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: Contribution to journalReview article査読

1 被引用数 (Scopus)

抄録

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.

本文言語英語
ページ(範囲)477-483
ページ数7
ジャーナルMaterials Transactions
54
4
DOI
出版ステータス出版済み - 2013

All Science Journal Classification (ASJC) codes

  • 材料科学(全般)
  • 凝縮系物理学
  • 材料力学
  • 機械工学

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