2011 Fiscal Year Final Research Report
Study on clarification of tritium transfer in fusion reactor bIankets and on development of new processes to recover tritium
Project Area | Tritium Science and Technology for Fusion Reactor |
Project/Area Number |
19055006
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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 | Kyushu University |
Principal Investigator |
FUKADA Satoshi 九州大学, 大学院・総合理工学研究院, 教授 (50117230)
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Co-Investigator(Kenkyū-buntansha) |
ENOEDA Mikio 日本原子力研究開発機構, 核融合研究開発部門, 主任研究員 (90354620)
KAWAMURA Yoshinori 日本原子力研究開発機構, 核融合研究開発部門, 主任研究員 (10354614)
KATAYAMA Kazunari 九州大学, 大学院・総合理工学研究院, 助教 (90380708)
NISHIKAWA Masabumi 九州大学, 大学院・総合理工学研究院, 名誉教授 (90026229)
SAGARA Akio 核融合科学研究所, 核融合システム研究系, 核融合研究プロジェクト総主幹,教授 (20187058)
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Project Period (FY) |
2007 – 2011
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Keywords | 核融合 / トリチウム / 安全性 / ブランケット / 増殖率 / 透過漏洩 |
Research Abstract |
Based on material's tritium breeding ratio (TBR) and tritium retentions that have been already determined for solid breeding materials of Li_2TiO_3 and Li_4SiO_4 and liquid breeding materials of Li, Li-Pb eutectic alloy and Flibe molten salt, blanket systems are experimentally investigated to achieve tritium self-sufficient condition and to realize safety to lower level than allowable tritium leak rate. Micro-scale He convection in solid blankets and new tritium recovery systems are experimentally proved for each of the solid and liquid blankets. The present study is heavily contributed to realize fusion reactor systems.
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[Journal Article] Transfer of tritium in concrete coated with hydrophobic paints2012
Author(s)
S. Fukada, Y. Edao, K. Sato, T, Takeishi, K. Katayama, K. Kobayashi, T. Hayashi, T. Yamanishi, Y. Hatano, A. Taguchi, S. Akamaru
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Journal Title
Fusion Engineering and Design
Volume: 87
Pages: 54-60
Peer Reviewed
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[Journal Article] Target system of IFMIF/EVEDA in Japanese activities2011
Author(s)
M. Ida, S. Fukada, T. Furukawa, Y. Hirakawa, H. Horiike, T. Kanemura, H. Kondo, M. Miyashita, H. Nakamura, H. Sigiura, A. Suzuki, T. Terai, Y. Tsuji, H. Ushimaru, K. Watanabe, J. Yagi
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Journal Title
Journal of Nuclear Materials
Volume: 417
Pages: 1294-1298
Peer Reviewed
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[Journal Article] IFMIF/EVEDA lithium test loop: design and fabrication technology of target assembly as a key component2011
Author(s)
H. Kondo, T. Furukawa, Y. Hirakawa, K Nakamura, M. Ida, K. Watanabe, T. Kaneraura, E. Wakai, H. Horiike, N. Yamaoka, H. Sugiura, T. Terai, A. Suzuki, J. Yagi, S. Fukada, H. Nakamura, I. Matsushita, F. Groeschel, K. Fujishiro, P. Garin, H. Kimura
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Journal Title
Nuclear Fusion
Volume: 51
Pages: 1-12
Peer Reviewed
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[Presentation] Fabrication of hydrogen recovery unit in the molten salt loop Oroshi-12011
Author(s)
T. Nagasaka, T. Tanaka, A. Sagara, T. Muroga, M. Kondo, T. Watanabe, S. Fukada, H. Yukawa, T. Namba, T. Iikubo
Organizer
21^<st> International Toki Conference on Integration of Fusion Science and Technology for steady-state operation
Place of Presentation
Toki, Japan
Year and Date
20111128-30
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[Presentation] Progress of ITER Test Blanket Module Development in Japan2011
Author(s)
M. Enoeda, H. Tanigawa, T. Hirose, S. Suzuki, K. Ochiai, C. Konno, Y. Kawamura, T. Yamanishi, T. Hoshino, M. Nakamichi, H. Tanigawa, K. Ezato, Y. Seki, A. Yoshikawa, D. Tsuru
Organizer
21st International Toki Conference (ITC-21) on Integration of Fusion Science and Technology for Steady State Operation
Place of Presentation
Toki, Japan
Year and Date
20111128-30
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[Presentation] Development of the Water Cooled Ceramic Breeder Test Blanket Module in Japan2011
Author(s)
M. Enoeda, H. Tanigawa, T. Hirose, S. Suzuki, K. Ezato, Y. Seki, A. Yoshikawa, D. Tsuru, K. Ochiai, C. Konno, Y. Kawamura, T. Yamanishi, T. Hoshino, M. Nakamichi, H. Tanigawa, M. Akiba
Organizer
10th International Symposium on Fusion Nuclear Technology (ISFNT-10)
Place of Presentation
Portland, USA.
Year and Date
20110912-16
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