Performance of the insulation mock-up used alumino-silicate fiber composite for Bi-2212 Cable-in-Conduit Conductor

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2024-11-18 DOI:10.1016/j.fusengdes.2024.114723

Jing Sun , Zhaohui Yan , Xin Luo , Jiefeng Wu , Wenge Chen , Zhihong Liu

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Abstract

The process for Bi-2212 CICC is wind & react technology, which places very high demands on the temperature resistance of the insulation material. This study investigated the insulation structural properties of alumino-silicate fibers as insulation fibers. Initially, alumino-silicate fiber resin composites were fabricated and tested for tensile strength, interlaminar shear strength, and high voltage property. The results indicated that the alumino-silicate fiber resin composites possess relatively excellent mechanical and insulation properties. Subsequently, a mock-up, consisting of a 10 × 10 conductor array with a length of 1 meter, was constructed and subjected to a series of tests, including thermal cycling, DC, AC, and Paschen tests, adhering to ITER PF6 specifications. The results demonstrate that the mock-up meets the required criteria for both DC and AC performance. However, in the Paschen test, it exhibits a relatively low breakdown voltage, indicating areas for further optimization.

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Bi-2212 电缆导管中使用的铝硅酸盐纤维复合材料的绝缘模拟性能

Bi-2212 CICC 的工艺是风力& 反应技术，这对绝缘材料的耐温性提出了很高的要求。本研究探讨了铝硅酸盐纤维作为绝缘纤维的绝缘结构特性。首先，制作了铝硅酸盐纤维树脂复合材料，并对其进行了拉伸强度、层间剪切强度和高压性能测试。结果表明，铝硅酸盐纤维树脂复合材料具有相对优异的机械性能和绝缘性能。随后，按照国际热核聚变实验堆 PF6 的技术规范，制作了一个由 10 × 10 导体阵列组成、长度为 1 米的模型，并对其进行了一系列测试，包括热循环、直流、交流和帕申测试。结果表明，该模拟装置在直流和交流性能方面都达到了要求的标准。不过，在帕申测试中，它显示出相对较低的击穿电压，这表明有需要进一步优化的地方。

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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.