Dynamics evaluation of hydrogen isotope behavior in tungsten simulating damage distribution

Moeko Nakata; Keisuke Azuma; Akihiro Togari; Qilai Zhou; Mingzhong Zhao; Takeshi Toyama; Yuji Hatano; Naoaki Yoshida; Hideo Watanabe; Masashi Shimada; Dean Buchenauer; Yasuhisa Oya

doi:10.1016/j.fusengdes.2019.03.114

Dynamics evaluation of hydrogen isotope behavior in tungsten simulating damage distribution

Moeko Nakata^*, Keisuke Azuma, Akihiro Togari, Qilai Zhou, Mingzhong Zhao, Takeshi Toyama, Yuji Hatano, Naoaki Yoshida, Hideo Watanabe, Masashi Shimada, Dean Buchenauer, Yasuhisa Oya

^*この論文の責任著者

研究推進機構水素同位体科学研究センター

研究成果: ジャーナルへの寄稿 › 学術論文 › 査読

抄録

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.

本文言語	英語
ページ（範囲）	2096-2099
ページ数	4
ジャーナル	Fusion Engineering and Design
巻	146
DOI	https://doi.org/10.1016/j.fusengdes.2019.03.114
出版ステータス	出版済み - 2019/09

ASJC Scopus 主題領域

土木構造工学
原子力エネルギーおよび原子力工学
材料科学一般
機械工学

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10.1016/j.fusengdes.2019.03.114

引用スタイル

@article{4b64f87746444e0e9a65e04ad1c1ad97,

title = "Dynamics evaluation of hydrogen isotope behavior in tungsten simulating damage distribution",

abstract = "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.",

keywords = "Damage distribution, Heavy ion irradiation, Hydrogen isotope retention behavior, Plasma facing materials, Tungsten",

author = "Moeko Nakata and Keisuke Azuma and Akihiro Togari and Qilai Zhou and Mingzhong Zhao and Takeshi Toyama and Yuji Hatano and Naoaki Yoshida and Hideo Watanabe and Masashi Shimada and Dean Buchenauer and Yasuhisa Oya",

note = "Publisher Copyright: {\textcopyright} 2019",

year = "2019",

month = sep,

doi = "10.1016/j.fusengdes.2019.03.114",

language = "英語",

volume = "146",

pages = "2096--2099",

journal = "Fusion Engineering and Design",

issn = "0920-3796",

publisher = "Elsevier B.V.",

}

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

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.

KW - Damage distribution

KW - Heavy ion irradiation

KW - Hydrogen isotope retention behavior

KW - Plasma facing materials

KW - Tungsten

UR - http://www.scopus.com/inward/record.url?scp=85063759806&partnerID=8YFLogxK

U2 - 10.1016/j.fusengdes.2019.03.114

DO - 10.1016/j.fusengdes.2019.03.114

M3 - 学術論文

AN - SCOPUS:85063759806

SN - 0920-3796

VL - 146

SP - 2096

EP - 2099

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

ER -

Dynamics evaluation of hydrogen isotope behavior in tungsten simulating damage distribution

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