Clarification of tritium behavior in fusion reactor blankets
| Project Area | Tritium Science and Technology for Fusion Reactor |
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| Project/Area Number |
19055007
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| Research Category |
Grant-in-Aid for Scientific Research on Priority Areas
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| Allocation Type | Single-year Grants |
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| Review Section |
Science and Engineering
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| Research Institution | Kyushu University |
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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) |
TERAI Takayuki 東京大学, 大学院・工学系研究科, 教授 (90175472)
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| Project Period (FY) |
2007 – 2011
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| Project Status |
Completed (Fiscal Year 2011)
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| Budget Amount *help |
¥7,300,000 (Direct Cost: ¥7,300,000)
Fiscal Year 2011: ¥2,500,000 (Direct Cost: ¥2,500,000)
Fiscal Year 2010: ¥1,200,000 (Direct Cost: ¥1,200,000)
Fiscal Year 2009: ¥1,200,000 (Direct Cost: ¥1,200,000)
Fiscal Year 2008: ¥1,200,000 (Direct Cost: ¥1,200,000)
Fiscal Year 2007: ¥1,200,000 (Direct Cost: ¥1,200,000)
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| Keywords | 核融合炉 / ブランケット / トリチウム / 増殖率 / 透過漏洩 / プラズマ核融合 / 原子力エネルギー / リチウム / 回収 / 核融合 / 透過 / 酸化膜 / 熱回収 / プランケット |
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| Research Abstract |
It is necessary to construct blanket systems higher than TBR>1 for solid or liquid breeder materials that is necessary for steady-state operation and to decrease the tritium leak rate lower than the ａllowable level. The B1 group performed experimental researches of effective tritium evolution and recovery of Li, Li-Pb, Li_2TiO_3 etc from ａ chemical-engineering scope, and the B2 group did experimental clarification of new breeding materials, material-breeder interaction and development of ａ new effective tritium permeation barrier of PRF<1/1000 from ａ material-science scope. In order to perform the researches effectively, the B3 group held meeting between B1 and Ｂ２ members regularly to exchange information and funded the group members to assist their researches.
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Report
(7 results)
Research Products
(178 results)
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[Journal Article] Current status of design and construction of IFMIF/EVEDA lithium test loop2011
Author(s)
H.Kondo, T.Furukawa, H.Horiike, Y.Hirakawa, H.Nakamura, H.Sugiura, T.Kanemura, M.Ida, I.Matsushita, J.Yagi, A.Suzuki, T.Terai, S.Fukada
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Journal Title
ASME Conference Proceedings, ICONE18-29268
Pages: 523-531
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[Journal Article] Optimization activities on design studies of LHD-type reactor FFHR2008
Author(s)
A.Sagara, O. Mitarai, T. Tanaka, S. Imagawa, Y. Kozaki, M. Kobayashi, T. Morisaki, T. Watanabe, K. Takahata, H. Tamura, N. Yanagi, K. Nishimura, H. Chikaraishi, S. Yamada, S. Fukada, S. Masuzaki, A Shishkin, Y. Igitichanov, T. Goto, Y Ogawa, T. Muroga, T. Mito, O. Motoiima and FFHR design group
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Journal Title
Fusion Engineering and Design 83
Pages: 1690-1695
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Peer Reviewed
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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
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Peer Reviewed
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[Presentation] Research and development on water-cooled solid breeder test blanket module in JAEA2008
Author(s)
M. Enoeda, H. Tanigawa, D. Tsuru, T. Hirose, K. Ezato, K. Yokoyama, M. Dairaku, Y. Seki, S. Suzuki, K. Mohri, H. Nishi, H. Tanigawa, K. Ochiai, S. Sato, Y. Kawamura, M. Akiba, S. Fukada
Organizer
16^<th> Pacific Basin Nuclear Conference (16PBNC)
Place of Presentation
Aomori, Japan （Paper ID P16P1272)
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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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