Integrated material system modeling of fusion blanket

A. Sagara, R. Nygren, M. Miyamoto, D. Nishijima, R. Doerner, S. Fukada, Y. Oya, T. Oda, Y. Watanabe, K. Morishita, F. Gao, T. Norimatsu

研究成果: ジャーナルへの寄稿評論記事

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抜粋

The blanket of fusion reactors is a multifunctional system that breeds tritium, harvests heat from the burning plasma, and protects the other components and the environment. The common task in the US-J TITAN (Tritium, Irradiation and Thermofluid for America and Nippon) project identifies cross-linked considerations in the blanket system modeling on the basis of the material research in each task. In this paper, we review the main outputs of this task: elucidation of the effect of helium on deuterium retention in the tungsten wall, analysis of tritium transfer in a PbLi liquid breeder, experimental and computational studies on the effects of radiation damage on hydrogen trapping, and modeling of the tritium barrier in a double-tube heat exchanger.

元の言語英語
ページ(範囲)477-483
ページ数7
ジャーナルMaterials Transactions
54
発行部数4
DOI
出版物ステータス出版済み - 4 8 2013

    フィンガープリント

All Science Journal Classification (ASJC) codes

  • Materials Science(all)
  • Condensed Matter Physics
  • Mechanics of Materials
  • Mechanical Engineering

これを引用

Sagara, A., Nygren, R., Miyamoto, M., Nishijima, D., Doerner, R., Fukada, S., ... Norimatsu, T. (2013). Integrated material system modeling of fusion blanket. Materials Transactions, 54(4), 477-483. https://doi.org/10.2320/matertrans.MG201210