Experimental study on simultaneous recovery of tritium and heat in several fludized liquid blankets
Project/Area Number |
24246153
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Research Category |
Grant-in-Aid for Scientific Research (A)
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Allocation Type | Single-year Grants |
Section | 一般 |
Research Field |
Nuclear fusion studies
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Research Institution | Kyushu University |
Principal Investigator |
Fukada Satoshi 九州大学, 総合理工学研究科(研究院), 教授 (50117230)
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Co-Investigator(Kenkyū-buntansha) |
KATAYAMA Kazunari 九州大学, 大学院総合理工学研究院, 准教授 (90380708)
枝尾 祐希 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, 研究員 (70633858)
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Co-Investigator(Renkei-kenkyūsha) |
EDAO Yuki 日本原子力研究開発機構, 核融合研究開発部門, 研究員 (70633858)
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Project Period (FY) |
2012-04-01 – 2016-03-31
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Project Status |
Completed (Fiscal Year 2015)
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Budget Amount *help |
¥36,270,000 (Direct Cost: ¥27,900,000、Indirect Cost: ¥8,370,000)
Fiscal Year 2015: ¥3,120,000 (Direct Cost: ¥2,400,000、Indirect Cost: ¥720,000)
Fiscal Year 2014: ¥6,760,000 (Direct Cost: ¥5,200,000、Indirect Cost: ¥1,560,000)
Fiscal Year 2013: ¥6,240,000 (Direct Cost: ¥4,800,000、Indirect Cost: ¥1,440,000)
Fiscal Year 2012: ¥20,150,000 (Direct Cost: ¥15,500,000、Indirect Cost: ¥4,650,000)
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Keywords | 液体ブランケット / トリチウム / 回収 / 溶融塩 / 共融合金 / 透過窓 / 液体リチウム / LiPb共融合金 / 溶融塩Flibe / Flinabe / 水素同位体 / 核融合炉 / フッ化物溶融塩 / 透過 / 気泡 / 物質移動 / リチウム鉛共融合金 / ブランケット / 熱 |
Outline of Final Research Achievements |
Promising liquid blanket candidates of Li17Pb83 eutectic alloy and Flinabe molten salt were investigated along with Li for comparison and circulating loops for each candidate were made up. Constitution of integrated blanket systems and clarification of their operating conditions have been made from various viewpoints for effective simultaneous recovery of heat and tritium from each fluidized liquid blanket. Permeation window. liquid-bubbles direct contact tower and Y getter bed were experimentally investigated as examples for effective tritium recovery methods and designs of concrete recovery apparatus were presented. The design which satisfies the conditions not only to keep tritium inventory in the Li-Pb or Flinabe blanket as low as possible but also to suppress tritium permeation leak through tubes of their blankets or heat exchanger as low as reasonably achievable was clearly presented in international scientific journals in English.
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Report
(5 results)
Research Products
(114 results)
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[Journal Article] Present Status and Recent Evaluation of Lithium Target Facility Development in IFMIF/EVEDA Project2014
Author(s)
E. Wakai, H. Kondo, T. Kanemura, T. Furukawa, Y. Hirakawa, K. Watanabe, M. Ida, Y. Ito, K. Nakaniwa, E. Hoashi, H. Horiike, H. Serizawa, Y. Kawahito, S. Fukada, Y. Sugie, A. Suzuki, J. Yagi, 他12名
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Journal Title
Fusion Science and Technology
Volume: 66
Issue: 1
Pages: 46-56
DOI
Related Report
Peer Reviewed
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[Journal Article] Clarification of Tritium Behavior in Pb–Li Blanket System2013
Author(s)
S. Fukada, T. Terai, S. Konishi, K. Katayama, T. Chikada, Y. Edao, T. Muroga, M. Shimada, B. Merrill, D. K. Sze
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Journal Title
MATERIALS TRANSACTIONS
Volume: 54
Issue: 4
Pages: 425-429
DOI
NAID
ISSN
1345-9678, 1347-5320
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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[Presentation] Chemical analysis of hydrogen isotopes dissolved in Li and Y for hot trap of IFMIF target loop2012
Author(s)
Tetsushi Hiromoto, Satoshi Fukada, Yuki Edao, Satoshi Shigeharu, Yusuke Hatachi, Hiroo Nakamura, Hiroo Kondo, Mizuho Ida, Kazuhiro Nakamura, Kazuyoshi Watanabe
Organizer
Topical meeting of Fusion Energy, TOFE-2012
Place of Presentation
Nashville, TN, USA
Related Report
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