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)
宗像 健三 九州大学, 大学院・総合理工学研究院, 准教授 (70264067)
|
Project Period (FY) |
2007 – 2011
|
Project Status |
Completed (Fiscal Year 2011)
|
Budget Amount *help |
¥90,800,000 (Direct Cost: ¥90,800,000)
Fiscal Year 2011: ¥8,000,000 (Direct Cost: ¥8,000,000)
Fiscal Year 2010: ¥24,000,000 (Direct Cost: ¥24,000,000)
Fiscal Year 2009: ¥23,100,000 (Direct Cost: ¥23,100,000)
Fiscal Year 2008: ¥20,400,000 (Direct Cost: ¥20,400,000)
Fiscal Year 2007: ¥15,300,000 (Direct Cost: ¥15,300,000)
|
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 / プラズマ核融合 / リチウム / 回収 / 透過 / プラズマ・核融合 / 原子力エネルギー / 核融合炉 / リチウム酸化物 / 吸着 / 同位体交換 / ノリチウム |
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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Report
(7 results)
Research Products
(245 results)
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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
Related Report
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
Related Report
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
Related Report
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.Kanemura, 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(123008)
Issue: 12
Pages: 1-12
DOI
Related Report
Peer Reviewed
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[Journal Article] Transfer of tritium in concrete coated with hydrophobic paints2011
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
Issue: 1
Pages: 54-60
DOI
Related Report
Peer Reviewed
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[Journal Article] Tritium transfer in porous concrete materials coated with hydrophobic paints2011
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 Science and Technology
Volume: 60
Pages: 1061-1064
Related Report
Peer Reviewed
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[Journal Article] R&D of a Li2TiO3 pebble bed for a test blanket module in JAEA2009
Author(s)
H. Tanigawa, T. Hoshino, Y. Kawamura, M. Nakamichi, K. Ochiai, M. Akiba, M.,o, M. Enoeda, K. Ezato, K. Hayashi, T. Hirose, C. Konno, H. Nakamura, T. Nozawa, H. Ogiwara, Y. Seki, H. Tanigawa, K. Tsuchiya, D. Tsuru, T. Yamanishi
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Journal Title
Nuclear Fusion 49
Pages: 55021-55021
Related Report
Peer Reviewed
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[Journal Article] Status of engineering design of lithium target in IFMIF-EVEDA2009
Author(s)
H.Nakamura, P.Agostini, K.Ara, S.Fukada, K.Furuya, P.Garin, A.Gessi, D.Giusti, F.Groeschel, H.Horiike, M.Ida, T.Kanemura, H.Kondo, N.Loginov, G.Micciche, M.Miashita, ES.Nitti, A.Suzuki, T.Terai, K.WatImabe, J.Yai, E.Yoshida, A-Mikheyev
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Journal Title
Fusion Engineering and Desien 84
Pages: 252-258
Related Report
Peer Reviewed
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[Journal Article] Nuclear Fusion2009
Author(s)
Y.Kawamura, K.Isobe, Y.Iwai, K.Kobayashi, H.Nakamura, T.Hayashi, T.Yamanishi
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Journal Title
Research and develofment of the tritium recovery system for the blanket of the fusion reactor in JAEA 49
Related Report
Peer Reviewed
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[Journal Article] R&D of a Li_2TiO_3 pebble bed for a test blanket module in JAEA2009
Author(s)
H.Tanigawa, T.Hoshino, Y.Kawamura, M.Nakamichi, K.Ochiai, M.Akiba, M.Ando, M.Enoeda, K.Ezato, K.Hayashi, T.Hirose, C.Konno, H.Nakamura, T.Nozawa, H.Ogiwara, Y.Seki, H.Tanigawa, K.Tsuchiya, D.Tsuru, T.Yamanishi
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Journal Title
Related Report
Peer Reviewed
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[Journal Article] Status of the development of Water Cooled Ceramic Breeder (WCCB) Test Blanket Module2009
Author(s)
M.Enoeda, S.Suzulci, D.Tsuru, T.Hirose, Hisashi Tanigawa, Y.Seki, K.Ezato, K.Yokoyama, H.Nishi, S.Mori, M.Dairaku, T.Hoshino, M.Nakamichi, Y.Kawamura, Hiroyasu Tanigawa
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Journal Title
Proceedings of 15th CBBI -Sapporo, 3-4, September, 2009-JAEA-Conf 2009-006 JAEA-Conf2009-006
Pages: 29-42
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[Journal Article] 核熱解析による固体増殖水冷却方式テストブランケットモジュールのトリチウム増殖比に関する検討2007
Author(s)
関洋 治, 谷川 尚, 鶴大 悟, 榎枝 幹男, 秋場 真人, 江里幸 一郎, 丹澤 貞光, 西 宏, 廣瀬 貴規, 本間 隆, 毛利 憲介, 横山 堅二
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Journal Title
JAEA-Technology
Pages: 67-74
Related Report
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[Journal Article] Reaction rate of beryllium with fluorine ion for Flibe redox control2007
Author(s)
S., Fukada・M., F., Simpson・R., A., Anderl・J., P., Sharpe・K., Katayama・G., R., Smolik・Y., Oya・T., Terai・K., Okuno・Y., Hatano・D., A., Petti・S., Tanaka・D., K., Sze・A., Sagara
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Journal Title
Journal of Nuclear Maaterials 367-370
Pages: 1190-1196
Related Report
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
Related Report
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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
Related Report
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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.
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[Presentation] Development of IFMIF-EVEDA liquid lithium target system in Japan2009
Author(s)
H.Nakamura, K.Ara, Y.Edao, S.Fukada, T.Furukawa, K.Furuya, P.Garin, G.Go, F.Grceschel, Y.Hirakawa, H.Horiike, M.Ida, T.Kanemura, H.Kondo,Y.Kukita, M.Miyashita, M.Ohtaka, A.Suzuki, T.Terai, Y.Tsuji, E.Wakai, K.Watanabe, J.Yagi, E.Yoshida
Organizer
9th International Symposium on Fusion Nuclear Technology
Place of Presentation
Dalian, China
Related Report
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[Presentation] Status of the development of water cooled ceramic breeder(WCCB) test blanket module2009
Author(s)
M.Enceda, S.Suzuki, D.Tsuru, T.Hirose, Hisashi Tanigawa, Y.Seki, K.Ezato, K.Yokoyama, H.Nishi, S.Mori, M.Dairaku, T.Hoshino, M.Nakamichi, Y.Kawamura, Hiroyasu Tanigawa
Organizer
固体増殖ブランケット相互作用国際ワ-クショップ(CBBI-15)
Place of Presentation
Sapporo, Japan
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[Presentation] R&Ds on Li_2TiO_3 Pebble Bed for Test Blanket Module in JAEA2008
Author(s)
H. Tanigawa, T. Hoshino, Y. Kawamura, M. Nakamichi, K. Ochiai, M. Akiba, M. Ando, M. Enoeda, K. Ezato, K. Hayashi, T. Hirose, C. Konno, H. Nakamura, T. Nozawa, H. Ogiwara, Y. Seki, H. Tanigawa, K. Tsuchiya, D. Tsuru. T. Yamanishi
Organizer
22nd IAEA Fusion Energy Conference
Place of Presentation
Geneva, Switzerland
Year and Date
2008-10-15
Related Report
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[Presentation] Research and development on Water-Cooled Solid Breeder Test Blanket Module in JAEA2007
Author(s)
Enoeda, M・Tanigawa, H・Tsuru, D・Ezato, K・Yokoyama, K・Dairaku, M・Seki, Y・Suzuki, S・Mohri, K・Nishi, H・Hirose, T・Tanigawa, H・Akiba, M
Organizer
The 16th Pacific Basin Nuclear Conference
Place of Presentation
Aomori
Year and Date
2007-10-15
Related Report
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[Presentation] Concentration profile of tritium penetrated into concrete wall2007
Author(s)
H., Takata・K., Furuichi・M., Nishikawa・S., Fukada・K., Katayama・T., Toshiharu・T., Hayashi・K., Kobayashi・H., Namba
Organizer
8th International Conhference on Tritium Science and Technology
Place of Presentation
Rochester, NY, USA
Year and Date
2007-09-18
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