Structural defect accumulation in tungsten and tungsten-5wt.% tantalum under incremental proton damage

I. Ipatova; R. W. Harrison; P. T. Wady; S. M. Shubeita; D. Terentyev; S. E. Donnelly; E. Jimenez-Melero

doi:10.1016/j.jnucmat.2017.11.030

Structural defect accumulation in tungsten and tungsten-5wt.% tantalum under incremental proton damage

I. Ipatova^*, R. W. Harrison, P. T. Wady, S. M. Shubeita, D. Terentyev, S. E. Donnelly, E. Jimenez-Melero

^*Corresponding author for this work

Metallurgy and Materials

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

Abstract

We have performed proton irradiation of W and W-5wt.%Ta materials at 350 °C with a step-wise damage level increase up to 0.7 dpa and using two beam energies, namely 40 keV and 3 MeV, in order to probe the accumulation of radiation-induced lattice damage in these materials. Interstitial-type a/2 <111> dislocation loops are formed under irradiation, and their size increases in W-5Ta up to a loop width of 21 ± 4 nm at 0.3 dpa, where loop saturation takes place. In contrast, the loop length in W increases progressively up to 183 ± 50 nm at 0.7 dpa, whereas the loop width remains relatively constant at 29 ± 7 nm at >0.3 dpa, giving rise to dislocation strings. The dislocation loops and tangles are observed in both materials examined after a 3 MeV proton irradiation at 350 °C. Ta doping delays the evolution of radiation-induced dislocation structures in W, and can consequently impact the hydrogen isotope retention under plasma exposure.

Original language	English
Pages (from-to)	329-335
Number of pages	7
Journal	Journal of Nuclear Materials
Volume	501
DOIs	https://doi.org/10.1016/j.jnucmat.2017.11.030
Publication status	Published - 1 Apr 2018

Bibliographical note

Funding Information:
The work described was supported by the Dalton Cumbrian Facility Project, a joint facility of the University of Manchester and the Nuclear Decommissioning Authority . We thank A.D. Smith and N. Mason for their assistance during the proton irradiation experiment. We acknowledge the support of EPSRC for the development of the MIAMI-1 Facility ( EP/E017266/1 ).

Publisher Copyright:
© 2018 Elsevier B.V.

Keywords

Binary alloys
Dislocation analysis
Proton irradiation
Refractory metals
Transmission electron microscopy

ASJC Scopus subject areas

Nuclear and High Energy Physics
General Materials Science
Nuclear Energy and Engineering

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10.1016/j.jnucmat.2017.11.030

Cite this

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title = "Structural defect accumulation in tungsten and tungsten-5wt.% tantalum under incremental proton damage",

abstract = "We have performed proton irradiation of W and W-5wt.%Ta materials at 350 °C with a step-wise damage level increase up to 0.7 dpa and using two beam energies, namely 40 keV and 3 MeV, in order to probe the accumulation of radiation-induced lattice damage in these materials. Interstitial-type a/2 <111> dislocation loops are formed under irradiation, and their size increases in W-5Ta up to a loop width of 21 ± 4 nm at 0.3 dpa, where loop saturation takes place. In contrast, the loop length in W increases progressively up to 183 ± 50 nm at 0.7 dpa, whereas the loop width remains relatively constant at 29 ± 7 nm at >0.3 dpa, giving rise to dislocation strings. The dislocation loops and tangles are observed in both materials examined after a 3 MeV proton irradiation at 350 °C. Ta doping delays the evolution of radiation-induced dislocation structures in W, and can consequently impact the hydrogen isotope retention under plasma exposure.",

keywords = "Binary alloys, Dislocation analysis, Proton irradiation, Refractory metals, Transmission electron microscopy",

author = "I. Ipatova and Harrison, {R. W.} and Wady, {P. T.} and Shubeita, {S. M.} and D. Terentyev and Donnelly, {S. E.} and E. Jimenez-Melero",

note = "Funding Information: The work described was supported by the Dalton Cumbrian Facility Project, a joint facility of the University of Manchester and the Nuclear Decommissioning Authority . We thank A.D. Smith and N. Mason for their assistance during the proton irradiation experiment. We acknowledge the support of EPSRC for the development of the MIAMI-1 Facility ( EP/E017266/1 ). Publisher Copyright: {\textcopyright} 2018 Elsevier B.V.",

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doi = "10.1016/j.jnucmat.2017.11.030",

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T1 - Structural defect accumulation in tungsten and tungsten-5wt.% tantalum under incremental proton damage

AU - Ipatova, I.

AU - Harrison, R. W.

AU - Wady, P. T.

AU - Shubeita, S. M.

AU - Terentyev, D.

AU - Donnelly, S. E.

AU - Jimenez-Melero, E.

N1 - Funding Information: The work described was supported by the Dalton Cumbrian Facility Project, a joint facility of the University of Manchester and the Nuclear Decommissioning Authority . We thank A.D. Smith and N. Mason for their assistance during the proton irradiation experiment. We acknowledge the support of EPSRC for the development of the MIAMI-1 Facility ( EP/E017266/1 ). Publisher Copyright: © 2018 Elsevier B.V.

PY - 2018/4/1

Y1 - 2018/4/1

N2 - We have performed proton irradiation of W and W-5wt.%Ta materials at 350 °C with a step-wise damage level increase up to 0.7 dpa and using two beam energies, namely 40 keV and 3 MeV, in order to probe the accumulation of radiation-induced lattice damage in these materials. Interstitial-type a/2 <111> dislocation loops are formed under irradiation, and their size increases in W-5Ta up to a loop width of 21 ± 4 nm at 0.3 dpa, where loop saturation takes place. In contrast, the loop length in W increases progressively up to 183 ± 50 nm at 0.7 dpa, whereas the loop width remains relatively constant at 29 ± 7 nm at >0.3 dpa, giving rise to dislocation strings. The dislocation loops and tangles are observed in both materials examined after a 3 MeV proton irradiation at 350 °C. Ta doping delays the evolution of radiation-induced dislocation structures in W, and can consequently impact the hydrogen isotope retention under plasma exposure.

AB - We have performed proton irradiation of W and W-5wt.%Ta materials at 350 °C with a step-wise damage level increase up to 0.7 dpa and using two beam energies, namely 40 keV and 3 MeV, in order to probe the accumulation of radiation-induced lattice damage in these materials. Interstitial-type a/2 <111> dislocation loops are formed under irradiation, and their size increases in W-5Ta up to a loop width of 21 ± 4 nm at 0.3 dpa, where loop saturation takes place. In contrast, the loop length in W increases progressively up to 183 ± 50 nm at 0.7 dpa, whereas the loop width remains relatively constant at 29 ± 7 nm at >0.3 dpa, giving rise to dislocation strings. The dislocation loops and tangles are observed in both materials examined after a 3 MeV proton irradiation at 350 °C. Ta doping delays the evolution of radiation-induced dislocation structures in W, and can consequently impact the hydrogen isotope retention under plasma exposure.

KW - Binary alloys

KW - Dislocation analysis

KW - Proton irradiation

KW - Refractory metals

KW - Transmission electron microscopy

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DO - 10.1016/j.jnucmat.2017.11.030

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JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

ER -

Structural defect accumulation in tungsten and tungsten-5wt.% tantalum under incremental proton damage

Abstract

Bibliographical note

Keywords

ASJC Scopus subject areas

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