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, Kazuo Nakamura, H. Yoshida, S. Sengoku, K. Tsuzuki, Y. Kusama, K. Yamaguchi, T. Muroga

Research output: Contribution to journalConference article

13 Citations (Scopus)

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 languageEnglish
Pages (from-to)673-677
Number of pages5
JournalJournal of Nuclear Materials
Volume329-333
Issue number1-3 PART A
DOIs
Publication statusPublished - Aug 1 2004
EventProceedings of the 11th Conference on Fusion Research - Kyoto, Japan
Duration: Dec 7 2003Dec 12 2003

Fingerprint

Helium
blankets
Deuterium
Stainless Steel
Beam plasma interactions
deuterium
stainless steels
permeability
Stainless steel
Chemical activation
vanadium alloys
helium
activation
Vanadium alloys
Plasmas
coatings
Coatings
Gas permeability
composite materials
Titanium oxides

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • Materials Science(all)

Cite this

Hino, T., Hirohata, Y., Yamauchi, Y., Hashiba, M., Kohyama, A., Katoh, Y., ... 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

Plasma material interaction studies on low activation materials used for plasma facing or blanket component. / Hino, T.; Hirohata, Y.; Yamauchi, Y.; Hashiba, M.; Kohyama, A.; Katoh, Y.; Lee, Y.; Jinushi, T.; Akiba, M.; Nakamura, Kazuo; Yoshida, H.; Sengoku, S.; Tsuzuki, K.; Kusama, Y.; Yamaguchi, K.; Muroga, T.

In: Journal of Nuclear Materials, Vol. 329-333, No. 1-3 PART A, 01.08.2004, p. 673-677.

Research output: Contribution to journalConference article

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
Hino, T. ; Hirohata, Y. ; Yamauchi, Y. ; Hashiba, M. ; Kohyama, A. ; Katoh, Y. ; Lee, Y. ; Jinushi, T. ; Akiba, M. ; Nakamura, Kazuo ; Yoshida, H. ; Sengoku, S. ; Tsuzuki, K. ; Kusama, Y. ; Yamaguchi, K. ; Muroga, T. / Plasma material interaction studies on low activation materials used for plasma facing or blanket component. In: Journal of Nuclear Materials. 2004 ; Vol. 329-333, No. 1-3 PART A. pp. 673-677.
@article{82ae5acd4cb34d518983708e0cdefcd2,
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 Kazuo Nakamura and H. Yoshida and S. Sengoku and K. Tsuzuki and Y. Kusama and K. Yamaguchi and T. Muroga",
year = "2004",
month = "8",
day = "1",
doi = "10.1016/j.jnucmat.2004.04.193",
language = "English",
volume = "329-333",
pages = "673--677",
journal = "Journal of Nuclear Materials",
issn = "0022-3115",
publisher = "Elsevier",
number = "1-3 PART A",

}

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, Kazuo

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.

UR - http://www.scopus.com/inward/record.url?scp=3342922686&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=3342922686&partnerID=8YFLogxK

U2 - 10.1016/j.jnucmat.2004.04.193

DO - 10.1016/j.jnucmat.2004.04.193

M3 - Conference article

AN - SCOPUS:3342922686

VL - 329-333

SP - 673

EP - 677

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

IS - 1-3 PART A

ER -