Effect of He Implantation on the Microstructure of Zircaloy-4 Studied Using In Situ TEM

Matheus Araujo Tunes, Robert Harrison, Graeme Greaves, Jonathan Hinks, Stephen Donnelly

Research output: Contribution to journalArticle

6 Citations (Scopus)

Abstract

Zirconium alloys are of great importance to the nuclear industry as they have been widely used as cladding materials in light-water reactors since the 1960s. This work examines the behaviour of these alloys under He ion implantation for the purposes of developing understanding of the fundamental processes behind their response to irradiation. Characterization of zircaloy-4 samples using TEM with in situ 6 keV He irradiation up to a fluence of 2.7×1017ions·cm−2 in the temperature range of 298 to 1148 K has been performed. Ordered arrays of He bubbles were observed at 473 and 1148 K at a fluence of 1.7×1017ions·cm−2 in αZr, the hexagonal compact (HCP) and in βZr, the body centred cubic (BCC) phases, respectively. In addition, the dissolution behaviour of cubic Zr hydrides under He irradiation has been investigated.
LanguageEnglish
Pages230-238
Number of pages9
JournalJournal of Nuclear Materials
Volume493
Early online date13 Jun 2017
DOIs
Publication statusPublished - Sep 2017

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implantation
Irradiation
Transmission electron microscopy
transmission electron microscopy
microstructure
Microstructure
irradiation
fluence
light water reactors
zirconium alloys
Zirconium alloys
Nuclear industry
Light water reactors
Hydrides
Ion implantation
hydrides
ion implantation
dissolving
Dissolution
bubbles

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title = "Effect of He Implantation on the Microstructure of Zircaloy-4 Studied Using In Situ TEM",
abstract = "Zirconium alloys are of great importance to the nuclear industry as they have been widely used as cladding materials in light-water reactors since the 1960s. This work examines the behaviour of these alloys under He ion implantation for the purposes of developing understanding of the fundamental processes behind their response to irradiation. Characterization of zircaloy-4 samples using TEM with in situ 6 keV He irradiation up to a fluence of 2.7×1017ions·cm−2 in the temperature range of 298 to 1148 K has been performed. Ordered arrays of He bubbles were observed at 473 and 1148 K at a fluence of 1.7×1017ions·cm−2 in αZr, the hexagonal compact (HCP) and in βZr, the body centred cubic (BCC) phases, respectively. In addition, the dissolution behaviour of cubic Zr hydrides under He irradiation has been investigated.",
keywords = "Radiation damage, Zirconium alloys, In situ ion irradiation, Hydrides, Bubble lattices",
author = "Tunes, {Matheus Araujo} and Robert Harrison and Graeme Greaves and Jonathan Hinks and Stephen Donnelly",
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journal = "Journal of Nuclear Materials",
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publisher = "Elsevier",

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Effect of He Implantation on the Microstructure of Zircaloy-4 Studied Using In Situ TEM. / Tunes, Matheus Araujo; Harrison, Robert; Greaves, Graeme; Hinks, Jonathan; Donnelly, Stephen.

In: Journal of Nuclear Materials, Vol. 493, 09.2017, p. 230-238.

Research output: Contribution to journalArticle

TY - JOUR

T1 - Effect of He Implantation on the Microstructure of Zircaloy-4 Studied Using In Situ TEM

AU - Tunes, Matheus Araujo

AU - Harrison, Robert

AU - Greaves, Graeme

AU - Hinks, Jonathan

AU - Donnelly, Stephen

PY - 2017/9

Y1 - 2017/9

N2 - Zirconium alloys are of great importance to the nuclear industry as they have been widely used as cladding materials in light-water reactors since the 1960s. This work examines the behaviour of these alloys under He ion implantation for the purposes of developing understanding of the fundamental processes behind their response to irradiation. Characterization of zircaloy-4 samples using TEM with in situ 6 keV He irradiation up to a fluence of 2.7×1017ions·cm−2 in the temperature range of 298 to 1148 K has been performed. Ordered arrays of He bubbles were observed at 473 and 1148 K at a fluence of 1.7×1017ions·cm−2 in αZr, the hexagonal compact (HCP) and in βZr, the body centred cubic (BCC) phases, respectively. In addition, the dissolution behaviour of cubic Zr hydrides under He irradiation has been investigated.

AB - Zirconium alloys are of great importance to the nuclear industry as they have been widely used as cladding materials in light-water reactors since the 1960s. This work examines the behaviour of these alloys under He ion implantation for the purposes of developing understanding of the fundamental processes behind their response to irradiation. Characterization of zircaloy-4 samples using TEM with in situ 6 keV He irradiation up to a fluence of 2.7×1017ions·cm−2 in the temperature range of 298 to 1148 K has been performed. Ordered arrays of He bubbles were observed at 473 and 1148 K at a fluence of 1.7×1017ions·cm−2 in αZr, the hexagonal compact (HCP) and in βZr, the body centred cubic (BCC) phases, respectively. In addition, the dissolution behaviour of cubic Zr hydrides under He irradiation has been investigated.

KW - Radiation damage

KW - Zirconium alloys

KW - In situ ion irradiation

KW - Hydrides

KW - Bubble lattices

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JO - Journal of Nuclear Materials

T2 - Journal of Nuclear Materials

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SN - 0022-3115

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