Preliminary Examination of Reflection Coefficient Measurement of RGB Lights on the First Wall in LHD-Reference-Cited by-同舟云学术

Preliminary Examination of Reflection Coefficient Measurement of RGB Lights on the First Wall in LHD

Published:2015 Issue:0 Volume:10 Page:1202074-1202074
ISSN:1880-6821
Container-title:Plasma and Fusion Research
language:en
Short-container-title:Plasma and Fusion Research

Author:

MOTOJIMA Gen¹,YOSHIDA Naoaki²,MURASE Takanori¹,TANAKA Hirohiko¹,MASUZAKI Suguru¹,SAKAMOTO Ryuichi¹,TOKITANI Masayuki¹,MATSUMOTO Kenji³,MIYAMOTO Mitsutaka⁴,YAJIMA Miyuki¹,SAKAMOTO Mizuki⁵,YAMADA Hiroshi¹,MORISAKI Tomohiro¹,

Affiliation:

1. National Institute for Fusion Science

2. Research Institute for Applied Mechanics, Kyushu University

3. Honda R & D Co. Ltd.

4. Department of Material Science, Shimane University

5. Plasma Research Center, University of Tsukuba

Publisher

Japan Society of Plasma Science and Nuclear Fusion Research

Subject

Condensed Matter Physics

Link

https://www.jstage.jst.go.jp/article/pfr/10/0/10_1202074/_pdf

Reference7 articles.

1. [1] G. Motojima et al., J. Nucl. Mater. 463, 1080 (2015).

2. [2] M. Tokitani et al., J. Nucl. Mater. 463, 91 (2015).

3. [3] P. Wienhold et al., J. Nucl. Mater. 220-222, 452 (1995).

4. [4] T. Shimoji, 2015 Thickness evaluation of deposition layer of plasma facing components by color measurements in QUEST, Master's Thesis (in Japanese).

5. [5] Karsten Hinriches et al., Ellipsometry of Functional Organic Surfaces and Films (Springer, 2013) p.16.

Cited by 5 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Validation of the plasma-wall interaction simulation code ERO2.0 by the analysis of tungsten migration in the open divertor region in the Large Helical Device;Nuclear Materials and Energy;2022-10

2. Colorimetry in Nuclear Fusion Research;Colorimetry;2022-07-20

3. Simulation Analysis of the Carbon Deposition Profile on Directional Material Probes in the Large Helical Device Using the ERO2.0 Code;Plasma and Fusion Research;2022-03-30

4. Exhaust behavior of tritium from the large helical device in the first deuterium plasma experiment;Journal of Nuclear Science and Technology;2020-06-24

5. Simulation of impurity transport in the peripheral plasma due to the emission of dust in long pulse discharges on the Large Helical Device;Nuclear Materials and Energy;2017-08