In-situ field--ion microscope study of the recovery behavior of ion-irradiated tungsten and tungsten alloys
Five grades of W specimens with different purity levels were irradiated to a dose of typicaly 5 x 10/sup 12/ ion cm/sup -2/ at 18/sup 0/K. Examination with a low-temperature field-ion microscope showed the isochronal-annealing spectra of the specimens to result from a large self-interstitial atom (SIA) flux at approx. 38/sup 0/K, followed by significant SIA flux from approx. 50 to 80/sup 0/K and a small amount of additional recovery up to 120/sup 0/K. The spectra for these specimens were essentially identical between 18 and 120/sup 0/K. High-purity W specimens doped with C showed only a small reduction in the amount of recovery observed for the long-range migration peak at 38/sup 0/K. The isochronal recovery spectra for W-Re specimens were different from the isochronal recovery spectra of pure W specimens. For both alloys the recovery of the Stage I long-range migration peak at 38/sup 0/K was strongly suppressed. All recovery from 18 to 120/sup 0/K was virtually eliminated indicating that during the long-range migration substage at 38/sup 0/K tightly-bound, immobile SIA-Re complexes were formed that suppressed the SIA--SIA reaction. This effect was observed at high Re atom concentrations. The lack of any significant differences for the annealing spectra of the five purity-levels of undoped W and the appearance of impurity effects in the extremely concentrated alloys indicated that the early Stage II recovery observed in the annealing spectra of self-ion irradiated high-purity W was intrinsic. Because of the highly inhomogeneous SIA distribution of the W/sup +/ ion damage, the SIA--SIA interaction during Stage I long-range migration at 38/sup 0/K appeared to be the dominant trapping mechanism. The early Stage II SIA recovery was attributed to the migration or dissolution of these SIA clusters.
- Research Organization:
- Cornell Univ., Ithaca, NY (USA). Dept. of Materials Science and Engineering
- DOE Contract Number:
- EY-76-S-02-3158
- OSTI ID:
- 6065200
- Report Number(s):
- COO-3158-61
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
ANNEALING
CARBON
CRYSTAL DEFECTS
CRYSTAL STRUCTURE
DATA
DATA FORMS
DEPOSITION
DOPED MATERIALS
ELEMENTS
EXPERIMENTAL DATA
GRAPHS
HEAT TREATMENTS
IMPURITIES
INFORMATION
INTERSTITIALS
IRRADIATION
METALS
MIGRATION
NONMETALS
NUMERICAL DATA
PHYSICAL RADIATION EFFECTS
POINT DEFECTS
RADIATION EFFECTS
RECOVERY
REFRACTORY METALS
RHENIUM ADDITIONS
RHENIUM ALLOYS
SELF-IRRADIATION
SURFACE COATING
TABLES
TRANSITION ELEMENTS
TUNGSTEN
TUNGSTEN ALLOYS
TUNGSTEN BASE ALLOYS