Removal rates of hydrogen isotope from liquid Li by HF-treated Y plate

Y. Wu, Y. Edao, S. Fukada, H. Nakamura, H. Kondo

研究成果: ジャーナルへの寄稿学術誌査読

4 被引用数 (Scopus)

抄録

The International Fusion Materials Irradiation Facility (IFMIF) is designed to provide an intense neutron source for the development of fusion reactor materials. Neutron is supplied by the D-7Li reaction, and at the same time tritium (T) is generated as its by-product. Therefore, the removal of T generated in Li becomes inevitable. It is proved in the present study that HF pretreatment of Y getter materials leads to enhance hydrogenating rates of Y placed in Li. The ratio of the H removal rate of HF-treated Y to that of non-treated Y is determined under the conditions of three different temperatures of 573K, 553K and 523K. The effect of enhancement of hydrogenating rates is quantitatively determined.

本文言語英語
ページ(範囲)1484-1487
ページ数4
ジャーナルFusion Engineering and Design
85
7-9
DOI
出版ステータス出版済み - 12月 2010

!!!All Science Journal Classification (ASJC) codes

  • 土木構造工学
  • 原子力エネルギーおよび原子力工学
  • 材料科学(全般)
  • 機械工学

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