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Evaluation and Mechanism Understanding of Mechanical Property Changes by Hydrogen Addition in Tungsten Irradiated by Particle Beams

Research Project

Project/Area Number 21H01068
Research Category

Grant-in-Aid for Scientific Research (B)

Allocation TypeSingle-year Grants
Section一般
Review Section Basic Section 14020:Nuclear fusion-related
Research InstitutionKagoshima University

Principal Investigator

Sato Koichi  鹿児島大学, 理工学域工学系, 教授 (30378971)

Co-Investigator(Kenkyū-buntansha) 笠田 竜太  東北大学, 金属材料研究所, 教授 (20335227)
畠山 賢彦  富山大学, 学術研究部都市デザイン学系, 准教授 (30375109)
徐 ぎゅう  京都大学, 複合原子力科学研究所, 准教授 (90273531)
Project Period (FY) 2021-04-01 – 2024-03-31
Project Status Completed (Fiscal Year 2023)
Budget Amount *help
¥17,810,000 (Direct Cost: ¥13,700,000、Indirect Cost: ¥4,110,000)
Fiscal Year 2023: ¥3,380,000 (Direct Cost: ¥2,600,000、Indirect Cost: ¥780,000)
Fiscal Year 2022: ¥3,380,000 (Direct Cost: ¥2,600,000、Indirect Cost: ¥780,000)
Fiscal Year 2021: ¥11,050,000 (Direct Cost: ¥8,500,000、Indirect Cost: ¥2,550,000)
Keywords水素 / タングステン / 機械的特性 / 微小試験 / 粒子線照射
Outline of Research at the Start

核融合炉は、水素同位体のプラズマ状態(物質を例えば1億度以上の高温に維持すると得られる)を磁場で閉じ込めることで起きる核融合反応において発生するエネルギーを発電に利用する。その中にダイバータというプラズマ中の不純物の除去や熱負荷・粒子負荷の除去を行う部分がある。ダイバータにはタングステンという材料が用いられる。核融合炉の運転中、ダイバータ内には水素が発生・侵入する。一般に材料中に水素が存在すると水素脆化という劣化現象が起こる。タングステンの水素による強度特性の変化を調べ、タングステンダイバータが核融合炉運転中に水素によって劣化してもその形状を維持できることを示すことが本研究の目的である。

Outline of Final Research Achievements

Tungsten samples were irradiated with ions at different temperatures, and those irradiated with electrons at different irradiation doses were annealed. In consequence, various sizes of vacancy clusters were formed. Upon hydrogen charging, samples including vacancies or small vacancy clusters hardened. In contrast, samples including large vacancy clusters did not exhibit changes in hardness. The cause of hardening due to hydrogen charging is expected to be that the vacancies and small vacancy clusters captured hydrogen, thereby more strongly hindering dislocation movement. Micro-tensile and micro-compression tests were also attempted on the ion-irradiated materials, but due to the shallow damage region and the small sample size, good results could not be obtained.

Academic Significance and Societal Importance of the Research Achievements

空孔型欠陥が水素を捕獲することによって硬くなることはシミュレーションによって報告されているが、その空孔型欠陥の中で原子空孔や小さな原子空孔集合体が水素を捕獲した場合のみ、硬さが上昇することを実験的に示すことができた。これは本研究で得られた学術的な知見の一つである。また、本研究からダイバータの冷却管近傍が水素によって硬化することが分かった。一般に強度と延性はトレードオフの関係にあるため、水素が存在する中で硬化と延性がどのような関係にあるのかを解明する必要があるが、その結果次第で核融合炉の設計において本研究の効果を考慮する必要が出てくることが分かった。これが得られた社会的意義の一つである。

Report

(4 results)
  • 2023 Annual Research Report   Final Research Report ( PDF )
  • 2022 Annual Research Report
  • 2021 Annual Research Report
  • Research Products

    (10 results)

All 2024 2023 2022 2021

All Journal Article (5 results) (of which Int'l Joint Research: 1 results,  Peer Reviewed: 5 results,  Open Access: 2 results) Presentation (5 results) (of which Int'l Joint Research: 4 results)

  • [Journal Article] Evaluation of hydrogen embrittlement in ODS-Cu, Cu-Cr-Zr, and Cu-Cr alloys using slow strain rate technique test2024

    • Author(s)
      Hatakeyama M.、Asai Y.、Nakato D.、Nishimura M.、Hatano Y.、Sunada S.、Sato K.
    • Journal Title

      Nuclear Materials and Energy

      Volume: 38 Pages: 101580-101580

    • DOI

      10.1016/j.nme.2024.101580

    • Related Report
      2023 Annual Research Report
    • Peer Reviewed / Open Access
  • [Journal Article] Mechanical properties of the W coating and interface of vacuum-plasma-sprayed W-ferritic steel joints under shear and bending loads2023

    • Author(s)
      Xiangyu Wu, Sosuke Kondo, Hao Yu, Takuya Nagasaka, Ryuta Kasada
    • Journal Title

      Surface and Coatings Technology

      Volume: 462 Pages: 129468-129468

    • DOI

      10.1016/j.surfcoat.2023.129468

    • Related Report
      2023 Annual Research Report
    • Peer Reviewed
  • [Journal Article] Effect of uniaxial tensile strain on binding energy of hydrogen atoms to vacancy-carbon-hydrogen complexes in α-iron2022

    • Author(s)
      Shintaro Hirayama, Koichi Sato, Daiji Kato, Hirotomo Iwakiri, Masatake Yamaguchi, Yoshiyuki Watanabe, Takashi Nozawa
    • Journal Title

      Nuclear Materials and Energy

      Volume: 31 Pages: 101179-101179

    • DOI

      10.1016/j.nme.2022.101179

    • Related Report
      2022 Annual Research Report
    • Peer Reviewed / Open Access
  • [Journal Article] Change in nanoindentation hardness of polycrystalline tungsten irradiated with Fe ions or electrons by hydrogen gas charging2022

    • Author(s)
      Koichi Sato, Ryuta Kasada, Atsushi Kiyohara, Masashi Hirabaru, Kenichi Nakano, Kiyohiro Yabuuchi, Masahiko Hatakeyama, Qiu Xu
    • Journal Title

      Journal of Nuclear Materials

      Volume: 560 Pages: 153483-153483

    • DOI

      10.1016/j.jnucmat.2021.153483

    • Related Report
      2021 Annual Research Report
    • Peer Reviewed
  • [Journal Article] Effects of Mo/Zr addition on deuterium retention in W-Y2O3 alloys2021

    • Author(s)
      Q. Xu, K. Murotani, L.M. Luo, K. Sato, H. Tsuchida
    • Journal Title

      Journal of Nuclear Materials

      Volume: 555 Pages: 153141-153141

    • DOI

      10.1016/j.jnucmat.2021.153141

    • Related Report
      2021 Annual Research Report
    • Peer Reviewed / Int'l Joint Research
  • [Presentation] Effect of hydrogen on mechanical properties in single-crystal tungsten irradiated with Fe ions at high temperatures2023

    • Author(s)
      K. Sato, K. Ueno, D.C. Geng, R. Kasada, M. Ando, K. Yabuuchi, Q. Xu, M. Hatakeyama, Y. Watanabe, T. Nozawa
    • Organizer
      21th International Conference on Fusion Reactor Materials (ICFRM-21)
    • Related Report
      2023 Annual Research Report
    • Int'l Joint Research
  • [Presentation] Binding energy of hydrogen atoms to vacancy-carbon-hydrogen complexes in α-iron under uniaxial compressive and hydrostatic strain2023

    • Author(s)
      T. Taniguchi, K. Sato, D. Kato, H. Iwakiri, Y. Watanabe, T. Nozawa
    • Organizer
      21th International Conference on Fusion Reactor Materials (ICFRM-21)
    • Related Report
      2023 Annual Research Report
    • Int'l Joint Research
  • [Presentation] Feイオンを照射した単結晶タングステンの水素添加による硬さの変化2023

    • Author(s)
      上野健太郎、佐藤紘一、D.C. Geng、笠田竜太、藪内聖皓、Q. Xu、畠山賢彦
    • Organizer
      日本金属学会 2023年春期大会
    • Related Report
      2022 Annual Research Report
  • [Presentation] Effect of elastic strain on the stability of vacancy-carbon-hydrogen complexes in α-iron2021

    • Author(s)
      S. Hirayama, K. Sato, D. Kato, Y. Watanabe, T. Nozawa
    • Organizer
      20th International Conference on Fusion Reactor Materials (ICFRM-20)
    • Related Report
      2021 Annual Research Report
    • Int'l Joint Research
  • [Presentation] Effect of Carbon on Quantitative Evaluation of Hydrogen Atoms Trapped at Vacancy-type Defects Using Positron Annihilation Spectroscopy in Tungsten2021

    • Author(s)
      K. Sato, M. Hirabaru, M. Onoue, M. Hatakeyama, Q. Xu, Y. Watanabe, T. Nozawa
    • Organizer
      20th International Conference on Fusion Reactor Materials (ICFRM-20)
    • Related Report
      2021 Annual Research Report
    • Int'l Joint Research

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Published: 2021-04-28   Modified: 2025-01-30  

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