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

doi:10.1016/j.jnucmat.2017.06.012

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 journal › Article › peer-review

22 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.

Original language	English
Pages (from-to)	230-238
Number of pages	9
Journal	Journal of Nuclear Materials
Volume	493
Early online date	13 Jun 2017
DOIs	https://doi.org/10.1016/j.jnucmat.2017.06.012
Publication status	Published - Sep 2017

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10.1016/j.jnucmat.2017.06.012Licence: Unspecified

http://eprints.hud.ac.uk/id/eprint/32270Licence: CC BY-NC-ND

Cite this

@article{84995a8563584eb5844350b22af3a9d7,

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",

year = "2017",

month = sep,

doi = "10.1016/j.jnucmat.2017.06.012",

language = "English",

volume = "493",

pages = "230--238",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier",

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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

UR - https://www.journals.elsevier.com/journal-of-nuclear-materials

U2 - 10.1016/j.jnucmat.2017.06.012

DO - 10.1016/j.jnucmat.2017.06.012

M3 - Article

VL - 493

SP - 230

EP - 238

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

ER -

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

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

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World Class Materials Facilities at the University of Huddersfield

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