relevant to fusion. The studies have been performed with asymptotic methods for high values of the Hartmann number and interaction parameter, as well as with FLUENT. Pressure drop correlation has been developed, which is important for blanket design. The results show a significant increase in three-dimensional effects with decreasing wall conductance ratio. For small values of c, a stagnant zone is present in the nonuniform field region for all the values of the field gradient, which may create difficulties for tritium removal. If the exit duct is very long, the three-dimensional pressure drop is relatively low, but the effect of the nonuniform magnetic field on the velocity profiles is significant.
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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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