Deuterium Permeation Behavior in Fe Ion Damaged Tungsten Studied by Gas-Driven Permeation Method

Mingzhong Zhao; Moeko Nakata; Fei Sun; Yuji Hatano; Yoji Someya; Kenji Tobita; Yasuhisa Oya

doi:10.1080/15361055.2019.1705727

Deuterium Permeation Behavior in Fe Ion Damaged Tungsten Studied by Gas-Driven Permeation Method

Mingzhong Zhao, Moeko Nakata, Fei Sun, Yuji Hatano, Yoji Someya, Kenji Tobita, Yasuhisa Oya

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

2 Citations (Scopus)

Abstract

The deuterium (D) permeation behavior for 1 displacement per atom Fe²⁺ damaged tungsten (W) was studied by the gas-driven permeation method and compared with undamaged W. The results of thermal desorption spectroscopy showed that dislocation loops and voids were formed in damaged W. It was found that the D permeation behavior in W was affected by irradiation defects. The effective diffusivity and permeability in the damaged W were lower than that in undamaged W. However, the difference in effective diffusivity and permeability between the undamaged sample and the damaged sample was reduced with increasing the heating temperature. Under 965 K, which was enough for D detrapping from voids, the permeability for damaged W was consistent with that for undamaged W.

Original language	English
Pages (from-to)	246-251
Number of pages	6
Journal	Fusion Science and Technology
Volume	76
Issue number	3
DOIs	https://doi.org/10.1080/15361055.2019.1705727
Publication status	Published - 2020 Apr 2
Externally published	Yes

Keywords

Tungsten
gas-driven permeation
irradiation damage

ASJC Scopus subject areas

Civil and Structural Engineering
Nuclear and High Energy Physics
Nuclear Energy and Engineering
Materials Science(all)
Mechanical Engineering

Access to Document

10.1080/15361055.2019.1705727

Cite this

@article{ed3a6b1742b9478e820148eb9018540b,

title = "Deuterium Permeation Behavior in Fe Ion Damaged Tungsten Studied by Gas-Driven Permeation Method",

abstract = "The deuterium (D) permeation behavior for 1 displacement per atom Fe2+ damaged tungsten (W) was studied by the gas-driven permeation method and compared with undamaged W. The results of thermal desorption spectroscopy showed that dislocation loops and voids were formed in damaged W. It was found that the D permeation behavior in W was affected by irradiation defects. The effective diffusivity and permeability in the damaged W were lower than that in undamaged W. However, the difference in effective diffusivity and permeability between the undamaged sample and the damaged sample was reduced with increasing the heating temperature. Under 965 K, which was enough for D detrapping from voids, the permeability for damaged W was consistent with that for undamaged W.",

keywords = "Tungsten, gas-driven permeation, irradiation damage",

author = "Mingzhong Zhao and Moeko Nakata and Fei Sun and Yuji Hatano and Yoji Someya and Kenji Tobita and Yasuhisa Oya",

note = "Funding Information: This work is supported by a QST collaboration program. TIARA at QST performed the Fe ion irradiation under the collaborative research project at the University of Tokyo, Nuclear Professional School, School of Engineering. This work is also performed with the support and under the auspices of the National Institute for Fusion Science (NIFS)–University of Toyama bilateral Collaboration Research Program (NIFS19KUHR055). Funding Information: This work is supported by a QST collaboration program. TIARA at QST performed the Fe ion irradiation under the collaborative research project at the University of Tokyo, Nuclear Professional School, School of Engineering. This work is also performed with the support and under the auspices of the National Institute for Fusion Science (NIFS)?University of Toyama bilateral Collaboration Research Program (NIFS19KUHR055). Publisher Copyright: {\textcopyright} 2020, {\textcopyright} 2020 American Nuclear Society.",

year = "2020",

month = apr,

day = "2",

doi = "10.1080/15361055.2019.1705727",

language = "English",

volume = "76",

pages = "246--251",

journal = "Fusion Science and Technology",

issn = "1536-1055",

publisher = "American Nuclear Society",

number = "3",

}

TY - JOUR

T1 - Deuterium Permeation Behavior in Fe Ion Damaged Tungsten Studied by Gas-Driven Permeation Method

AU - Zhao, Mingzhong

AU - Nakata, Moeko

AU - Sun, Fei

AU - Hatano, Yuji

AU - Someya, Yoji

AU - Tobita, Kenji

AU - Oya, Yasuhisa

N1 - Funding Information: This work is supported by a QST collaboration program. TIARA at QST performed the Fe ion irradiation under the collaborative research project at the University of Tokyo, Nuclear Professional School, School of Engineering. This work is also performed with the support and under the auspices of the National Institute for Fusion Science (NIFS)–University of Toyama bilateral Collaboration Research Program (NIFS19KUHR055). Funding Information: This work is supported by a QST collaboration program. TIARA at QST performed the Fe ion irradiation under the collaborative research project at the University of Tokyo, Nuclear Professional School, School of Engineering. This work is also performed with the support and under the auspices of the National Institute for Fusion Science (NIFS)?University of Toyama bilateral Collaboration Research Program (NIFS19KUHR055). Publisher Copyright: © 2020, © 2020 American Nuclear Society.

PY - 2020/4/2

Y1 - 2020/4/2

N2 - The deuterium (D) permeation behavior for 1 displacement per atom Fe2+ damaged tungsten (W) was studied by the gas-driven permeation method and compared with undamaged W. The results of thermal desorption spectroscopy showed that dislocation loops and voids were formed in damaged W. It was found that the D permeation behavior in W was affected by irradiation defects. The effective diffusivity and permeability in the damaged W were lower than that in undamaged W. However, the difference in effective diffusivity and permeability between the undamaged sample and the damaged sample was reduced with increasing the heating temperature. Under 965 K, which was enough for D detrapping from voids, the permeability for damaged W was consistent with that for undamaged W.

AB - The deuterium (D) permeation behavior for 1 displacement per atom Fe2+ damaged tungsten (W) was studied by the gas-driven permeation method and compared with undamaged W. The results of thermal desorption spectroscopy showed that dislocation loops and voids were formed in damaged W. It was found that the D permeation behavior in W was affected by irradiation defects. The effective diffusivity and permeability in the damaged W were lower than that in undamaged W. However, the difference in effective diffusivity and permeability between the undamaged sample and the damaged sample was reduced with increasing the heating temperature. Under 965 K, which was enough for D detrapping from voids, the permeability for damaged W was consistent with that for undamaged W.

KW - Tungsten

KW - gas-driven permeation

KW - irradiation damage

UR - http://www.scopus.com/inward/record.url?scp=85078442841&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=85078442841&partnerID=8YFLogxK

U2 - 10.1080/15361055.2019.1705727

DO - 10.1080/15361055.2019.1705727

M3 - Article

AN - SCOPUS:85078442841

SN - 1536-1055

VL - 76

SP - 246

EP - 251

JO - Fusion Science and Technology

JF - Fusion Science and Technology

IS - 3

ER -

Deuterium Permeation Behavior in Fe Ion Damaged Tungsten Studied by Gas-Driven Permeation Method

Abstract

Keywords

ASJC Scopus subject areas

Access to Document

Other files and links

Fingerprint

Cite this