Laser erosion diagnostics of plasma facing materials with displacement sensors and their application to safeguard monitors to protect nuclear fusion chambers

Koichi Kasuya, Shinji Motokoshi, Seiji Taniguchi, Mitsuo Nakai, Kazutoshi Tokunaga, Waldemar Mroz, Boguslaw Budner, Barbara Korczyc

研究成果: 著書/レポートタイプへの貢献会議での発言

1 引用 (Scopus)

抄録

Tungsten and SiC are candidates for the structural materials of the nuclear fusion reactor walls, while CVD poly-crystal diamond is candidate for the window material under the hazardous fusion stresses. We measured the surface endurance strength of such materials with commercial displacement sensors and our recent evaluation method. The pulsed high thermal input was put into the material surfaces by UV lasers, and the surface erosions were diagnosed. With the increase of the total number of the laser shots per position, the crater depth increased gradually. The 3D and 2D pictures of the craters were gathered and compared under various experimental conditions. For example, the maximum crater depths were plotted as a function of shot accumulated numbers, from which we evaluated the threshold thermal input for the surface erosions to be induced. The simple comparison-result showed that tungsten was stronger roughly two times than SiC. Then we proposed how to monitor the surface conditions of combined samples with such diamonds coated with thin tungsten layers, when we use such samples as parts of divertor inner walls, fusion chamber first walls, and various diagnostic windows. We investigated how we might be able to measure the inner surface erosions with the same kinds of displacement sensors. We found out the measurable maximum thickness of such diamond which is useful to monitor the erosion. Additionally we showed a new scheme of fusion reactor systems with injectors for anisotropic pellets and heating lasers under the probable use of W and/or SiC.

元の言語英語
ホスト出版物のタイトルXX International Symposium on High-Power Laser Systems and Applications 2014
編集者Xiaolin Tang, Shu Chen, Chun Tang
出版者SPIE
ISBN(電子版)9781628413229
DOI
出版物ステータス出版済み - 1 1 2015
イベント20th International Symposium on High Power Systems and Applications 2014, HPLS and A 2014 - Chengdu, 中国
継続期間: 8 25 20148 29 2014

出版物シリーズ

名前Proceedings of SPIE - The International Society for Optical Engineering
9255
ISSN(印刷物)0277-786X
ISSN(電子版)1996-756X

その他

その他20th International Symposium on High Power Systems and Applications 2014, HPLS and A 2014
中国
Chengdu
期間8/25/148/29/14

Fingerprint

Erosion
nuclear fusion
erosion
monitors
Diagnostics
Fusion
Monitor
Fusion reactions
Plasma
chambers
Laser
Plasmas
Sensor
Tungsten
Diamond
Lasers
sensors
Sensors
Strombus or kite or diamond
craters

All Science Journal Classification (ASJC) codes

  • Electronic, Optical and Magnetic Materials
  • Condensed Matter Physics
  • Computer Science Applications
  • Applied Mathematics
  • Electrical and Electronic Engineering

これを引用

Kasuya, K., Motokoshi, S., Taniguchi, S., Nakai, M., Tokunaga, K., Mroz, W., ... Korczyc, B. (2015). Laser erosion diagnostics of plasma facing materials with displacement sensors and their application to safeguard monitors to protect nuclear fusion chambers. : X. Tang, S. Chen, & C. Tang (版), XX International Symposium on High-Power Laser Systems and Applications 2014 [925548] (Proceedings of SPIE - The International Society for Optical Engineering; 巻数 9255). SPIE. https://doi.org/10.1117/12.2065233

Laser erosion diagnostics of plasma facing materials with displacement sensors and their application to safeguard monitors to protect nuclear fusion chambers. / Kasuya, Koichi; Motokoshi, Shinji; Taniguchi, Seiji; Nakai, Mitsuo; Tokunaga, Kazutoshi; Mroz, Waldemar; Budner, Boguslaw; Korczyc, Barbara.

XX International Symposium on High-Power Laser Systems and Applications 2014. 版 / Xiaolin Tang; Shu Chen; Chun Tang. SPIE, 2015. 925548 (Proceedings of SPIE - The International Society for Optical Engineering; 巻 9255).

研究成果: 著書/レポートタイプへの貢献会議での発言

Kasuya, K, Motokoshi, S, Taniguchi, S, Nakai, M, Tokunaga, K, Mroz, W, Budner, B & Korczyc, B 2015, Laser erosion diagnostics of plasma facing materials with displacement sensors and their application to safeguard monitors to protect nuclear fusion chambers. : X Tang, S Chen & C Tang (版), XX International Symposium on High-Power Laser Systems and Applications 2014., 925548, Proceedings of SPIE - The International Society for Optical Engineering, 巻. 9255, SPIE, 20th International Symposium on High Power Systems and Applications 2014, HPLS and A 2014, Chengdu, 中国, 8/25/14. https://doi.org/10.1117/12.2065233
Kasuya K, Motokoshi S, Taniguchi S, Nakai M, Tokunaga K, Mroz W その他. Laser erosion diagnostics of plasma facing materials with displacement sensors and their application to safeguard monitors to protect nuclear fusion chambers. : Tang X, Chen S, Tang C, 編集者, XX International Symposium on High-Power Laser Systems and Applications 2014. SPIE. 2015. 925548. (Proceedings of SPIE - The International Society for Optical Engineering). https://doi.org/10.1117/12.2065233
Kasuya, Koichi ; Motokoshi, Shinji ; Taniguchi, Seiji ; Nakai, Mitsuo ; Tokunaga, Kazutoshi ; Mroz, Waldemar ; Budner, Boguslaw ; Korczyc, Barbara. / Laser erosion diagnostics of plasma facing materials with displacement sensors and their application to safeguard monitors to protect nuclear fusion chambers. XX International Symposium on High-Power Laser Systems and Applications 2014. 編集者 / Xiaolin Tang ; Shu Chen ; Chun Tang. SPIE, 2015. (Proceedings of SPIE - The International Society for Optical Engineering).
@inproceedings{ebd2cbfbc1f643e884f55b02865df293,
title = "Laser erosion diagnostics of plasma facing materials with displacement sensors and their application to safeguard monitors to protect nuclear fusion chambers",
abstract = "Tungsten and SiC are candidates for the structural materials of the nuclear fusion reactor walls, while CVD poly-crystal diamond is candidate for the window material under the hazardous fusion stresses. We measured the surface endurance strength of such materials with commercial displacement sensors and our recent evaluation method. The pulsed high thermal input was put into the material surfaces by UV lasers, and the surface erosions were diagnosed. With the increase of the total number of the laser shots per position, the crater depth increased gradually. The 3D and 2D pictures of the craters were gathered and compared under various experimental conditions. For example, the maximum crater depths were plotted as a function of shot accumulated numbers, from which we evaluated the threshold thermal input for the surface erosions to be induced. The simple comparison-result showed that tungsten was stronger roughly two times than SiC. Then we proposed how to monitor the surface conditions of combined samples with such diamonds coated with thin tungsten layers, when we use such samples as parts of divertor inner walls, fusion chamber first walls, and various diagnostic windows. We investigated how we might be able to measure the inner surface erosions with the same kinds of displacement sensors. We found out the measurable maximum thickness of such diamond which is useful to monitor the erosion. Additionally we showed a new scheme of fusion reactor systems with injectors for anisotropic pellets and heating lasers under the probable use of W and/or SiC.",
author = "Koichi Kasuya and Shinji Motokoshi and Seiji Taniguchi and Mitsuo Nakai and Kazutoshi Tokunaga and Waldemar Mroz and Boguslaw Budner and Barbara Korczyc",
year = "2015",
month = "1",
day = "1",
doi = "10.1117/12.2065233",
language = "English",
series = "Proceedings of SPIE - The International Society for Optical Engineering",
publisher = "SPIE",
editor = "Xiaolin Tang and Shu Chen and Chun Tang",
booktitle = "XX International Symposium on High-Power Laser Systems and Applications 2014",
address = "United States",

}

TY - GEN

T1 - Laser erosion diagnostics of plasma facing materials with displacement sensors and their application to safeguard monitors to protect nuclear fusion chambers

AU - Kasuya, Koichi

AU - Motokoshi, Shinji

AU - Taniguchi, Seiji

AU - Nakai, Mitsuo

AU - Tokunaga, Kazutoshi

AU - Mroz, Waldemar

AU - Budner, Boguslaw

AU - Korczyc, Barbara

PY - 2015/1/1

Y1 - 2015/1/1

N2 - Tungsten and SiC are candidates for the structural materials of the nuclear fusion reactor walls, while CVD poly-crystal diamond is candidate for the window material under the hazardous fusion stresses. We measured the surface endurance strength of such materials with commercial displacement sensors and our recent evaluation method. The pulsed high thermal input was put into the material surfaces by UV lasers, and the surface erosions were diagnosed. With the increase of the total number of the laser shots per position, the crater depth increased gradually. The 3D and 2D pictures of the craters were gathered and compared under various experimental conditions. For example, the maximum crater depths were plotted as a function of shot accumulated numbers, from which we evaluated the threshold thermal input for the surface erosions to be induced. The simple comparison-result showed that tungsten was stronger roughly two times than SiC. Then we proposed how to monitor the surface conditions of combined samples with such diamonds coated with thin tungsten layers, when we use such samples as parts of divertor inner walls, fusion chamber first walls, and various diagnostic windows. We investigated how we might be able to measure the inner surface erosions with the same kinds of displacement sensors. We found out the measurable maximum thickness of such diamond which is useful to monitor the erosion. Additionally we showed a new scheme of fusion reactor systems with injectors for anisotropic pellets and heating lasers under the probable use of W and/or SiC.

AB - Tungsten and SiC are candidates for the structural materials of the nuclear fusion reactor walls, while CVD poly-crystal diamond is candidate for the window material under the hazardous fusion stresses. We measured the surface endurance strength of such materials with commercial displacement sensors and our recent evaluation method. The pulsed high thermal input was put into the material surfaces by UV lasers, and the surface erosions were diagnosed. With the increase of the total number of the laser shots per position, the crater depth increased gradually. The 3D and 2D pictures of the craters were gathered and compared under various experimental conditions. For example, the maximum crater depths were plotted as a function of shot accumulated numbers, from which we evaluated the threshold thermal input for the surface erosions to be induced. The simple comparison-result showed that tungsten was stronger roughly two times than SiC. Then we proposed how to monitor the surface conditions of combined samples with such diamonds coated with thin tungsten layers, when we use such samples as parts of divertor inner walls, fusion chamber first walls, and various diagnostic windows. We investigated how we might be able to measure the inner surface erosions with the same kinds of displacement sensors. We found out the measurable maximum thickness of such diamond which is useful to monitor the erosion. Additionally we showed a new scheme of fusion reactor systems with injectors for anisotropic pellets and heating lasers under the probable use of W and/or SiC.

UR - http://www.scopus.com/inward/record.url?scp=84924012149&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=84924012149&partnerID=8YFLogxK

U2 - 10.1117/12.2065233

DO - 10.1117/12.2065233

M3 - Conference contribution

AN - SCOPUS:84924012149

T3 - Proceedings of SPIE - The International Society for Optical Engineering

BT - XX International Symposium on High-Power Laser Systems and Applications 2014

A2 - Tang, Xiaolin

A2 - Chen, Shu

A2 - Tang, Chun

PB - SPIE

ER -