The General-Purpose Irradiated Fiber and Foil Experiment for material characterization under fusion-relevant loads

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

Fusion Engineering and Design Pub Date : 2025-05-08 DOI:10.1016/j.fusengdes.2025.115114

Alexander Feichtmayer , Johann Riesch , Bailey Curzadd , Till Höschen , Thomas Schwarz-Selinger , Marcel Appel , Raphaël Colson , Sebastian Estermann , Robert Lürbke , Rudolf Neu

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Abstract

On the path towards nuclear fusion as a future energy source, the development and subsequent qualification of suitable materials play a crucial role. Especially the scarcity of a 14 MeV fusion neutron source represents a major challenge, which can only be partially mitigated by existing alternatives. Furthermore, it is not sufficient to investigate the individual fusion-relevant loads such as irradiation damage, thermomechanical loads and the implantation of hydrogen isotopes in isolation from each other.

For this purpose, the General-Purpose Irradiated Fiber and Foil Experiment (GIRAFFE) was developed at the Max Planck Institute for Plasma Physics (IPP) in Garching, a high-precision tensile testing machine installed in a particle accelerator beamline. The simultaneous application of irradiation damage from high-energy ions, implantation of hydrogen and helium ions as well as thermomechanical loads, enable a previously unachievable simulation of the synergistic effects of a fusion environment. This article describes the technical design of the machine, as well as the possible applications.

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融合相关载荷下材料特性的通用辐照纤维和箔实验

在通往核聚变作为未来能源的道路上，合适材料的开发和后续鉴定起着至关重要的作用。特别是缺乏14兆电子伏的聚变中子源是一个主要的挑战，现有的替代方案只能部分缓解这一挑战。此外，单独研究辐照损伤、热机械载荷和氢同位素注入等与聚变相关的载荷是不够的。为此，位于加兴的马克斯普朗克等离子体物理研究所（IPP）开发了通用辐照纤维和箔实验（GIRAFFE），这是一台安装在粒子加速器束流线上的高精度拉伸试验机。同时应用高能离子辐照损伤、氢离子和氦离子注入以及热机械载荷，使以前无法实现的聚变环境协同效应模拟成为可能。本文介绍了该机器的技术设计，以及可能的应用。

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.