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
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- 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).
- ID情報
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- DOI : 10.1016/j.fusengdes.2020.112100