Designing and Simulating an additive manufacturable liquid metal heat pipe for future fusion application

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
M. Bakker , N. Maassen , L. Kaserer
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引用次数: 0

Abstract

The feasibility of a radiatively cooled 3D-printable liquid metal heat pipe (HP) design is assessed. Using the design flexibility offered by 3D-printing, the design of the wick and geometry of the HP were optimised to meet the requirement of 20 MW/m2 heat load for a HP placed in a 1.5 T magnetic field. COMSOL was used to assess the operational limits of the HP, the thermal stresses in the wall, the thermally radiated power, and various materials for the HP. The main parameters are the diameter and spacing of the screen wires and the emissivity, 200 μm, 200 μm and 0.86 respectively. Molybdenum was chosen as the wall material and lithium as the working fluid. The design was made in Siemens NX and then exported to COMSOL. From simulations it was concluded that a molybdenum HP with the final design was capable of handling a steady state heat load of 20 MW/m2.

设计和模拟用于未来核聚变应用的可增材制造液态金属热管
对辐射冷却三维打印液态金属热管(HP)设计的可行性进行了评估。利用三维打印技术提供的设计灵活性,对热管的芯和几何形状进行了优化,以满足在 1.5 T 磁场中放置热管的 20 热负荷要求。COMSOL 用于评估 HP 的工作极限、壁中的热应力、热辐射功率以及 HP 的各种材料。主要参数包括屏蔽线的直径和间距以及发射率,分别为 200、200 和 0.86。壁材料选用钼,工作流体选用锂。设计在西门子 NX 中完成,然后导出到 COMSOL。模拟结果表明,采用最终设计的钼 HP 能够承受稳定状态下 20% 的热负荷。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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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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