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

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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

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All Science Journal Classification (ASJC) codes

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

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