Annealing effects on deuterium retention behavior in damaged tungsten
Creators
- 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.2016.06.012Additional 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
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50079737
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- ANNEALING; ATOMIC DISPLACEMENTS; DAMAGE; DEFECTS; DESORPTION; DEUTERIUM; HEAVY IONS; IRON IONS; IRRADIATION; POSITRON ANNIHILATION SPECTROSCOPY; RETENTION; TUNGSTEN; VOIDS
- Descriptors DEC
- CHARGED PARTICLES; ELEMENTS; HEAT TREATMENTS; HYDROGEN ISOTOPES; IONS; ISOTOPES; LIGHT NUCLEI; METALS; NUCLEI; ODD-ODD NUCLEI; PHYSICAL RADIATION EFFECTS; RADIATION EFFECTS; REFRACTORY METALS; SORPTION; SPECTROSCOPY; STABLE ISOTOPES; TRANSITION ELEMENTS
Optional Information
- Notes
- © 2016 The Authors. Published by Elsevier Ltd.