Hydrogen retention in radiation-damaged tungsten and development of retention reduction method
| Project/Area Number |
26289352
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| Research Category |
Grant-in-Aid for Scientific Research (B)
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| Allocation Type | Partial Multi-year Fund |
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| Section | 一般 |
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| Research Field |
Nuclear fusion studies
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| Research Institution | University of Tsukuba |
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Principal Investigator |
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| Co-Investigator(Kenkyū-buntansha) |
渡辺 英雄 九州大学, 応用力学研究所, 准教授 (90212323)
時谷 政行 核融合科学研究所, ヘリカル研究部, 助教 (30455208)
芦川 直子 核融合科学研究所, ヘリカル研究部, 助教 (00353441)
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| Project Period (FY) |
2014-04-01 – 2019-03-31
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| Project Status |
Completed (Fiscal Year 2018)
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| Budget Amount *help |
¥15,340,000 (Direct Cost: ¥11,800,000、Indirect Cost: ¥3,540,000)
Fiscal Year 2017: ¥2,470,000 (Direct Cost: ¥1,900,000、Indirect Cost: ¥570,000)
Fiscal Year 2016: ¥2,470,000 (Direct Cost: ¥1,900,000、Indirect Cost: ¥570,000)
Fiscal Year 2015: ¥7,540,000 (Direct Cost: ¥5,800,000、Indirect Cost: ¥1,740,000)
Fiscal Year 2014: ¥2,860,000 (Direct Cost: ¥2,200,000、Indirect Cost: ¥660,000)
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| Keywords | プラズマ・核融合 / 水素吸蔵 / 照射損傷 / タングステン / 表面改質 |
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| Outline of Final Research Achievements |
Deuterium (D) retention in tungsten (W) irradiated with 2.4 MeV Cu2+ ions under various conditions has been investigated. A new desorption peak appeared at ~830 K in thermal desorption spectra due to the heavy ion irradiation, which is attributed to nano-voids and vacancy clusters. The D retention in W irradiated with 2.4 MeV Cu2+ ions increased with the damage dose up to 0.4 dpa and then saturated in the case of high dose rate. On the other hand, the D retention increased with the damage dose in the case of low dose rate. The D retention in the irradiated W significantly reduced by simultaneous annealing with irradiation. Deuterium retention in W deposited with Cr and W has been investigated.
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| Academic Significance and Societal Importance of the Research Achievements |
核融合炉実現のための重要な課題のひとつにプラズマ対向壁へのトリチウム吸蔵の問題がある。原型炉のプラズマ対向壁の材料として、タングステンは低水素吸蔵の特性を有するが中性子照射によりタングステン全体に水素捕捉サイトが形成されることになる。このことにより、トリチウム吸蔵量は大幅に増加してしまう。タングステンの水素吸蔵に関する中性子照射効果のデータベースは極めて少ない。そこで、高エネルギーイオン照射による実験により照射欠陥と重水素吸蔵特性の関係を明らかにすることは、中性子照射効果のデータベースを補完する観点から意義がある。また、積極的に表面改質を活用して水素吸蔵量を低減する手法の開発も必要である。
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Report
(6 results)
Research Products
(41 results)
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[Presentation] Hydrogen Isotope Retention in Tungsten Surface-modified by Heavy Ion Irradiation, Helium bubbles and Tungsten Deposition2016
Author(s)
M. Sakamoto, H. Tanaka, H. Watanabe, N. Yoshida, M. Tokitani, S. Ino, A. Terakado, N. Ezumi and Y. Nakashima
Organizer
26th IAEA Fusion Energy Conference
Place of Presentation
Kyoto International Conference Center, Kyoto, Japan
Year and Date
2016-10-17
Related Report
Int'l Joint Research
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[Presentation] Deuterium retention in heavy-ion-irradiated tungsten exposed to low energy and high flux plasma2016
Author(s)
H. Tanaka, M. Sakamoto, H. Watanabe, M. Tokitani, N. Ashikawa, S. Ino, A. Terakado, N. Ezumi, Y. Nakashima
Organizer
The 13th China-Japan Symposium on Materials for Advanced Energy Systems and Fission and Fusion Engineering
Place of Presentation
Institute of Nuclear Energy Safety Technology, Hefei, China
Year and Date
2016-09-26
Related Report
Int'l Joint Research
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[Presentation] Hydrogen isotope retention in W irradiated by heavy ions and helium plasma2015
Author(s)
M. Sakamoto, H. Tanaka, S. Ino, H. Watanabe, M. Tokitani, R. Ohyama, A. Rusinov and N. Yoshida
Organizer
2nd Research Coordinated Meeting of CRP on Plasma-Wall Interaction with Irradiated Tungsten and Tungsten Alloys in Fusion Devices
Place of Presentation
Seoul National University, Seoul, Republic of Korea
Year and Date
2015-09-08
Related Report
Int'l Joint Research
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