First result of deuterium retention in neutron-irradiated tungsten exposed to high flux plasma in TPE

Masashi Shimada*, Y. Hatano, P. Calderoni, T. Oda, Y. Oya, M. Sokolov, K. Zhang, G. Cao, R. Kolasinski, J. P. Sharpe

*この論文の責任著者

研究成果: ジャーナルへの寄稿学術論文査読

75 被引用数 (Scopus)

抄録

With the Japan-US joint research project Tritium, Irradiations, and Thermofluids for America and Nippon (TITAN), an initial set of tungsten samples (99.99% purity, A.L.M.T. Co.) were irradiated by high flux neutrons at 323 K to 0.025 dpa in High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL). Subsequently, one of the neutron-irradiated tungsten samples was exposed to a high-flux deuterium plasma (ion flux: 5 × 1021 m -2 s-1, ion fluence: 4 × 1025 m -2) in the Tritium Plasma Experiment (TPE) at Idaho National Laboratory (INL). The deuterium retention in the neutron-irradiated tungsten was 40% higher in comparison to the unirradiated tungsten. The observed broad desorption spectrum from neutron-irradiated tungsten and associated TMAP modeling of the deuterium release suggest that trapping occurs in the bulk material at more than three different energy sites.

本文言語英語
ページ(範囲)S667-S671
ジャーナルJournal of Nuclear Materials
415
1 SUPPL
DOI
出版ステータス出版済み - 2011/08/01

ASJC Scopus 主題領域

  • 核物理学および高エネルギー物理学
  • 材料科学一般
  • 原子力エネルギーおよび原子力工学

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