托卡马克COMPASS-U型高温真空绝缘体的热测试

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-06-22 DOI:10.1016/j.fusengdes.2025.115259

P. Bartoň , P. Holejšovská , M. Šebík , Š. Fuková , J. Varju

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引用次数: 0

摘要

本研究介绍了布拉格IPP的COMPASS升级（COMPASS- u）托卡马克高温真空绝缘体的开发和测试。这包括开发一种特定的高真空高温（500°C）测试设备，能够在类似托卡马克的环境中测试绝缘性能。首先，测试了基线绝缘选项，如被动隔热罩，以验证所使用方法的合理性。然后，对几种商业绝缘材料（微孔绝缘、多层绝缘等）进行了测试，结果与理论预测相符。最后，我们开发了具有良好热性能的mli类绝缘材料，但增加了对电磁感应力的抵抗力，并测量了其不同层数的性能。

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Thermal testing of high-temperature vacuum insulations for tokamak COMPASS-U

This study presents the development and testing of high-temperature vacuum insulations for the COMPASS Upgrade (COMPASS-U) tokamak at IPP Prague. This included the development of a specific high-vacuum high-temperature (500 °C) testing apparatus, able to test the insulation performance in a tokamak-like environment. At first, baseline insulation options, such as passive heat shields, were tested to verify the soundness of the method used. Then, several commercial insulations (microporous insulation, multilayer insulation,

\dots

) were tested, with results that matched the theoretical predictions. Finally, we have developed our MLI-like insulation with good thermal properties but increased resistance against electromagnetic-induced forces and measured its performance with various amounts of layers.

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来源期刊

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.