红外定量数据在托卡马克测量与安全中的应用:现状与未来

J. Travere, C. Balorin, G. Caulier, C. Desgranges, G. Dunand, M. Jouve, P. Moreau, N. Ravenel
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引用次数: 4

摘要

在目前的核聚变装置运行过程中,等离子体面组件(pfc)会受到10-20 MW/m2范围内的大热流。理解和防止这些组件在长脉冲放电期间过热是一个关键问题。利用红外照相机与复杂光学系统相结合,测量了托卡马克内腔中pfc的表面温度。由于观察到的红外场景的复杂性和产生的大量数据,红外图像的计算机辅助分析将是ITER的一个关键点,ITER是下一个实时应用和延迟时间分析的聚变装置。本文介绍了Tore Supra基于感兴趣区域(ROI)方法的红外图像分析的现状,并对未来的ITER托卡马克进行了外推。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Image Analysis of Infrared Quantitative Data Applied to Tokamak Survey and Safety: present and future
During operation of present fusion devices, the plasma facing components (PFCs) are submitted to large heat fluxes within a range of 10-20 MW/m2. Understanding and preventing overheating of these components during long pulse discharges is a crucial issue. The surface temperature of the PFCs in the inner chamber of a tokamak is measured by infrared (IR) cameras interfaced with complex optical systems. Due to the complexity of the observed IR scenes and the large amount of data produced, a computer-aided analysis of infrared images will be a key point for ITER, the next fusion device for both real-time applications and deferred-time analysis. This paper describes the current state of IR image analysis based on region of interest (ROI) approach at Tore Supra with an extrapolation to the future ITER tokamak.
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