Influence of dynamic annealing of irradiation defects on the deuterium retention behaviors in tungsten irradiated with neutron

Makoto Kobayashi; Masashi Shimada; Chase N. Taylor; Dean Buchenauer; Robert Kolasinski; Takaaki Koyanagi; Yuji Nobuta; Yuji Hatano; Yasuhisa Oya

doi:10.1016/j.fusengdes.2019.03.003

Influence of dynamic annealing of irradiation defects on the deuterium retention behaviors in tungsten irradiated with neutron

Makoto Kobayashi^*, Masashi Shimada, Chase N. Taylor, Dean Buchenauer, Robert Kolasinski, Takaaki Koyanagi, Yuji Nobuta, Yuji Hatano, Yasuhisa Oya

^*Corresponding author for this work

Hydrogen Isotope Research Center, Organization for Promotion of Research

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

9 Scopus citations

Abstract

Tungsten (W) samples were damaged by neutron and 6.4 MeV Fe-ion irradiation above 1000 K simulating the divertor operation temperature. Deuterium (D) retention properties were examined by decorating the damaged W with D and subsequent thermal desorption spectroscopy (TDS) measurements. Vacancy clusters were the major D trapping site in the W irradiated with Fe-ion at 873 K, although D retention by vacancy clusters decreased in the W irradiated with Fe-ion at 1173 K due to dynamic annealing. The D de-trapping activation energy from vacancy clusters was found to be 1.85 eV. D retention in neutron damage W was larger than that damaged by Fe-ion due to the uniform distribution of irradiation defects. The D desorption behaviors from neutron damaged W was simulated well by assuming the D de-trapping activation energy to be 1.52 eV.

Original language	English
Pages (from-to)	1624-1627
Number of pages	4
Journal	Fusion Engineering and Design
Volume	146
DOIs	https://doi.org/10.1016/j.fusengdes.2019.03.003
State	Published - 2019/09

Keywords

Divertor
Neutron
TDS
Tungsten

ASJC Scopus subject areas

Civil and Structural Engineering
Nuclear Energy and Engineering
General Materials Science
Mechanical Engineering

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10.1016/j.fusengdes.2019.03.003

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@article{0b84369eb6204cb3aa576639b8b70d45,

title = "Influence of dynamic annealing of irradiation defects on the deuterium retention behaviors in tungsten irradiated with neutron",

abstract = "Tungsten (W) samples were damaged by neutron and 6.4 MeV Fe-ion irradiation above 1000 K simulating the divertor operation temperature. Deuterium (D) retention properties were examined by decorating the damaged W with D and subsequent thermal desorption spectroscopy (TDS) measurements. Vacancy clusters were the major D trapping site in the W irradiated with Fe-ion at 873 K, although D retention by vacancy clusters decreased in the W irradiated with Fe-ion at 1173 K due to dynamic annealing. The D de-trapping activation energy from vacancy clusters was found to be 1.85 eV. D retention in neutron damage W was larger than that damaged by Fe-ion due to the uniform distribution of irradiation defects. The D desorption behaviors from neutron damaged W was simulated well by assuming the D de-trapping activation energy to be 1.52 eV.",

keywords = "Divertor, Neutron, TDS, Tungsten",

author = "Makoto Kobayashi and Masashi Shimada and Taylor, {Chase N.} and Dean Buchenauer and Robert Kolasinski and Takaaki Koyanagi and Yuji Nobuta and Yuji Hatano and Yasuhisa Oya",

note = "Publisher Copyright: {\textcopyright} 2019 Elsevier B.V.",

year = "2019",

month = sep,

doi = "10.1016/j.fusengdes.2019.03.003",

language = "英語",

volume = "146",

pages = "1624--1627",

journal = "Fusion Engineering and Design",

issn = "0920-3796",

publisher = "Elsevier B.V.",

}

TY - JOUR

T1 - Influence of dynamic annealing of irradiation defects on the deuterium retention behaviors in tungsten irradiated with neutron

AU - Kobayashi, Makoto

AU - Shimada, Masashi

AU - Taylor, Chase N.

AU - Buchenauer, Dean

AU - Kolasinski, Robert

AU - Koyanagi, Takaaki

AU - Nobuta, Yuji

AU - Hatano, Yuji

AU - Oya, Yasuhisa

PY - 2019/9

Y1 - 2019/9

N2 - Tungsten (W) samples were damaged by neutron and 6.4 MeV Fe-ion irradiation above 1000 K simulating the divertor operation temperature. Deuterium (D) retention properties were examined by decorating the damaged W with D and subsequent thermal desorption spectroscopy (TDS) measurements. Vacancy clusters were the major D trapping site in the W irradiated with Fe-ion at 873 K, although D retention by vacancy clusters decreased in the W irradiated with Fe-ion at 1173 K due to dynamic annealing. The D de-trapping activation energy from vacancy clusters was found to be 1.85 eV. D retention in neutron damage W was larger than that damaged by Fe-ion due to the uniform distribution of irradiation defects. The D desorption behaviors from neutron damaged W was simulated well by assuming the D de-trapping activation energy to be 1.52 eV.

AB - Tungsten (W) samples were damaged by neutron and 6.4 MeV Fe-ion irradiation above 1000 K simulating the divertor operation temperature. Deuterium (D) retention properties were examined by decorating the damaged W with D and subsequent thermal desorption spectroscopy (TDS) measurements. Vacancy clusters were the major D trapping site in the W irradiated with Fe-ion at 873 K, although D retention by vacancy clusters decreased in the W irradiated with Fe-ion at 1173 K due to dynamic annealing. The D de-trapping activation energy from vacancy clusters was found to be 1.85 eV. D retention in neutron damage W was larger than that damaged by Fe-ion due to the uniform distribution of irradiation defects. The D desorption behaviors from neutron damaged W was simulated well by assuming the D de-trapping activation energy to be 1.52 eV.

KW - Divertor

KW - Neutron

KW - TDS

KW - Tungsten

UR - http://www.scopus.com/inward/record.url?scp=85063464412&partnerID=8YFLogxK

U2 - 10.1016/j.fusengdes.2019.03.003

DO - 10.1016/j.fusengdes.2019.03.003

M3 - 学術論文

AN - SCOPUS:85063464412

SN - 0920-3796

VL - 146

SP - 1624

EP - 1627

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

ER -

Influence of dynamic annealing of irradiation defects on the deuterium retention behaviors in tungsten irradiated with neutron

Abstract

Keywords

ASJC Scopus subject areas

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