TY - JOUR
T1 - Dynamics evaluation of hydrogen isotope behavior in tungsten simulating damage distribution
AU - Nakata, Moeko
AU - Azuma, Keisuke
AU - Togari, Akihiro
AU - Zhou, Qilai
AU - Zhao, Mingzhong
AU - Toyama, Takeshi
AU - Hatano, Yuji
AU - Yoshida, Naoaki
AU - Watanabe, Hideo
AU - Shimada, Masashi
AU - Buchenauer, Dean
AU - Oya, Yasuhisa
N1 - Funding Information:
This study was supported by, University of Toyama Collaboration Program, Collaboration program of Research Institute for Applied Mechanics, Kyushu University and by Instrumental Research Support Office, Research Institute of Green Science and Technology at Shizuoka University. The Fe ion implantation was done in the framework of collaborative research program at The University of Tokyo. This material is based upon work supported by the U.S. Department of Energy Office of Science, Office of Fusion Energy Sciences, under the DOE Idaho Operations Office contract number DE-AC07-05ID14517. Sandia National Laboratories is a multimission laboratory managed and operated by National Technology and Engineering Solutions of Sandia, LLC, a wholly owned subsidiary of Honeywell International, Inc. for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-NA0003525.
Publisher Copyright:
© 2019
PY - 2019/9
Y1 - 2019/9
N2 - 0.8 MeV and 6 MeV iron (Fe) ions were implanted into tungsten (W) to produce the irradiation damages with the various damage distributions. Thereafter, 1.0 keV deuterium ion (D2 +) implantation was performed to evaluate the D retention behavior on damage distribution in W. The experimental results showed that the total D retentions were decreased by increasing the damage concentration introduced near the surface region by 0.8 MeV Fe ion implantation. The retention of D trapped by vacancy clusters and voids, which would be the stable trapping sites with higher trapping energies, were reduced, suggesting that the recombination of D atom into D2 on the W surface was enhanced due to D accumulation near the surface region. It can be said that the hydrogen retention behavior in PFMs will be controlled by the damage distribution near the surface.
AB - 0.8 MeV and 6 MeV iron (Fe) ions were implanted into tungsten (W) to produce the irradiation damages with the various damage distributions. Thereafter, 1.0 keV deuterium ion (D2 +) implantation was performed to evaluate the D retention behavior on damage distribution in W. The experimental results showed that the total D retentions were decreased by increasing the damage concentration introduced near the surface region by 0.8 MeV Fe ion implantation. The retention of D trapped by vacancy clusters and voids, which would be the stable trapping sites with higher trapping energies, were reduced, suggesting that the recombination of D atom into D2 on the W surface was enhanced due to D accumulation near the surface region. It can be said that the hydrogen retention behavior in PFMs will be controlled by the damage distribution near the surface.
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U2 - 10.1016/j.fusengdes.2019.03.114
DO - 10.1016/j.fusengdes.2019.03.114
M3 - Article
AN - SCOPUS:85063759806
SN - 0920-3796
VL - 146
SP - 2096
EP - 2099
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
ER -