Surface or bulk He existence effect on deuterium retention in Fe ion damaged W

Yasuhisa Oya; Shodai Sakurada; Keisuke Azuma; Qilai Zhou; Akihiro Togari; Sosuke Kondo; Tatsuya Hinoki; Naoaki Yoshida; Dean Buchenauer; Robert Kolasinski; Masashi Shimada; Chase N. Taylor; Takumi Chikada; Yuji Hatano

doi:10.1016/j.nme.2018.06.018

Surface or bulk He existence effect on deuterium retention in Fe ion damaged W

Yasuhisa Oya, Shodai Sakurada, Keisuke Azuma, Qilai Zhou, Akihiro Togari, Sosuke Kondo, Tatsuya Hinoki, Naoaki Yoshida, Dean Buchenauer, Robert Kolasinski, Masashi Shimada, Chase N. Taylor, Takumi Chikada, Yuji Hatano

IMR - Materials Design Division

Research output: Contribution to journal › Article › peer-review

7 Citations (Scopus)

Abstract

To evaluate Helium (He) effect on hydrogen isotope retention in tungsten (W), He⁺ was introduced into W bulk by 201 – 1000 keV He⁺, or W surface by 3 keV He⁺ for 6 MeV Fe ion damaged W at room temperature. The deuterium (D) retention behavior was evaluated by thermal desorption spectroscopy (TDS). In addition, the amount of tritium (T) at surface and bulk were separately evaluated by beta-ray induced X-ray spectroscopy (BIXS). The experimental results indicated that the formation of He-void complexes reduced the D trapping in vacancies and voids which have higher trapping energy by the bulk He retention. The BIXS measurement also supported the He enhanced the D reduction in the W bulk region. On the other hand, the He ion irradiation near the surface region enhanced D trapping by dislocation loops or surface, indicating the existence of He near surface interfered the D diffusion toward the bulk. It was concluded that the He existence in bulk or surface will significantly change the D trapping and diffusion behavior in damaged W.

Original language	English
Pages (from-to)	217-220
Number of pages	4
Journal	Nuclear Materials and Energy
Volume	16
DOIs	https://doi.org/10.1016/j.nme.2018.06.018
Publication status	Published - 2018 Aug

Keywords

Damaged W
Fusion
He in damaged W
Hydrogen isotope retention behavior

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10.1016/j.nme.2018.06.018

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@article{4e08070f6c224efebbc5404d29254998,

title = "Surface or bulk He existence effect on deuterium retention in Fe ion damaged W",

abstract = "To evaluate Helium (He) effect on hydrogen isotope retention in tungsten (W), He+ was introduced into W bulk by 201 – 1000 keV He+, or W surface by 3 keV He+ for 6 MeV Fe ion damaged W at room temperature. The deuterium (D) retention behavior was evaluated by thermal desorption spectroscopy (TDS). In addition, the amount of tritium (T) at surface and bulk were separately evaluated by beta-ray induced X-ray spectroscopy (BIXS). The experimental results indicated that the formation of He-void complexes reduced the D trapping in vacancies and voids which have higher trapping energy by the bulk He retention. The BIXS measurement also supported the He enhanced the D reduction in the W bulk region. On the other hand, the He ion irradiation near the surface region enhanced D trapping by dislocation loops or surface, indicating the existence of He near surface interfered the D diffusion toward the bulk. It was concluded that the He existence in bulk or surface will significantly change the D trapping and diffusion behavior in damaged W.",

keywords = "Damaged W, Fusion, He in damaged W, Hydrogen isotope retention behavior",

author = "Yasuhisa Oya and Shodai Sakurada and Keisuke Azuma and Qilai Zhou and Akihiro Togari and Sosuke Kondo and Tatsuya Hinoki and Naoaki Yoshida and Dean Buchenauer and Robert Kolasinski and Masashi Shimada and Taylor, {Chase N.} and Takumi Chikada and Yuji Hatano",

note = "Funding Information: This study was supported by Japan-US collaboration program, PHENIX, the Joint Usage/Research Program on Zero-Emission Energy Research, Institute of Advanced Energy, Kyoto University (ZE29A-8), by the Collaborative Research Program of Research Institute for Applied Mechanics, Kyushu University, University of Toyama Collaboration Program (NIFS16KUHR035) and Inter-University Laboratory for the Common Use of Nuclear Facilities, Kaihoken. 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-NA-0003525. Publisher Copyright: {\textcopyright} 2018",

year = "2018",

month = aug,

doi = "10.1016/j.nme.2018.06.018",

language = "English",

volume = "16",

pages = "217--220",

journal = "Nuclear Materials and Energy",

issn = "2352-1791",

publisher = "Elsevier Ltd.",

}

TY - JOUR

T1 - Surface or bulk He existence effect on deuterium retention in Fe ion damaged W

AU - Oya, Yasuhisa

AU - Sakurada, Shodai

AU - Azuma, Keisuke

AU - Zhou, Qilai

AU - Togari, Akihiro

AU - Kondo, Sosuke

AU - Hinoki, Tatsuya

AU - Yoshida, Naoaki

AU - Buchenauer, Dean

AU - Kolasinski, Robert

AU - Shimada, Masashi

AU - Taylor, Chase N.

AU - Chikada, Takumi

AU - Hatano, Yuji

N1 - Funding Information: This study was supported by Japan-US collaboration program, PHENIX, the Joint Usage/Research Program on Zero-Emission Energy Research, Institute of Advanced Energy, Kyoto University (ZE29A-8), by the Collaborative Research Program of Research Institute for Applied Mechanics, Kyushu University, University of Toyama Collaboration Program (NIFS16KUHR035) and Inter-University Laboratory for the Common Use of Nuclear Facilities, Kaihoken. 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-NA-0003525. Publisher Copyright: © 2018

PY - 2018/8

Y1 - 2018/8

N2 - To evaluate Helium (He) effect on hydrogen isotope retention in tungsten (W), He+ was introduced into W bulk by 201 – 1000 keV He+, or W surface by 3 keV He+ for 6 MeV Fe ion damaged W at room temperature. The deuterium (D) retention behavior was evaluated by thermal desorption spectroscopy (TDS). In addition, the amount of tritium (T) at surface and bulk were separately evaluated by beta-ray induced X-ray spectroscopy (BIXS). The experimental results indicated that the formation of He-void complexes reduced the D trapping in vacancies and voids which have higher trapping energy by the bulk He retention. The BIXS measurement also supported the He enhanced the D reduction in the W bulk region. On the other hand, the He ion irradiation near the surface region enhanced D trapping by dislocation loops or surface, indicating the existence of He near surface interfered the D diffusion toward the bulk. It was concluded that the He existence in bulk or surface will significantly change the D trapping and diffusion behavior in damaged W.

AB - To evaluate Helium (He) effect on hydrogen isotope retention in tungsten (W), He+ was introduced into W bulk by 201 – 1000 keV He+, or W surface by 3 keV He+ for 6 MeV Fe ion damaged W at room temperature. The deuterium (D) retention behavior was evaluated by thermal desorption spectroscopy (TDS). In addition, the amount of tritium (T) at surface and bulk were separately evaluated by beta-ray induced X-ray spectroscopy (BIXS). The experimental results indicated that the formation of He-void complexes reduced the D trapping in vacancies and voids which have higher trapping energy by the bulk He retention. The BIXS measurement also supported the He enhanced the D reduction in the W bulk region. On the other hand, the He ion irradiation near the surface region enhanced D trapping by dislocation loops or surface, indicating the existence of He near surface interfered the D diffusion toward the bulk. It was concluded that the He existence in bulk or surface will significantly change the D trapping and diffusion behavior in damaged W.

KW - Damaged W

KW - Fusion

KW - He in damaged W

KW - Hydrogen isotope retention behavior

UR - http://www.scopus.com/inward/record.url?scp=85050006139&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=85050006139&partnerID=8YFLogxK

U2 - 10.1016/j.nme.2018.06.018

DO - 10.1016/j.nme.2018.06.018

M3 - Article

AN - SCOPUS:85050006139

SN - 2352-1791

VL - 16

SP - 217

EP - 220

JO - Nuclear Materials and Energy

JF - Nuclear Materials and Energy

ER -

Surface or bulk He existence effect on deuterium retention in Fe ion damaged W

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Keywords

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