用于ITER广角观测系统(WAVS)诊断的全尺寸镀铑第一反射镜的光学特性

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
E. León-Gutierrez , R. López Heredero , C. Rodriguez , M.C. Torquemada , R. García-López , J.M. Fernandez Marin , C.L. Barber Daza , C. Pastor , M. Medrano , R. Vila , J.J. Piqueras , F. Le Guern , A. Pereira
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引用次数: 0

摘要

在ITER的赤道可见和红外广角观测系统(WAVS)诊断装置的前部安装了几个第一面反射镜。对由不锈钢(SS316L)制造并涂覆的全尺寸WAVS球面第一反射镜原型进行了光学表征。测量了可见光范围(400 ~ 1100 nm)的反射率和波前误差。专门开发了一个特别的实验装置,以实现对大型和弯曲镜子的精确反射率测量。测得的波前误差峰谷比(PV)为波长(λ)的1.695倍,均方根误差(RMS)为125.3 nm满足规定的公差,孔径间的反射率不均匀性低于10%。为了评估涂层的稳定性,在高真空(10 - 9兆帕)下,镜子在100°C和240°C之间进行了三个热循环。在热循环前后进行的光学反射率测量显示没有明显变化,证实了铑涂层的热机械稳定性。这些结果验证了制造工艺和涂层性能,证明了该反射镜设计适合ITER的WAVS诊断系统苛刻的操作条件。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Optical characterization of a full scale rhodium coated first mirror for ITER Wide Angle Viewing System (WAVS) diagnostic
Several first mirrors are located at the front of the equatorial visible and infrared Wide Angle Viewing System (WAVS) diagnostic in ITER. Optical characterization of a full-scale WAVS spherical first mirror prototype, manufactured from stainless steel (SS316L) and coated were conducted. Optical reflectance in the visible range (400–1100 nm) and wavefront error were measured. An ad-hoc experimental setup was specifically developed to enable accurate reflectance measurements of large and curved mirrors. The measured wavefront error was Peak to Valley (PV) of 1.695 times the wavelength (λ) and a Root Mean Square (RMS) of 125.3 nm met the specified tolerances, and reflectance inhomogeneity across the aperture was below 10%. To assess coating stability, the mirror was subjected to three thermal cycles between 100 °C and 240 °C under high vacuum (10⁻9 MPa). Optical reflectance measurements performed before and after thermal cycling showed no significant changes, confirming the thermomechanical stability of the rhodium coating. These results validate both the manufacturing process and the coating performance, demonstrating the suitability of this mirror design for the demanding operational conditions of ITER’s WAVS diagnostic system.
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来源期刊
Fusion Engineering and Design
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.
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