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タイトル: Annealing effects on deuterium retention behavior in damaged tungsten
著者: 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.
著者名の別形: 檜木, 達也
近藤, 創介
キーワード: Hydrogen isotopes retention
Heavy-ion irradiation
Annealing
TDS
TEM
PAS
発行日: Dec-2016
出版者: Elsevier BV
誌名: Nuclear Materials and Energy
巻: 9
開始ページ: 141
終了ページ: 144
抄録: 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.
著作権等: © 2016 The Authors. Published by Elsevier Ltd. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
URI: http://hdl.handle.net/2433/218607
DOI(出版社版): 10.1016/j.nme.2016.06.012
出現コレクション:学術雑誌掲載論文等

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