Blister formation and deuterium retention on tungsten exposed to low energy and high flux deuterium plasma

K. Tokunaga, M. J. Baldwin, R. P. Doerner, N. Noda, Y. Kubota, N. Yoshida, T. Sogabe, T. Kato, B. Schedler

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Abstract

Deuterium ion irradiation on tungsten has been carried out with incident energies of 100 eV and flux of 1 × 1022 D+ m -2 s-1 at a temperature in range between 333 K and 1130 K up to a dose of 1 × 1026 D+ m-2. Three kinds of tungsten used are pure tungsten made by powder metallurgy tungsten (PM-W), vacuum plasma spray tungsten (VPS-W) and single crystal tungsten (SC-W). Surface morphology before and after the irradiation is observed with an SEM. In addition, retention property of deuterium after the irradiation is also examined with a TDS. Behavior of blister formation depends on the kind of the samples and the irradiation temperatures. TDS measurement also shows that deuterium is not retained in sample, which the blisters are not formed. The behavior of the blister formation and deuterium retention is influenced by the manufacturing process and the sample history of tungsten.

Original languageEnglish
Pages (from-to)887-891
Number of pages5
JournalJournal of Nuclear Materials
Volume337-339
Issue number1-3 SPEC. ISS.
DOIs
Publication statusPublished - Mar 1 2005

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All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering

Cite this

Tokunaga, K., Baldwin, M. J., Doerner, R. P., Noda, N., Kubota, Y., Yoshida, N., ... Schedler, B. (2005). Blister formation and deuterium retention on tungsten exposed to low energy and high flux deuterium plasma. Journal of Nuclear Materials, 337-339(1-3 SPEC. ISS.), 887-891. https://doi.org/10.1016/j.jnucmat.2004.10.137