Temperature threshold for preferential bubble formation on grain boundaries in tungsten under in-situ helium irradiation

O. El-Atwani; W. S. Cunningham; D. Perez; E. Martinez; J. R. Trelewicz; M. Li; S. A. Maloy

doi:10.1016/j.scriptamat.2020.01.013

Temperature threshold for preferential bubble formation on grain boundaries in tungsten under in-situ helium irradiation

O. El-Atwani
, W. S. Cunningham
, D. Perez
, E. Martinez
, J. R. Trelewicz
, M. Li
, S. A. Maloy

Materials Science and Engineering

Los Alamos National Laboratory Materials Science and Technology Division
Stony Brook University
Los Alamos National Laboratory Theoretical Division
Argonne National Laboratory

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

52 Scopus citations

Abstract

Understanding a material's radiation tolerance requires examining its performance under different irradiation conditions. Here, we investigate the radiation tolerance in terms of helium bubble damage in tungsten irradiated in-situ with 16 keV helium at 1073 K and 1223 K. Damage evolution represented by helium bubble density, size and total change in volume in the grain matrices and the grain boundaries are quantified as a function of fluence. Preferential large bubble formation and a higher change in volume on the grain boundaries occurred at 1223 K, suggesting faster migration of certain helium-vacancy complexes as confirmed by a diffusion-reaction model.

Original language	English
Pages (from-to)	6-10
Number of pages	5
Journal	Scripta Materialia
Volume	180
DOIs	https://doi.org/10.1016/j.scriptamat.2020.01.013
State	Published - Apr 15 2020

Keywords

Electron microscopy
Grain boundaries
Helium-vacancy complexes
Implantation
In-situ

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10.1016/j.scriptamat.2020.01.013

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title = "Temperature threshold for preferential bubble formation on grain boundaries in tungsten under in-situ helium irradiation",

abstract = "Understanding a material's radiation tolerance requires examining its performance under different irradiation conditions. Here, we investigate the radiation tolerance in terms of helium bubble damage in tungsten irradiated in-situ with 16 keV helium at 1073 K and 1223 K. Damage evolution represented by helium bubble density, size and total change in volume in the grain matrices and the grain boundaries are quantified as a function of fluence. Preferential large bubble formation and a higher change in volume on the grain boundaries occurred at 1223 K, suggesting faster migration of certain helium-vacancy complexes as confirmed by a diffusion-reaction model.",

keywords = "Electron microscopy, Grain boundaries, Helium-vacancy complexes, Implantation, In-situ",

author = "O. El-Atwani and Cunningham, \{W. S.\} and D. Perez and E. Martinez and Trelewicz, \{J. R.\} and M. Li and Maloy, \{S. A.\}",

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doi = "10.1016/j.scriptamat.2020.01.013",

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T1 - Temperature threshold for preferential bubble formation on grain boundaries in tungsten under in-situ helium irradiation

AU - El-Atwani, O.

AU - Cunningham, W. S.

AU - Perez, D.

AU - Martinez, E.

AU - Trelewicz, J. R.

AU - Li, M.

AU - Maloy, S. A.

PY - 2020/4/15

Y1 - 2020/4/15

N2 - Understanding a material's radiation tolerance requires examining its performance under different irradiation conditions. Here, we investigate the radiation tolerance in terms of helium bubble damage in tungsten irradiated in-situ with 16 keV helium at 1073 K and 1223 K. Damage evolution represented by helium bubble density, size and total change in volume in the grain matrices and the grain boundaries are quantified as a function of fluence. Preferential large bubble formation and a higher change in volume on the grain boundaries occurred at 1223 K, suggesting faster migration of certain helium-vacancy complexes as confirmed by a diffusion-reaction model.

AB - Understanding a material's radiation tolerance requires examining its performance under different irradiation conditions. Here, we investigate the radiation tolerance in terms of helium bubble damage in tungsten irradiated in-situ with 16 keV helium at 1073 K and 1223 K. Damage evolution represented by helium bubble density, size and total change in volume in the grain matrices and the grain boundaries are quantified as a function of fluence. Preferential large bubble formation and a higher change in volume on the grain boundaries occurred at 1223 K, suggesting faster migration of certain helium-vacancy complexes as confirmed by a diffusion-reaction model.

KW - Electron microscopy

KW - Grain boundaries

KW - Helium-vacancy complexes

KW - Implantation

KW - In-situ

UR - https://www.scopus.com/pages/publications/85078295255

U2 - 10.1016/j.scriptamat.2020.01.013

DO - 10.1016/j.scriptamat.2020.01.013

M3 - Article

AN - SCOPUS:85078295255

SN - 1359-6462

VL - 180

SP - 6

EP - 10

JO - Scripta Materialia

JF - Scripta Materialia

ER -

Temperature threshold for preferential bubble formation on grain boundaries in tungsten under in-situ helium irradiation

Abstract

Keywords

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