2011 Fiscal Year Final Research Report
Experimental studies on in-vessel tritium inventory in complicated environment of fusion reactors
Project Area | Tritium Science and Technology for Fusion Reactor |
Project/Area Number |
19055003
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Research Category |
Grant-in-Aid for Scientific Research on Priority Areas
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Allocation Type | Single-year Grants |
Review Section |
Science and Engineering
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Research Institution | Osaka University |
Principal Investigator |
UEDA Yoshio 大阪大学, 大学院・工学研究科, 教授 (30193816)
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Co-Investigator(Kenkyū-buntansha) |
HINO Tomoaki 北海道大学, 工学研究科, 教授 (30109491)
OHNO Noriyasu 名古屋大学, 工学研究科, 教授 (60203890)
TAKAGI Ikuji 京都大学, 工学研究科, 教授 (20206717)
NAKANO Tomohide 独立行政法人日本原子力研究開発機構, 核融合研究開発部門, 副主任研究員 (50354593)
TANABE Tetsuo 九州大学, 総合理工学研究科, 教授 (00029331)
NAGATA Shinji 東北大学, 金属材料研究所, 准教授 (40208012)
MASAKI Kei 独立行政法人日本原子力研究開発機構, 核融合研究開発部門, 研究職 (10354648)
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Project Period (FY) |
2007 – 2011
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Keywords | 核融合炉 / トリチウム / プラズマ壁相互作用 / 照射損傷 / 材料混合 / スパッタリング / 再堆積 / トリチウム除去 |
Research Abstract |
In order to understand tritium accumulation behavior and to develop tritium removal methods in fusion reactors, experimental researches have been done for retention and permeation under mixed ion irradiation, retention in high-energy ion damaged tungsten, generation and retention of dust particles, erosion-transport-deposition of wall materials and its effects on retention in JT-60U tokamak, and removal of hydrogen isotopes from redeposition layers. Many useful results have been obtained for estimation of T retention in fusion reactors.
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Research Products
(29 results)
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[Journal Article] Deuterium trapping in tungsten damaged by high-energy hydrogen ion irradiation2009
Author(s)
M. Fukumoto, H. Kashiwagi, Y. Ohtsuka, Y. Ueda, M. Taniguchi, T. Inoue, K. Sakamoto, J.Yagyu, T. Arai, I. Takagi, T.Kawamura
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Journal Title
Journal of Nuclear Materials
Volume: 390-391
Pages: 572-575
URL
Peer Reviewed
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