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Plasma driven permeation for plasma facing materials and its hydrogen isotope effect

Research Project

Project/Area Number 20H01885
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 InstitutionShizuoka University

Principal Investigator

OYA YASUHISA  静岡大学, 理学部, 准教授 (80334291)

Co-Investigator(Kenkyū-buntansha) 芦川 直子  核融合科学研究所, ヘリカル研究部, 准教授 (00353441)
染谷 洋二  国立研究開発法人量子科学技術研究開発機構, 六ヶ所研究所 核融合炉システム研究開発部, 主幹研究員 (20589345)
波多野 雄治  富山大学, 学術研究部理学系, 教授 (80218487)
Project Period (FY) 2020-04-01 – 2023-03-31
Project Status Completed (Fiscal Year 2022)
Budget Amount *help
¥17,420,000 (Direct Cost: ¥13,400,000、Indirect Cost: ¥4,020,000)
Fiscal Year 2022: ¥4,160,000 (Direct Cost: ¥3,200,000、Indirect Cost: ¥960,000)
Fiscal Year 2021: ¥6,110,000 (Direct Cost: ¥4,700,000、Indirect Cost: ¥1,410,000)
Fiscal Year 2020: ¥7,150,000 (Direct Cost: ¥5,500,000、Indirect Cost: ¥1,650,000)
Keywordsプラズマ駆動透過 / 同位体効果 / 水素同位体移行 / プラズマ対向壁 / プラズマ対向材
Outline of Research at the Start

核融合炉プラズマ対向材料タングステンから真空容器を跨ぐ核融合炉システムにおいて、燃料となるトリチウムを含む水素同位体(H,D,T)の移行挙動に関連する物理定数(透過係数、溶解度等)を、水素同位体の存在比を考慮して明らかにするとともに、その水素同位体効果を解明する。
原型炉プラズマ対向材へはプラズマ側からTとDが入射するとともに冷却水から流入するHの移行も想定されるため、双方向の水素同位体移行挙動やその物理定数について水素同位体を考慮して明らかにする。これらを活用し、精度の高い水素同位体移行シミュレーションを構築し、種々の環境での水素同位体移行評価を行う。

Outline of Final Research Achievements

Hydrogen isotope plasma driven permeation was evaluated under the consideration of hydrogen isotope. It was found that large hydrogen isotope effect was observed at lower temperature less than 800 K, where the permeation flux of H:D was 2:1. At higher temperature above 900 K, the permeation flux was almost unity. But, the permeation flux of H:D for neutron damaged tungsten was limited to be 3:2. This fact indicates that the irradiation defects may influence on hydrogen isotope permeation behavior. For He mixed plasma exposure to undamaged tungsten, no large hydrogen isotope effect was observed at all the temperature region.

Academic Significance and Societal Importance of the Research Achievements

核融合炉プラズマ対向壁での水素同位体透過に及ぼす水素同位体効果について明らかにしてきた。低温では水素透過に大きな同位体効果があることが明らかになり、実際の核融合炉でDTプラズマ燃焼の際には壁温度や照射損傷により水素同位体ごとの透過フラックスが変化することから、核融合炉燃料透過制御シミュレーションに必要な知見を得ることができた。

Report

(4 results)
  • 2022 Annual Research Report   Final Research Report ( PDF )
  • 2021 Annual Research Report
  • 2020 Annual Research Report
  • Research Products

    (23 results)

All 2023 2022 2021 2020 Other

All Int'l Joint Research (5 results) Journal Article (5 results) (of which Int'l Joint Research: 3 results,  Peer Reviewed: 5 results) Presentation (12 results) (of which Int'l Joint Research: 9 results,  Invited: 1 results) Remarks (1 results)

  • [Int'l Joint Research] アイダホ国立研究所/サンディア国立研究所(米国)

    • Related Report
      2022 Annual Research Report
  • [Int'l Joint Research] 合肥工業大学(中国)

    • Related Report
      2022 Annual Research Report
  • [Int'l Joint Research] アイダホ国立研究所/サンディア国立研究所/オークリッジ国立研究所(米国)

    • Related Report
      2021 Annual Research Report
  • [Int'l Joint Research] 合肥工業大学(中国)

    • Related Report
      2021 Annual Research Report
  • [Int'l Joint Research] Idaho National Laboratory/Sandia National Laboratories/Oak Ridge National Laboratory(米国)

    • Related Report
      2020 Annual Research Report
  • [Journal Article] Effect of He seeding on hydrogen isotope permeation in tungsten by H-D mixed plasma exposure2023

    • Author(s)
      Yasuhisa Oyaa, Kyosuke Ashizawa, Fei Sun, Shiori Hirata, Naoko Ashikawa, Yoji Someya, Yuji Hatano, Robert Kolasinski, Chase N. Taylor, Masashi Shimada
    • Journal Title

      Fusion Engineering and Design

      Volume: 194 Pages: 113722-113722

    • DOI

      10.1016/j.fusengdes.2023.113722

    • Related Report
      2022 Annual Research Report
    • Peer Reviewed / Int'l Joint Research
  • [Journal Article] 核融合プラズマ対向材の残留トリチウム測定法2023

    • Author(s)
      菊地絃太、芦川直子、鳥養祐二
    • Journal Title

      プラズマ・核融合学会誌

      Volume: 99(6)

    • Related Report
      2022 Annual Research Report
    • Peer Reviewed
  • [Journal Article] Deuterium recombination coefficient on tungsten surface determined by plasma driven permeation2020

    • Author(s)
      Mingzhong Zhao, Shota Yamazaki, Takuro Wada, Ayaka Koike, Fei Sun, Naoko Ashikawa, Yoji Someya, Tetsu Mieno, Yasuhisa Oya
    • Journal Title

      Fusion Engineering and Design

      Volume: 160 Issue: 3 Pages: 111853-111853

    • DOI

      10.1080/15361055.2019.1705727

    • Related Report
      2020 Annual Research Report
    • Peer Reviewed
  • [Journal Article] D retention and depth profile behavior for single crystal tungsten with high temperature neutron irradiation2020

    • Author(s)
      Y. Oya, F. Sun, Y. Yamauchi, Y. Nobuta, M. Shimada, C.N. Taylor, W.R. Wampler, M. Nakata, L.M. Garrison, and Y. Hatano
    • Journal Title

      Journal of Nuclear Materials

      Volume: 539 Pages: 152323-152323

    • DOI

      10.1016/j.jnucmat.2020.152323

    • Related Report
      2020 Annual Research Report
    • Peer Reviewed / Int'l Joint Research
  • [Journal Article] Modeling and simulation for surface helium effect on hydrogen isotopes diffusion and trapping/detrapping behavior in plasma facing materials2020

    • Author(s)
      F. Sun, X.C. Li, L. Zhang, M. Nakata, M. Zhao, T. Wada, S. Yamazaki, A. Koike, Y. Oya
    • Journal Title

      Journal of Nuclear Materials

      Volume: 537 Pages: 152227-152227

    • DOI

      10.1016/j.jnucmat.2020.152227

    • Related Report
      2020 Annual Research Report
    • Peer Reviewed / Int'l Joint Research
  • [Presentation] Temperature dependence on D retention for damaged W-10%Re alloy2022

    • Author(s)
      Yasuhisa Oya, Nao Inozume, Shiori Hirata, Naoaki Yoshida, Tatsuya Hinoki, Kiyohiro Yabuuchi
    • Organizer
      16th International Workshop on Hydrogen Isotopes in Fusion Reactor materials
    • Related Report
      2022 Annual Research Report
    • Int'l Joint Research
  • [Presentation] Thermal annealing effect on D retention for damaged W-10%Re alloy2022

    • Author(s)
      Yasuhisa Oyaa, Nao Inozume, Shiori Hirata, Naoaki Yoshida, Tatsuya Hinoki, Kiyohiro Yabuuchi
    • Organizer
      Nuclear Material Conference 2022
    • Related Report
      2022 Annual Research Report
    • Int'l Joint Research
  • [Presentation] Hydrogen isotope effect on plasma driven permeation for neutron damaged W2022

    • Author(s)
      Yasuhisa Oya, Kyosuke Ashizawa, Shiori Hirata, Fei Sun, Naoko Ashikawa, Masashi Shimada, Chase N. Taylor, Robert Kolasinski, Lauren Garrison, Yuji Hatano, Yoji Someya
    • Organizer
      13th International Conference on Tritium Science and Technology
    • Related Report
      2022 Annual Research Report
    • Int'l Joint Research
  • [Presentation] プラズマ駆動水素同位体透過に及ぼすタングステン中の照射損傷影響2022

    • Author(s)
      大矢 恭久,芦沢 京祐,平田 詩織,三福寺 旭 ,齋藤永 ,星野柚香 ,芦川 直子,染谷 洋二,波多野 雄治,島田 雅,Chase N. Taylor, Robert Kolasinski, 外山健
    • Organizer
      第14回核融合エネルギー連合講演会
    • Related Report
      2022 Annual Research Report
  • [Presentation] タングステン中における水素同位体輸送に及ぼすヘリウムの役割2022

    • Author(s)
      大矢恭久、孫飛、平田詩織、芦川直子、檜木達也、 波多野雄治
    • Organizer
      日本放射化学会第66回討論会
    • Related Report
      2022 Annual Research Report
  • [Presentation] 中性子照射タングステンを用いた水素同位体混合プラズマ照射におけるプラズマ駆動透過2022

    • Author(s)
      大矢 恭久,芦沢 京祐,平田 詩織,芦川 直子,染谷 洋二,波多野 雄治, 島田 雅,Chase N. Taylor, Robert Kolasinski
    • Organizer
      日本原子力学会 2022年春の年会
    • Related Report
      2022 Annual Research Report
  • [Presentation] Effect of irradiation damages and He existence on hydrogen isotope plasma driven permeation for W2021

    • Author(s)
      Yasuhisa Oya
    • Organizer
      AAPPS-DPP2021
    • Related Report
      2021 Annual Research Report
    • Int'l Joint Research / Invited
  • [Presentation] Permeation characteristics of hydrogen isotope in tungsten under H-D mixed plasma irradiation2021

    • Author(s)
      Kyosuke Ashizawa
    • Organizer
      ICFRM-20
    • Related Report
      2021 Annual Research Report
    • Int'l Joint Research
  • [Presentation] HYDROGEN ISOTOPE RETENTION AND PERMEATION BEHAVIOR FOR DAMAGED TUNGSTEN UNDER H/D MIXED PLASMA EXPOSURE AND THEIR HE EFFECT2021

    • Author(s)
      Yasuhisa Oya
    • Organizer
      ICFRM-20
    • Related Report
      2021 Annual Research Report
    • Int'l Joint Research
  • [Presentation] Deuterium gas driven permeation behaviour for W-10%Re alloy2021

    • Author(s)
      Yuki Koyama
    • Organizer
      PFMC-18
    • Related Report
      2021 Annual Research Report
    • Int'l Joint Research
  • [Presentation] Effect of deuterium-helium mixed plasma exposure on hydrogen isotopes retention in damaged tungsten2020

    • Author(s)
      Yasuhisa Oya
    • Organizer
      Nuclear Materials Conference 2020
    • Related Report
      2020 Annual Research Report
    • Int'l Joint Research
  • [Presentation] Influence of He and/or irradiation defects on the plasma driven permeation behavior in tungsten material2020

    • Author(s)
      Yasuhisa Oya
    • Organizer
      3rd Asia-Pacific Symposium on Tritium Science
    • Related Report
      2020 Annual Research Report
    • Int'l Joint Research
  • [Remarks] 大矢研究室

    • URL

      http://fusion.sci.shizuoka.ac.jp

    • Related Report
      2020 Annual Research Report

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Published: 2020-04-28   Modified: 2024-01-30  

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