JT-60SA超高真空环境下应变测量系统设计

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

Fusion Engineering and Design Pub Date : 2025-06-12 DOI:10.1016/j.fusengdes.2025.115245

Shigetoshi Nakamura, Manabu Takechi, Satoshi Yamamoto, Akihiko Isayama, Go Matsunaga

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引用次数: 0

摘要

应变片安装在JT-60SA真空容器内部，以监测施加在支撑误差场校正线圈的基座上的机械负荷。用于JT-60SA的应变片和电缆需要具有(1)耐真空容器200°C的烘烤，(2)在超高真空环境下无有机粘合剂材料以减少放气，(3)长时间连续使用的可行性，因为一旦容器内组件组装完成，就无法接触到测量目标。为了满足这些要求，研制了无有机粘合剂的焊接式应变片及其电缆。该应变片的特点是通过焊接将其连接到客观部件上。焊接式应变仪用电缆由MgO矿物绝缘（MI）电缆和聚醚醚酮（PEEK）电缆组成。MI电缆可承受真空容器200℃的烘烤。PEEK电缆用于连接真空馈电通道。测试系统的设计已成功完成。

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Design of strain measuring system in ultra-high vacuum environment for JT-60SA

Strain gauges are installed inside the JT-60SA vacuum vessel to monitor mechanical load applied on the pedestals for supporting the error field correction coils. The strain gauges and cables for JT-60SA need to have (1) resistance to 200°C baking of the vacuum vessel, (2) no organic adhesive material to reduce outgassing under ultra-high vacuum environment, (3) feasibility of long-duration continuous use, because of no access to the measuring target once assembly of in-vessel components has finished. To meet these requirements, the welded-type strain gauge and its cables without organic adhesive have been developed. The strain gauge is featured by attaching it to the objective component with welding. The cables for the welded-type strain gauge are composed of mineral-insulated (MI) cable with MgO and polyether ether ketone (PEEK) cables. MI cable can withstand the 200 °C baking of the vacuum vessel. PEEK cable is used for connecting to vacuum feed through. Design of the measuring system has finished successfully.

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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.