Published December 2016 | Version v1
Journal article

Annealing effects on deuterium retention behavior in damaged tungsten

  • 1. Graduate School of Science & Technology, Shizuoka University, Shizuoka (Japan)
  • 2. Institute for Materials Research, Tohoku University, Ibaraki (Japan)
  • 3. Insitute for Applied Mechanics, Kyushu University, Fukuoka (Japan)
  • 4. Insitute of Advanced Energy, Kyoto University, Kyoto (Japan)
  • 5. Fusion Safety Program, Idaho National Laboratory, Idaho (United States)
  • 6. Hydrogen and Combustion Technology Department, Sandia National Laboratories, Livermore (United States)

Description

Highlights: • W samples were irradiated with 6.0 MeV Fe2+ at room temperature and 6.4 MeV Fe3+at elevating temperature. • D retention in W irradiated at elevating temperature was reduced as compared to that in annealed W after Fe2+ irradiation. • D desorption behaviors were almost same in both W sample annealed at ≥1173 K under/after irradiation. - Abstract: Effects of annealing after/under iron (Fe) ion irradiation on deuterium (D) retention behavior in tungsten (W) were studied. The D2 TDS spectra as a function of heating temperature for 0.1 dpa damaged W showed that the D retention was clearly decreased as the annealing temperature was increased. In particular, the desorption of D trapped by voids was largely reduced by annealing at 1173 K. The TEM observation indicated that the size of dislocation loops was clearly grown, and its density was decreased by the annealing above 573 K. After annealing at 1173 K, almost all the dislocation loops were recovered. The results of positron annihilation spectroscopy suggested that the density of vacancy-type defects such as voids, was decreased as the annealing temperature was increased, while its size was increased, indicating that the D retention was reduced by the recovery of the voids. Furthermore, it was found that the desorption temperature of D trapped by the voids for damaged W above 0.3 dpa was shifted toward higher temperature side. These results lead to a conclusion that the D retention behavior is controlled by defect density. The D retention in the samples annealed during irradiation was less than that annealed after irradiation. This result shows that defects would be quickly annihilated before stabilization by annealing during irradiation.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nme.2016.06.012

Additional details

Identifiers

DOI
10.1016/j.nme.2016.06.012;
PII
S2352179115301071;

Publishing Information

Journal Title
Nuclear Materials and Energy
Journal Volume
9
Journal Page Range
p. 141-144
ISSN
2352-1791

Optional Information

Notes
© 2016 The Authors. Published by Elsevier Ltd.