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Mechanism of Hydrogen Transport and the Interaction with Defects in Graphite and Carbon-Based Materials

Research Project

Project/Area Number 13680571
Research Category

Grant-in-Aid for Scientific Research (C)

Allocation TypeSingle-year Grants
Section一般
Research Field Nuclear fusion studies
Research InstitutionKinki University

Principal Investigator

ATSUMI Hisao  Kinki University, Faculty of Science and Engineering, Associate professor, 理工学部, 助教授 (70192979)

Project Period (FY) 2001 – 2004
Project Status Completed (Fiscal Year 2004)
Budget Amount *help
¥4,100,000 (Direct Cost: ¥4,100,000)
Fiscal Year 2004: ¥500,000 (Direct Cost: ¥500,000)
Fiscal Year 2003: ¥1,000,000 (Direct Cost: ¥1,000,000)
Fiscal Year 2002: ¥1,100,000 (Direct Cost: ¥1,100,000)
Fiscal Year 2001: ¥1,500,000 (Direct Cost: ¥1,500,000)
Keywordsgraphite / carbon / hydrogen / plasma facing component / diffusion / trapping / desorption / 昇温脱離 / 核融合炉
Research Abstract

Hydrogen absorption, desorption and diffusion on graphite and carbon materials have been studied to estimate hydrogen recycling and tritium inventory under a fusion reactor environment. Following investigations have been performed during four years supported by the grant-in-aid : 1)detailed estimation on hydrogen absorption process into graphite, 2)clarifying trapping sites for hydrogen in graphite, 3)modeling of hydrogen absorption and desorption and its numerical simulation, 4)hydrogen absorption measurement on atomized carbon. Two processes for hydrogen absorption were identified. The first process would be hydrogen diffusion through crystallite boundaries within a filler grain. The second process would be occurred in migration of hydrogen into a graphite crystallite which controlled by the dissociation at a crystallite surface. Two kinds of hydrogen trapping sites are also determined. The first will be one of lined carbon dangling bonds located at the edge surface of a crystallite with an absorption enthalpy of 2.6 eV, the second will be a solitary carbon dangling bond, such as an interstitial cluster loop edge, with an enthalpy of 4.45 eV. Kinetic simulations have been performed with the model obtained in this project, and the results were compared with thermal desorption spectra of deuterium from graphites which were gas charged, ion irradiated and nano-structured by ball milling. These spectra can be well represented with three kinds of desorption process with activation energies of 1.3,2.6 and 4.4 eV. This model proposed in this study should simulate hydrogen recycling and tritium inventory in a fusion reactor well.

Report

(5 results)
  • 2004 Annual Research Report   Final Research Report Summary
  • 2003 Annual Research Report
  • 2002 Annual Research Report
  • 2001 Annual Research Report
  • Research Products

    (19 results)

All 2004 2003 2002 2001 Other

All Journal Article (13 results) Publications (6 results)

  • [Journal Article] 黒鉛中の水素挙動2004

    • Author(s)
      渥美 寿雄
    • Journal Title

      核融合炉 11

      Pages: 25-29

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Annual Research Report 2004 Final Research Report Summary
  • [Journal Article] Hydrogen Behavior in Graphite.2004

    • Author(s)
      Hisao Atsumi
    • Journal Title

      Nuclear Reactor (Atomic Energy Society of Japan) 11

      Pages: 25-29

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] Hydrogen Retention in Graphite and Carbon Materials under a Fusion Reactor Environment.2003

    • Author(s)
      H.Atsumi
    • Journal Title

      Journal of Nuclear Materials 313-316

      Pages: 546-550

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] Mechanism of Hydrogen Trapping and Transport in Carbon Materials.2003

    • Author(s)
      H.Atsumi
    • Journal Title

      Physica Scripta T103

      Pages: 77-80

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] Hydrogen Absorption and Transport in Graphite Materials.2003

    • Author(s)
      H.Atsumi
    • Journal Title

      Journal of Alloys and Compounds 356-357

      Pages: 705-709

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] 核融合炉用炭素材料中の水素拡散に及ぼす中性子照射効果2002

    • Author(s)
      渥美 寿雄
    • Journal Title

      東北大学金属材料研究所附属材料試験炉利用施設共同利用研究経過報告書 18

      Pages: 23-23

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] High Thermal Conductivity of Graphite Fiber Silicon Carbides for Fusion Reactor Application.2002

    • Author(s)
      L.L.Snead
    • Journal Title

      Journal of Nuclear Materials 307-311

      Pages: 1200-1204

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] Hydrogen Bulk Retention in Graphite and Kinetics of Diffusion.2002

    • Author(s)
      H.Atsumi
    • Journal Title

      Journal of Nuclear Materials 307-311

      Pages: 1466-1470

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] Neutron-Irradiation Effect on Hydrogen Diffusion in Carbon Materials Applied for Nuclear Fusion Reactors.2002

    • Author(s)
      Hisao Atsumi
    • Journal Title

      Progress Reports of the Oarai branch IMR, Tohoku Universitu 18

      Pages: 23-23

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] 水素濃度による黒鉛中の水素拡散係数の変化2001

    • Author(s)
      渥美 寿雄
    • Journal Title

      JAERI-Conf 2001-001

      Pages: 88-96

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] 核融合炉用炭素材料・水素吸蔵用炭素材料の水素吸収に及ぼす中性子照射効果2001

    • Author(s)
      渥美 寿雄
    • Journal Title

      平成13年度大洗研究会報告書

      Pages: 195-203

    • Description
      「研究成果報告書概要(和文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] Variation of Hydrogen Diffusion Coefficient in Graphite with the Change of Hydrogen Concentration.2001

    • Author(s)
      Hisao Atsumi
    • Journal Title

      JAERI-Conf 2001-001

      Pages: 88-96

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Journal Article] Neutron-Irradiation Effect on Hydrogen Absorption into Carbon Materials Applied for Nuclear Fusion Reactors and Hydrogen Storage Materials.2001

    • Author(s)
      Hisao Atsumi
    • Journal Title

      Reports of Oarai Workshop 2001 of Institute for Materials Research, Tohoku University

      Pages: 195-203

    • Description
      「研究成果報告書概要(欧文)」より
    • Related Report
      2004 Final Research Report Summary
  • [Publications] H.Atsumi: "Hydrogen Absorption and Transport in Graphite Materials"Journal of Alloys and Compounds. 356-357. 705-709 (2003)

    • Related Report
      2003 Annual Research Report
  • [Publications] H.Atsumi: "Hydrogen Bulk Retention in Graphite and the Kinetics of Diffusion"Journal of Nuclear Materials. 307-311. 1466-1470 (2002)

    • Related Report
      2002 Annual Research Report
  • [Publications] L.L.Snead, M.Balden, R.A.Causey, H.Atsumi: "High Thermal Conductivity of Graphite Fiber Silicon Carbide Composites for Fusion Reactor Application"Journal of Nuclear Materials. 307-311. 1200-1204 (2002)

    • Related Report
      2002 Annual Research Report
  • [Publications] H.Atsumi: "Hydrogen Retention in Graphite and Carbon Materials under a Fusion Reactor Environment"Journal of Nuclear Materials. 313-316. 546-550 (2003)

    • Related Report
      2002 Annual Research Report
  • [Publications] H.Atsumi: "Mechanism of Hydrogen Trapping and Transport in Carbon Materials"Physica Scripta. T103. 77-80 (2003)

    • Related Report
      2002 Annual Research Report
  • [Publications] H.Atsumi: "Hydrogen Bulk Retention in Graphite and Kinetics of Diffusion"Journal of Nuclear Materials. (印刷中). (2002)

    • Related Report
      2001 Annual Research Report

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Published: 2001-04-01   Modified: 2016-04-21  

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