Dependence of Plasma irradiation energy on hydrogen isotope retention and release characteristics in damaged materials
| Project/Area Number |
15K18309
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| Research Category |
Grant-in-Aid for Young Scientists (B)
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| Allocation Type | Multi-year Fund |
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| Research Field |
Nuclear fusion studies
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| Research Institution | National Institute for Fusion Science |
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Principal Investigator |
Yajima Miyuki 核融合科学研究所, ヘリカル研究部, 助教 (70749085)
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| Project Period (FY) |
2015-04-01 – 2019-03-31
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| Project Status |
Completed (Fiscal Year 2018)
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| Budget Amount *help |
¥4,160,000 (Direct Cost: ¥3,200,000、Indirect Cost: ¥960,000)
Fiscal Year 2017: ¥650,000 (Direct Cost: ¥500,000、Indirect Cost: ¥150,000)
Fiscal Year 2016: ¥1,040,000 (Direct Cost: ¥800,000、Indirect Cost: ¥240,000)
Fiscal Year 2015: ¥2,470,000 (Direct Cost: ¥1,900,000、Indirect Cost: ¥570,000)
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| Keywords | タングステン / 重水素プラズマ / 水素同位体 / 照射損傷 / 中性子照射 / 昇温脱離ガス分析 / プラズマ・核融合 / 核融合 / プラズマ壁相互作用 / 拡散 / 重イオン照射 |
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| Outline of Final Research Achievements |
The objective of this study is to investigate the effects of neutron (n) irradiation on hydrogen isotope transport in tungsten (W). W samples were irradiated with neutrons in a fission reactor and then exposed to high flux deuterium (D) plasma at 563 K and 773 K in a linear plasma device. The fraction of D released in a high temperature region increased with increasing exposure time. In addition, the D retention in n-irradiated W increased in proportion to the square root of the plasma exposure time. These observations were explained by increase in the penetration depth of D with filling up displacement damages acting as strong trapping sites.
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| Academic Significance and Societal Importance of the Research Achievements |
核融合炉の実現において、中性子照射がタングステンの水素吸蔵特性に与える影響に関する系統的な実験研究は急務な課題の一つである。そのような背景の中、本研究により損傷材料中の水素同位体拡散モデルを実験的に明らかにしたことは非常に大きな成果である。また、中性子照射試料に対する重水素プラズマ曝露実験は国内初の試みであり、酸化膜の影響（試料の前処理として電解研磨を実施）やプラズマ曝露後大気開放の影響を排除することで、より核融合炉内環境に近い条件で実験を実施したという点では世界初の成果である。得られた知見は、将来の原型炉の設計および炉内トリチウム管理において、大きな貢献となると期待される。
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Report
(5 results)
Research Products
(9 results)
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[Journal Article] Development of a Compact Divertor Plasma Simulator for Plasma-Wall Interaction Studies on Neutron-Irradiated Materials2017
Author(s)
Noriyasu OHNO, Tatsuya KUWABARA, Makoto TAKAGI, Ryo NISHIMURA, Miyuki YAJIMA, Akio SAGARA, Takeshi TOYAMA, Katuya SUZUKI, Hiroaki KURISHITA, Tatsuo SHIKAMA, Yuji HATANO, Naoaki YOSHIDA
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Journal Title
Plasma and Fusion Research
Volume: 12
Issue: 0
Pages: 1405040-1405040
DOI
NAID
ISSN
1880-6821
Related Report
Peer Reviewed / Open Access
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[Presentation] Deuterium retention in neutron irradiated tungsten-rhenium alloy and potassium-doped tungsten2018
Author(s)
M. Oya, H.T. Lee, T. Yamane, A. Nakamura, H. Ito, T. Kuwabara, M. Yajima, T. Toyama, K. Suzuki, M. Takagi, N. Ohno, Y. Ueda, Y. Hatano
Organizer
The 23rd International Conference on Plasma Surface Interactions in Controlled Fusion Devices
Related Report
Int'l Joint Research
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[Presentation] 中性子照射されたW-Re合金とK-doped Wの水素同位体吸蔵特性2018
Author(s)
大宅諒, Lee Heun Tae, 中村揚, 伊東英貴, 桑原竜弥, 矢嶋美幸, 外山健, 鈴木克弥, 高木誠, 大野哲靖, 上田良夫, 波多野雄治
Organizer
第12回核融合エネルギー連合講演会
Related Report
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