Development of an in-vessel special calibration light source for ITER divertor infrared thermography

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

Fusion Engineering and Design Pub Date : 2025-03-23 DOI:10.1016/j.fusengdes.2025.114963

Tomohiko Ushiki , Tatsuo Sugie , Hiroyuki Tachibana , Kosuke Shimizu , Butch Buenavidez , Naoto Kasano , Yuzi Katayanagi , Yoshihiko Nunoya

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引用次数: 0

Abstract

This study designed an in-vessel special calibration light source (heater) for calibrating the total transmittance change of the ITER divertor infrared thermography system. The top plate of this calibration heater was designed having a multi-pyramid structure that uses triangular pyramids to ensure robustness and high reproducibility for calibrations over ITER's 20-year operational period. The triangular pyramid structure enhances robustness by minimizing the impact of changes in surface emissivity, such as changes caused by contamination, on the effective emissivity. A prototype of this calibration heater was fabricated, and its performance was evaluated. The prototype heater demonstrated stable light source performance, achieving a low variation rate of luminance on the heater top plate surface of approximately 3.2 % within the measurement wavelength range of 1.5–4.5 μm by controlling the temperature of the thermocouple embedded in the top plate during several heating cycles. Furthermore, the light source proved to be robust, as the effective emissivity changed by only 4.5 %, even when the local surface emissivity of the top plate varied by ±40 % due to surface contamination.

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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.