2011 Fiscal Year Final Research Report
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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| Keywords | 核融合炉 / ブランケット / トリチウム / 増殖率 / 透過漏洩 |
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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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[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)
Year and Date
20081013-18
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