論文

査読有り 国際共著 国際誌
2020年11月18日

Tritium retention in displacement-damaged tungsten exposed to deuterium-tritium gas mixture at elevated temperatures

Fusion Engineering and Design
  • V.Kh.Alimov
  • ,
  • Y.Torikaia
  • ,
  • Y.Hatano
  • ,
  • T.Schwarz-Selingerd

記述言語
英語
掲載種別
研究論文(学術雑誌)
DOI
10.1016/j.fusengdes.2020.112100
出版者・発行元
ELSEVIER

W samples, previously irradiated with 20 MeV W ions at room temperature to a displacement-damage level of 0.23 displacements per atom (dpa) at the peak of displacements, were exposed to a deuterium-tritium (D2 ― DT ― T2) gas mixture with a tritium content of 6% at a total pressure of 1.2 kPa and temperatures of 773 K and 973 K for 3 h. The concentration of tritium retained in the displacement-damage zone of these W samples was determined by a method combining chemical etching and subsequent analysis of tritium in the etching solution using liquid scintillation counting (CE-LSC).

リンク情報
DOI
https://doi.org/10.1016/j.fusengdes.2020.112100
ID情報
  • DOI : 10.1016/j.fusengdes.2020.112100

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