A laser-based diagnostic for in situ monitoring of fuel retention in ITER

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

Fusion Engineering and Design Pub Date : 2025-06-29 DOI:10.1016/j.fusengdes.2025.115298

A. Huber , Ph. Andrew , G. Sergienko , J. Assmann , D. Castano , A. De Schepper , S. Friese , I. Ivashov , D. Kampf , Y. Krasikov , H.T. Lambertz , Ph. Mertens , K. Mlynczak , K. Rasinska , M. Schrader , D. Van Staden , A. Terra , Xi Jiang , M. Zlobinski , A. Reutlinger , Ch. Linsmeier

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引用次数: 0

Abstract

This paper addresses the critical challenge of tritium inventory control in ITER and future fusion devices, emphasizing the necessity for precise measurement and spatial distribution of tritium within the vacuum vessel. The proposed laser-based T-monitor diagnostic system from Forschungszentrum Jülich employs Laser-Induced Desorption (LID) combined with Residual Gas Analysis (RGA) to measure hydrogen isotope concentrations on the inner divertor tiles. Key design elements include high-power laser integration, advanced optical systems, and a Fast Scanning Mirror Unit for accurate laser spot positioning. The diagnostic aims to measure in situ tritium retention, improving operational safety and efficiency in nuclear fusion environments.

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基于激光的ITER燃料保留原位监测诊断

本文讨论了ITER和未来核聚变装置中氚库存控制的关键挑战，强调了真空容器中氚的精确测量和空间分布的必要性。该激光t -监测诊断系统采用激光诱导解吸（LID）与残余气体分析（RGA）相结合的方法来测量内分流瓦上的氢同位素浓度。关键设计元素包括高功率激光集成、先进的光学系统和用于精确激光光斑定位的快速扫描镜单元。该诊断旨在测量原位氚保留，提高核聚变环境中的操作安全性和效率。

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.