Design of 1D carbon fiber composite tiles infrared diagnostic calorimeter for the CRAFT NNBI test platform

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

Fusion Engineering and Design Pub Date : 2025-06-17 DOI:10.1016/j.fusengdes.2025.115279

Yue Hu , Yongjian Xu , Tao Yang , Yahong Xie , Chundong Hu , Lizhen Liang

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引用次数: 0

Abstract

A novel bidirectional, remotely operable diagnostic calorimeter has been developed for the Comprehensive Research Facility for Fusion Technology (CRAFT) Negative Neutral Beam Injection (NNBI) test platform to evaluate beam uniformity and divergence. The system employs 1D-carbon fiber composite (CFC) tiles, selected for their exceptional thermal conductivity and high-temperature resistance, ensuring accurate diagnostics under extreme operating conditions. The calorimeter comprises a 4 × 4 array of CFC tiles, a robust support structure, and a precise linear motion system, enabling accurate positioning within the vacuum chamber. Integrated infrared (IR) cameras provide thermal imaging capabilities, while finite element analysis (FEA) confirms the thermodynamic performance of the CFC tile and the mechanical reliability of the design. Following successful fabrication and installation, the system was fully integrated into the NNBI test platform in early 2024. This diagnostic calorimeter offers a reliable solution for evaluating the characteristics of negative neutral beams and establishes a solid foundation for future experimental research in fusion technology.

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用于CRAFT NNBI测试平台的1D碳纤维复合瓦红外诊断量热计的设计

为融合技术综合研究设施（CRAFT）负中性束注入（NNBI）测试平台开发了一种新型的双向远程可操作诊断量热计，用于评估光束均匀性和发散性。该系统采用1d碳纤维复合材料（CFC）瓦片，其优异的导热性和耐高温性使其得以选择，确保在极端操作条件下进行准确诊断。该量热计由4 × 4的CFC瓦片阵列、坚固的支撑结构和精确的线性运动系统组成，可在真空室内进行精确定位。集成红外（IR）摄像机提供热成像功能，而有限元分析（FEA）证实了CFC瓷砖的热力学性能和设计的机械可靠性。在成功制造和安装之后，该系统于2024年初完全集成到NNBI测试平台中。该诊断量热计为评价负中性光束的特性提供了可靠的解决方案，为今后核聚变技术的实验研究奠定了坚实的基础。

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 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.