Plasma material interaction studies on low activation materials used for plasma facing or blanket component

T. Hino; Y. Hirohata; Y. Yamauchi; M. Hashiba; A. Kohyama; Y. Katoh; Y. Lee; T. Jinushi; M. Akiba; K. Nakamura; H. Yoshida; S. Sengoku; K. Tsuzuki; Y. Kusama; K. Yamaguchi; T. Muroga

doi:10.1016/j.jnucmat.2004.04.193

Plasma material interaction studies on low activation materials used for plasma facing or blanket component

T. Hino, Y. Hirohata, Y. Yamauchi, M. Hashiba, A. Kohyama, Y. Katoh, Y. Lee, T. Jinushi, M. Akiba, K. Nakamura, H. Yoshida, S. Sengoku, K. Tsuzuki, Y. Kusama, K. Yamaguchi, T. Muroga

Research output: Contribution to journal › Conference article › peer-review

14 Scopus citations

Abstract

Numerous issues on the plasma material interactions were investigated for low activation materials. Co-deposited carbon dust was prepared and the deuterium concentration was measured. The concentration was approximately half of the present design value for ITER. For ferritic steel, the deuterium retention was observed to be comparable to that of stainless steel. Physical sputtering yield was roughly the same as that for stainless steel. For the reduction of absorption rate in vanadium alloy, titanium oxide coating was conducted, and the coating was observed to be very effective for reduction of hydrogen absorption. Helium gas permeability was measured for numerous SiC/SiC composites, and the SiC/SiC composite made by the NITE process showed quite low permeability. The SiC/SiC blanket may be able to be used without helium leakage into plasma.

Original language	English
Pages (from-to)	673-677
Number of pages	5
Journal	Journal of Nuclear Materials
Volume	329-333
Issue number	1-3 PART A
DOIs	https://doi.org/10.1016/j.jnucmat.2004.04.193
State	Published - Aug 1 2004
Externally published	Yes
Event	Proceedings of the 11th Conference on Fusion Research - Kyoto, Japan Duration: Dec 7 2003 → Dec 12 2003

Funding

The present study was partly supported by collaboration studies of Japan Atomic Energy Research Institute and National Institute of Fusion Science.

Funders	Funder number
Japan Atomic Energy Research Institute
National Institute for Fusion Science

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1016/j.jnucmat.2004.04.193

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Hino, T., Hirohata, Y., Yamauchi, Y., Hashiba, M., Kohyama, A., Katoh, Y., Lee, Y., Jinushi, T., Akiba, M., Nakamura, K., Yoshida, H., Sengoku, S., Tsuzuki, K., Kusama, Y., Yamaguchi, K., & Muroga, T. (2004). Plasma material interaction studies on low activation materials used for plasma facing or blanket component. Journal of Nuclear Materials, 329-333(1-3 PART A), 673-677. https://doi.org/10.1016/j.jnucmat.2004.04.193

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title = "Plasma material interaction studies on low activation materials used for plasma facing or blanket component",

abstract = "Numerous issues on the plasma material interactions were investigated for low activation materials. Co-deposited carbon dust was prepared and the deuterium concentration was measured. The concentration was approximately half of the present design value for ITER. For ferritic steel, the deuterium retention was observed to be comparable to that of stainless steel. Physical sputtering yield was roughly the same as that for stainless steel. For the reduction of absorption rate in vanadium alloy, titanium oxide coating was conducted, and the coating was observed to be very effective for reduction of hydrogen absorption. Helium gas permeability was measured for numerous SiC/SiC composites, and the SiC/SiC composite made by the NITE process showed quite low permeability. The SiC/SiC blanket may be able to be used without helium leakage into plasma.",

author = "T. Hino and Y. Hirohata and Y. Yamauchi and M. Hashiba and A. Kohyama and Y. Katoh and Y. Lee and T. Jinushi and M. Akiba and K. Nakamura and H. Yoshida and S. Sengoku and K. Tsuzuki and Y. Kusama and K. Yamaguchi and T. Muroga",

year = "2004",

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doi = "10.1016/j.jnucmat.2004.04.193",

language = "English",

volume = "329-333",

pages = "673--677",

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Hino, T, Hirohata, Y, Yamauchi, Y, Hashiba, M, Kohyama, A, Katoh, Y, Lee, Y, Jinushi, T, Akiba, M, Nakamura, K, Yoshida, H, Sengoku, S, Tsuzuki, K, Kusama, Y, Yamaguchi, K & Muroga, T 2004, 'Plasma material interaction studies on low activation materials used for plasma facing or blanket component', Journal of Nuclear Materials, vol. 329-333, no. 1-3 PART A, pp. 673-677. https://doi.org/10.1016/j.jnucmat.2004.04.193

TY - JOUR

T1 - Plasma material interaction studies on low activation materials used for plasma facing or blanket component

AU - Hino, T.

AU - Hirohata, Y.

AU - Yamauchi, Y.

AU - Hashiba, M.

AU - Kohyama, A.

AU - Katoh, Y.

AU - Lee, Y.

AU - Jinushi, T.

AU - Akiba, M.

AU - Nakamura, K.

AU - Yoshida, H.

AU - Sengoku, S.

AU - Tsuzuki, K.

AU - Kusama, Y.

AU - Yamaguchi, K.

AU - Muroga, T.

PY - 2004/8/1

Y1 - 2004/8/1

N2 - Numerous issues on the plasma material interactions were investigated for low activation materials. Co-deposited carbon dust was prepared and the deuterium concentration was measured. The concentration was approximately half of the present design value for ITER. For ferritic steel, the deuterium retention was observed to be comparable to that of stainless steel. Physical sputtering yield was roughly the same as that for stainless steel. For the reduction of absorption rate in vanadium alloy, titanium oxide coating was conducted, and the coating was observed to be very effective for reduction of hydrogen absorption. Helium gas permeability was measured for numerous SiC/SiC composites, and the SiC/SiC composite made by the NITE process showed quite low permeability. The SiC/SiC blanket may be able to be used without helium leakage into plasma.

AB - Numerous issues on the plasma material interactions were investigated for low activation materials. Co-deposited carbon dust was prepared and the deuterium concentration was measured. The concentration was approximately half of the present design value for ITER. For ferritic steel, the deuterium retention was observed to be comparable to that of stainless steel. Physical sputtering yield was roughly the same as that for stainless steel. For the reduction of absorption rate in vanadium alloy, titanium oxide coating was conducted, and the coating was observed to be very effective for reduction of hydrogen absorption. Helium gas permeability was measured for numerous SiC/SiC composites, and the SiC/SiC composite made by the NITE process showed quite low permeability. The SiC/SiC blanket may be able to be used without helium leakage into plasma.

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U2 - 10.1016/j.jnucmat.2004.04.193

DO - 10.1016/j.jnucmat.2004.04.193

M3 - Conference article

AN - SCOPUS:3342922686

SN - 0022-3115

VL - 329-333

SP - 673

EP - 677

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 1-3 PART A

T2 - Proceedings of the 11th Conference on Fusion Research

Y2 - 7 December 2003 through 12 December 2003

ER -

Plasma material interaction studies on low activation materials used for plasma facing or blanket component

Abstract

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UN SDGs

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