Published March 2007 | Version v1
Journal article

Microstructure dependence of deuterium retention and blistering in the near-surface region of tungsten exposed to high flux deuterium plasmas of 38 eV at 315 K

  • 1. Tritium Technology Group, JAEA, Tokai, Ibaraki 319-1195 (Japan)
  • 2. Positron Beam Laboratory, JAEA, Takasaki, Gunma 370-1292 (Japan)
  • 3. Research Group for Corrosion Damage Mechanism, JAEA, Tokai, Ibaraki 319-1195 (Japan)
  • 4. Research Group for Irradiation Field Materials, JAEA, Tokai, Ibaraki 319-1195 (Japan)

Description

Four kinds of tungsten samples were exposed to 76 eV D2+ ions (38 eV D-1) at a flux of 1022 D m-2s-1. For plasma exposure at 315 K, blistering occurred more significantly on the unrecrystallized and single crystal W samples than the partially and fully recrystallized W samples. The un-recrystallized W sample showed the largest retention ratio at the same fluence. For samples exposed to higher fluences (up to 1027 D m-2), the phenomena of bursting release of deuterium and blister bursting were clearly observed. Preliminary positron annihilation measurements indicated that the vacancy concentration in the near-surface region of tungsten increased after the deuterium plasma exposure. The results of electron back-scattering diffraction showed a strong dependence of blistering upon grain orientation, suggesting the possibility of alleviating blistering by selective texturing of tungsten for future fusion reactors

Additional details

Identifiers

DOI
10.1088/0031-8949/2007/T128/019;
PII
S0031-8949(07)38280-19;

Publishing Information

Journal Title
Physica Scripta (Online)
Journal Volume
2007
Journal Issue
T128
Journal Page Range
p. 96-99
ISSN
1402-4896