TY - JOUR
T1 - Effect of helium irradiation on deuterium permeation behavior in tungsten
AU - Uemura, Yuki
AU - Sakurada, Shodai
AU - Fujita, Hiroe
AU - Azuma, Keisuke
AU - Zhou, Quilai
AU - Chikada, Takumi
AU - Oya, Yasuhisa
AU - Hatano, Yuji
AU - Yoshida, Naoaki
AU - Watanabe, Hideo
AU - Oyaizu, Makoto
AU - Isobe, Kanetsugu
AU - Shimada, Masashi
AU - Buchenauer, Dean
AU - Kolasinski, Robert
N1 - Publisher Copyright:
© 2017 Elsevier B.V.
PY - 2017/7/1
Y1 - 2017/7/1
N2 - In this study, we measured deuterium (D) gas-driven permeation through tungsten (W) foils that had been pre-damaged by helium ions (He+). The goal of this work was to determine how ion-induced damage affects hydrogen isotope permeation. At 873 K, the D permeability for W irradiated by 3.0 keV He+ was approximately one order of magnitude lower than that for un-damaged W. This difference diminished with increasing temperature. Even after heating to 1173 K, the permeability returned to less than half of the value measured for un-damaged W. We propose that this is due to nucleation of He bubbles near the surface which potentially serve as a barrier to diffusion deeper into the bulk. Exposure at higher temperatures shows that the D permeability and diffusion coefficients return to levels observed for undamaged material. It is possible that these effects are linked to annealing of defects introduced by ion damage, and whether the defects are stabilized by the presence of trapped He.
AB - In this study, we measured deuterium (D) gas-driven permeation through tungsten (W) foils that had been pre-damaged by helium ions (He+). The goal of this work was to determine how ion-induced damage affects hydrogen isotope permeation. At 873 K, the D permeability for W irradiated by 3.0 keV He+ was approximately one order of magnitude lower than that for un-damaged W. This difference diminished with increasing temperature. Even after heating to 1173 K, the permeability returned to less than half of the value measured for un-damaged W. We propose that this is due to nucleation of He bubbles near the surface which potentially serve as a barrier to diffusion deeper into the bulk. Exposure at higher temperatures shows that the D permeability and diffusion coefficients return to levels observed for undamaged material. It is possible that these effects are linked to annealing of defects introduced by ion damage, and whether the defects are stabilized by the presence of trapped He.
UR - http://www.scopus.com/inward/record.url?scp=85018934439&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=85018934439&partnerID=8YFLogxK
U2 - 10.1016/j.jnucmat.2017.04.041
DO - 10.1016/j.jnucmat.2017.04.041
M3 - Article
AN - SCOPUS:85018934439
SN - 0022-3115
VL - 490
SP - 242
EP - 246
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
ER -