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Title: Annealing effects on deuterium retention behavior in damaged tungsten
Authors: Sakurada, S.
Yuyama, K.
Uemura, Y.
Fujita, H.
Hu, C.
Toyama, T.
Yoshida, N.
Hinoki, T.
Kondo, S.
Shimada, M.
Buchenauer, D.
Chikada, T.
Oya, Y.
Author's alias: 檜木, 達也
近藤, 創介
Keywords: Hydrogen isotopes retention
Heavy-ion irradiation
Issue Date: Dec-2016
Publisher: Elsevier BV
Journal title: Nuclear Materials and Energy
Volume: 9
Start page: 141
End page: 144
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.
Rights: © 2016 The Authors. Published by Elsevier Ltd. This is an open access article under the CC BY-NC-ND license (
DOI(Published Version): 10.1016/j.nme.2016.06.012
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