Radiation effects in optical fibres measured during JET DT plasma experiments

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

Fusion Engineering and Design Pub Date : 2025-04-03 DOI:10.1016/j.fusengdes.2025.115011

M Maslov , D Kos , Z Ghani , A Milocco , Z Huang , B Gray , I Ipatova , the JET contributors and the EUROfusion Tokamak Exploitation Team

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引用次数: 0

Abstract

In 2021 and 2023 JET has completed experiments with D/T plasma mixtures where a significant amount of 14 MeV neutrons were released. To collect experimental data on the effect of fusion relevant radiation environment on optical fibres, a 60 metres long pure fused silica fibre has been coiled and placed in the vicinity of the JET machine to accumulate neutron and gamma dose during these experiments. Existing high-OH content radiation resistant fibres were used to connect the sample fibre with the lab space outside the neutron shield, so that the change in optical properties could be measured remotely in real time during and between JET plasma pulses. Significant amount of data was collected over that period. Radiation-induced emission (RIE) was observed over the whole measured spectrum but was dominant in the blue range. Prompt radiation-induced attenuation (RIA) is also dominant the blue range of spectrum and very weak in the near-infrared. The majority of the short-term radiation-induced damage recovers within 1 h after the irradiation, but a fraction of the transmission loss remained permanent.

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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.