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2005 Fiscal Year Final Research Report Summary

Tritium behavior at formation of re-deposition layer from plasma facing material

Research Project

Project/Area Number 15360493
Research Category

Grant-in-Aid for Scientific Research (B)

Allocation TypeSingle-year Grants
Section一般
Research Field Nuclear fusion studies
Research InstitutionKYUSHU UNIVERSITY

Principal Investigator

NISHIKAWA Masabumi  Kyushu University, Graduate School of Engineering Science, Professor, 大学院・総合理工学研究院, 教授 (90026229)

Project Period (FY) 2003 – 2005
Keywordsplasma facing material / re-deposition layer / tritium uptake / RF plasma / graphite / tungsten / co-deposition / dust formation
Research Abstract

In order to understand the tritium behavior at formation of re-deposition layer of plasma facing materials in a fusion reactor, experimental research has been performed using RF hydrogen plasma reactors in this study and new observations are obtained.
(1)The re-deposition layer of graphite or tungsten has the porous construction and it contains rather large amount of hydrogen. The H/C ratio observed in this study is 0.1-0.3, and that of H/W is about 0.1. It is known that solubility of hydrogen in tungsten is negligibly small. Accordingly, observation in this study suggests that dusts formed in fusion reactor may contain much more tritium than expected at present.
(2)The amount of hydrogen trapped in the co-deposition layer of graphite and tungsten is observed. The release behavior from co-deposition layer is different from the behavior of the re-deposition layer of single component.
(3)The deuterium plasma gives several times larger re-position layer than the hydrogen plasma. This suggests that the DT plasma may give thicker re-deposition layer than the hydrogen plasma.
(4).The empirical equation for the forming rate of re-deposition layer is made.

  • Research Products

    (9 results)

All 2006 2005

All Journal Article (8 results) Book (1 results)

  • [Journal Article] Release behavior of hydrogen isotopes 【rom】T-60U graphite tiles2005

    • Author(s)
      K.Katayama, T.Takeishi, Y.Manabe, H.Nagase, M.Nishikawa, N.Miya
    • Journal Title

      Fusion Science and Technology 48.1

      Pages: 561-564

    • Description
      「研究成果報告書概要(和文)」より
  • [Journal Article] Hydrogen retention in a tungsten re-deposition layer by hydrogen RF plasma2005

    • Author(s)
      T.Kawasaki, Y.Manabe, K.Katayama, T.Takeishi, M.Nishikawa
    • Journal Title

      Fusion Science and Technology 48.1

      Pages: 581-584

    • Description
      「研究成果報告書概要(和文)」より
  • [Journal Article] Recovery of retained tritium from graphite tiles of JT-60U2005

    • Author(s)
      T.Takeishi, K.Katayama, M.Nishikawa, N.Miya, K.Masaki
    • Journal Title

      Fusion Science and Technology 48.1

      Pages: 565-568

    • Description
      「研究成果報告書概要(和文)」より
  • [Journal Article] Tritium release behavior from the graphite tiles at the dome unit of the W-shaped diverter region in JT-60U2005

    • Author(s)
      K.Katayama, T.Takeishi, Y.Manabe, H.Nagase, M.Nishikawa, N.Miya
    • Journal Title

      Journal of Nuclear Materials 340.1

      Pages: 83-92

    • Description
      「研究成果報告書概要(和文)」より
  • [Journal Article] Release behavior of hydrogen isotopes from JT-60 U graphite tiles2005

    • Author(s)
      K.Katayama, T.Takeishi, Y.Manabe, H.Nagase, M.Nishikawa, N.Miya
    • Journal Title

      Fusion Science and Technology Vol.48(1)

      Pages: 561-564

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] Hydrogen retention in a tungusten Re-deposition layer by hydrogen RF Plasma2005

    • Author(s)
      T.Kawasaki, Y.Manabe, K.Katayama, T.Takeishi, M.Nishikawa
    • Journal Title

      Fusion Science and Technology Vol.48(1)

      Pages: 581-584

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] Recovery of retained tritium from graphite tiles of JP-60U2005

    • Author(s)
      T.Takeishi, K.Katayama, M.Nishikawa, N.Miya, K.Masaki
    • Journal Title

      Fusion Science and Technology Vol.48(1)

      Pages: 565-568

    • Description
      「研究成果報告書概要(欧文)」より
  • [Journal Article] Tritium release behavior from the Graphite tiles at the dome unit of the W-shaped divertor region in JT-60U2005

    • Author(s)
      K.Katayama, T.Takeishi, Y.Manabe, H.Nagase, M.Nishikawa, N.Miya
    • Journal Title

      Journal of Nuclear Materials Vol.340

      Pages: 83-92

    • Description
      「研究成果報告書概要(欧文)」より
  • [Book] 水素-将来のエネルギーを目指して2006

    • Author(s)
      西川正史, 深田智, 渡辺幸信
    • Total Pages
      310
    • Publisher
      養賢堂
    • Description
      「研究成果報告書概要(和文)」より

URL: 

Published: 2007-12-13  

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