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Clarification of Damage Process by Fusion Plasma in High Toughness Tungsten Alloys

Research Project

Project/Area Number 20K03900
Research Category

Grant-in-Aid for Scientific Research (C)

Allocation TypeMulti-year Fund
Section一般
Review Section Basic Section 14020:Nuclear fusion-related
Research InstitutionKyoto University

Principal Investigator

XU QIU  京都大学, 複合原子力科学研究所, 准教授 (90273531)

Co-Investigator(Kenkyū-buntansha) 宮本 光貴  島根大学, 学術研究院理工学系, 准教授 (80379693)
時谷 政行  核融合科学研究所, ヘリカル研究部, 准教授 (30455208)
Project Period (FY) 2020-04-01 – 2023-03-31
Project Status Completed (Fiscal Year 2022)
Budget Amount *help
¥4,420,000 (Direct Cost: ¥3,400,000、Indirect Cost: ¥1,020,000)
Fiscal Year 2022: ¥910,000 (Direct Cost: ¥700,000、Indirect Cost: ¥210,000)
Fiscal Year 2021: ¥910,000 (Direct Cost: ¥700,000、Indirect Cost: ¥210,000)
Fiscal Year 2020: ¥2,600,000 (Direct Cost: ¥2,000,000、Indirect Cost: ¥600,000)
Keywordsタングステン合金 / プラズマ / ヘリウム / 重水素 / 照射欠陥 / Y / Zr / 核融合炉 / 対向材 / 損傷
Outline of Research at the Start

タングステンは融点が高い、スパッタ率が低い、水素蓄積が少ない利点があるため、プラ ズマ対向材として注目されている。一方、低温脆化、再結晶脆化及び照射脆化がタングステ ン合金使用の問題点となっている。これらの脆化に関する問題を解決するために、われわれ は液相ドーピング法を用いて、400℃以上の温度で10%以上の伸びを有するタングステン合 金の開発を成功した。本研究では、この合金における核融合プラズマの水素、ヘリウム粒子 の照射によりタングステン合金の照射特性を調べ、このタングステン合金における核融合プ ラズマによる損傷の素過程を解明する。

Outline of Final Research Achievements

W has a high melting point, low sputtering rate, and low H accumulation and is a promising plasma-facing material for fusion reactors. However, low-temperature embrittlement, recrystallization embrittlement, and irradiation embrittlement are known issues when using W. To solve such problems, we developed alloys of W with Y2O3 nanoparticles and further adding Mo or Zr. In this study, plasma irradiation resistance of these four materials containing W was investigated. Compared to pure W, W-Y2O3 and W-Zr-Y2O3 were about two times and five times better in resistance to He plasma irradiation, respectively. On the other hand, W-Mo-Y2O3 was almost the same as W. This is thought to be related to the density and size of the He-trapping Y2O3 nanoparticles in each alloy.

Academic Significance and Societal Importance of the Research Achievements

化石エネルギーを代わる最も有望な代替エネルギー源として核融合炉のプラズマ対向材は高温、高フラックス粒子及び高エネルギー中性子に曝される。Wは融点が高い、スパッタ率が低いため、プラズマ対向材として注目されている。一方、脆化がW使用の問題点となっている。本研究では、Wの脆化問題を解決するため、Y2O3ナノ粒子とそれに更にMoまたはZrを添加した合金を開発した。本研究結果がW合金の耐プラズマ照射性を向上するには、プラズマ原子の溶解度及びそれをトラップするサイドを増やすことを示した。また、純Wより5倍以上良い耐Heプラズマ照射性を持つW-Zr-Y2O3開発の成功が核融合炉の研究を推進した。

Report

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

    (26 results)

All 2023 2022 2021 2020 Other

All Int'l Joint Research (3 results) Journal Article (16 results) (of which Int'l Joint Research: 15 results,  Peer Reviewed: 16 results) Presentation (7 results)

  • [Int'l Joint Research] 合肥工業大学/浙江工業大学/貴州大学(中国)

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

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

    • Related Report
      2020 Research-status Report
  • [Journal Article] Microstructure Evolution and Effect on Deuterium Retention in TiC- and ZrC-Doped Tungsten under He+ Ion Irradiation2023

    • Author(s)
      Ding Xiaoyu、Fang Jiahui、Xu Qiu、Zhang Panpan、Zhang Haojie、Luo Laima、Wu Yucheng、Yao Jianhua
    • Journal Title

      Metals

      Volume: 13 Issue: 4 Pages: 783-783

    • DOI

      10.3390/met13040783

    • Related Report
      2022 Annual Research Report
    • Peer Reviewed / Int'l Joint Research
  • [Journal Article] Hydrogen retention and affecting factors in rolled tungsten: Thermal desorption spectra and molecular dynamics simulations2023

    • Author(s)
      Chen Hongyu、Wang Lin、Peng Feng、Xu Qiu、Xiong Yaoxu、Zhao Shijun、Tokunaga Kazutoshi、Wu Zhenggang、Ma Yi、Chen Pengqi、Luo Laima、Wu Yucheng
    • Journal Title

      International Journal of Hydrogen Energy

      Volume: ー Issue: 78 Pages: 30522-30531

    • DOI

      10.1016/j.ijhydene.2023.03.151

    • Related Report
      2022 Annual Research Report
    • Peer Reviewed / Int'l Joint Research
  • [Journal Article] Effects of Zr/Mo addition on He bubble formation in Y2O3-added W alloys2022

    • Author(s)
      Xu Qiu、Miyamoto M.、Luo Lai-Ma
    • Journal Title

      Tungsten

      Volume: - Issue: 3 Pages: 203-211

    • DOI

      10.1007/s42864-021-00131-4

    • Related Report
      2022 Annual Research Report
    • Peer Reviewed / Int'l Joint Research
  • [Journal Article] The superior thermal stability and irradiation resistance capacities of tungsten composites synthesized by simple second-phase particle component modulation2022

    • Author(s)
      Yao Gang、Chen HongYu、Zhao Zhi-Hao、Luo Lai-Ma、Ma Yong、Cheng Ji-Gui、Zan Xiang、Xu Qiu、Wu Yu-Cheng
    • Journal Title

      Journal of Nuclear Materials

      Volume: 561 Pages: 153522-153522

    • DOI

      10.1016/j.jnucmat.2022.153522

    • Related Report
      2021 Research-status Report
    • Peer Reviewed / Int'l Joint Research
  • [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 Research-status Report
    • Peer Reviewed
  • [Journal Article] Evaluating surface damage behavior of W-(Y0.9La0.1)2O3 composites during spark plasma sintering process improvement2022

    • Author(s)
      Yao Gang、Liu Xue-Peng、Zhao Zhi-Yuan、Zhao Zhi-Hao、Luo Lai-Ma、Cheng Ji-Gui、Zan Xiang、Xu Qiu、Wu Yu-Cheng
    • Journal Title

      Journal of Nuclear Materials

      Volume: 558 Pages: 153322-153322

    • DOI

      10.1016/j.jnucmat.2021.153322

    • Related Report
      2021 Research-status Report
    • Peer Reviewed / Int'l Joint Research
  • [Journal Article] Excellent performance of W?Y2O3 composite via powder process improvement and Y2O3 refinement2021

    • Author(s)
      Yao Gang、Liu Xuepeng、Zhao Zhihao、Luo Laima、Cheng Jigui、Zan Xiang、Wang Zumin、Xu Qiu、Wu Yucheng
    • Journal Title

      Materials & Design

      Volume: 212 Pages: 110249-110249

    • DOI

      10.1016/j.matdes.2021.110249

    • Related Report
      2021 Research-status Report
    • Peer Reviewed / Int'l Joint Research
  • [Journal Article] Damage evolutions of completely recrystallized W?Y2O3 composite evaluated using the dual effects of electron beam thermal shock and helium ion irradiation2021

    • Author(s)
      Yao Gang、Zhao Zhi-Hao、Luo Lai-Ma、Cheng Ji-Gui、Zan Xiang、Xu Qiu、Wu Yu-Cheng
    • Journal Title

      Materials Chemistry and Physics

      Volume: 271 Pages: 124947-124947

    • DOI

      10.1016/j.matchemphys.2021.124947

    • Related Report
      2021 Research-status Report
    • Peer Reviewed / Int'l Joint Research
  • [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 Research-status Report
    • Peer Reviewed / Int'l Joint Research
  • [Journal Article] Anisotropy and stability of the mechanical properties of the W alloy plate reinforced with Y-Zr-O particles and prepared by a wet chemical method2021

    • Author(s)
      Zhao Zhi-Hao、Yao Gang、Luo Lai-Ma、Zan Xiang、Xu Qiu、Wu Yu-Cheng
    • Journal Title

      International Journal of Refractory Metals and Hard Materials

      Volume: 99 Pages: 105597-105597

    • DOI

      10.1016/j.ijrmhm.2021.105597

    • Related Report
      2021 Research-status Report
    • Peer Reviewed / Int'l Joint Research
  • [Journal Article] Tensile fracture behavior and texture evolution of a hot-rolled W?Y2(Zr)O3 alloy2021

    • Author(s)
      Zhao ZhiHao、Yao Gang、Luo Lai?Ma、Zan Xiang、Xu Qiu、Wu YuCheng
    • Journal Title

      Journal of Nuclear Materials

      Volume: 554 Pages: 153080-153080

    • DOI

      10.1016/j.jnucmat.2021.153080

    • Related Report
      2021 Research-status Report
    • Peer Reviewed / Int'l Joint Research
  • [Journal Article] Design and properties of FeAl/Al2O3/TiO2 composite tritium-resistant coating prepared through pack cementation and sol?gel method2021

    • Author(s)
      Zhu Liu、Zheng Liang、Xie Hao、Liu Dong-Guang、Xu Qiu、Luo Lai-Ma、Wu Yu-Cheng
    • Journal Title

      Materials Today Communications

      Volume: 26 Pages: 101848-101848

    • DOI

      10.1016/j.mtcomm.2020.101848

    • Related Report
      2021 Research-status Report
    • Peer Reviewed / Int'l Joint Research
  • [Journal Article] Plasma-surface interaction experimental device: PSIEC and its first plasma exposure experiments on bulk tungsten and coatings2021

    • Author(s)
      Xu Yue、Xu Yunfeng、Wu Zuosheng、Luo Laima、Zan Xiang、Yao Gang、Xi Ya、Wang Yafeng、Ding Xiaoyu、Bi Hailin、Zhu Xiaoyong、Xu Qiu、Wu Jiefeng、Wu Yucheng
    • Journal Title

      Fusion Engineering and Design

      Volume: 164 Pages: 112198-112198

    • DOI

      10.1016/j.fusengdes.2020.112198

    • Related Report
      2020 Research-status Report
    • Peer Reviewed / Int'l Joint Research
  • [Journal Article] The influence of different isochronal annealing temperature on helium ion irradiation damage of W-Nb composites2020

    • Author(s)
      Chen Hong-Yu、Zhou Yu-Fen、Xu Meng-Yao、Luo Lai-Ma、Xu Qiu、Zhu Xiao-Yong、Wu Yu-Cheng
    • Journal Title

      Fusion Engineering and Design

      Volume: 159 Pages: 111857-111857

    • DOI

      10.1016/j.fusengdes.2020.111857

    • Related Report
      2020 Research-status Report
    • Peer Reviewed / Int'l Joint Research
  • [Journal Article] D2 retention behavior and microstructural evolution of W-2wt.%Y2O3 alloy during He-ion irradiation at high temperatures2020

    • Author(s)
      Xu Q.、Luo L.M.、Chen Z.、Hirakawa M.、Miyamoto M.、Chen H.Y.、Sato K.、Tsuchida H.
    • Journal Title

      Journal of Nuclear Materials

      Volume: 539 Pages: 152273-152273

    • DOI

      10.1016/j.jnucmat.2020.152273

    • Related Report
      2020 Research-status Report
    • Peer Reviewed / Int'l Joint Research
  • [Journal Article] Microstructure evolution and effect on deuterium retention in oxide dispersion strengthened tungsten during He+ irradiation2020

    • Author(s)
      Ding Xiao-Yu、Xu Qiu、Zhu Xiao-yong、Luo Lai-Ma、Huang Jian-Jun、Yu Bin、Gao Xiang、Li Jian-Gang、Wu Yu-Cheng
    • Journal Title

      Nuclear Engineering and Technology

      Volume: 52 Issue: 12 Pages: 2860-2866

    • DOI

      10.1016/j.net.2020.05.022

    • Related Report
      2020 Research-status Report
    • Peer Reviewed / Int'l Joint Research
  • [Presentation] W-Y2O3合金の耐プラズマ照射性に及ぼすMoまたはZrの添加効果2023

    • Author(s)
      徐ぎゅう、宮本光貴、時谷政行、佐藤紘一
    • Organizer
      原子力学会春大会
    • Related Report
      2022 Annual Research Report
  • [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、Geng Dingcheng、笠田 竜太、藪内 聖皓、Xu Qiu、畠山 賢彦
    • Organizer
      金属学会春大会
    • Related Report
      2022 Annual Research Report
  • [Presentation] BCC金属中の空孔クラスターの安定構造2022

    • Author(s)
      大沢一人、徐ぎゅう
    • Organizer
      金属学会2022年春季大会
    • Related Report
      2021 Research-status Report
  • [Presentation] タングステンにおける注入He深さプロファイル分析と引張応力負荷の影響2021

    • Author(s)
      徳永和俊、松尾悟、栗下裕明、永田普二、土屋文、徐ぎゅう、時谷政行、永田大介、長谷川真、中村一男
    • Organizer
      イオンビームによる表面・界面の解析と改質
    • Related Report
      2021 Research-status Report
  • [Presentation] Mo添加によるW-Y2O3における重水素蓄積への影響2021

    • Author(s)
      室谷賢二、土田秀次、徐 ぎゅう
    • Organizer
      第55回KUR学術講演会
    • Related Report
      2020 Research-status Report
  • [Presentation] Mo添加によるW-Y2O3タングステン合金における重水素蓄積挙動への影響2021

    • Author(s)
      室谷賢二
    • Organizer
      日本鉄鋼協会・日本金属学会関西支部材料物性工学談話会2020年度第2回講演会
    • Related Report
      2020 Research-status Report
  • [Presentation] W-Y2O3合金の重水素蓄積挙動に及ぼすMoの影響2020

    • Author(s)
      室谷賢二、土田秀次、徐 ぎゅう
    • Organizer
      QSEC公開シンポジウム
    • Related Report
      2020 Research-status Report

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

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