The effect of fission-energy Xe ion irradiation on dissolution of UO2 thin films

A.J. Popel; V.G. Petrov; V.A. Lebedev; J. Day; S.N. Kalmykov; R. Springell; T.B. Scott; I. Farnan

doi:10.1016/j.jallcom.2017.05.084

The effect of fission-energy Xe ion irradiation on dissolution of UO2 thin films

A.J. Popel, V.G. Petrov, V.A. Lebedev, J. Day, S.N. Kalmykov, R. Springell, T.B. Scott, I. Farnan

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Abstract

Abstract The aim of this work was to study the effect of fission fragment damage on the dissolution of UO2 thin films in water. For this purpose, thin films of UO2 on LSAT (Al10La3O51Sr14Ta7) substrates were produced and irradiated by 92 MeV 129Xe23+ ions to a fluence of 4.8 × 1015 ions/cm2 to simulate the fission damage and induce chemical mixing that occur within nuclear fuels. The dissolution experiment was conducted under a nitrogen atmosphere (200–900 O2 ppm in N2) to study the effect of the induced irradiation damage and mixing on the dissolution of the UO2 matrix. The irradiated samples showed a decrease in the amount of dissolved uranium, as compared to the corresponding unirradiated samples. This was ascribed to the irradiation-induced chemical mixing of the UO2 films with the substrate elements, which resulted in stabilisation of the UO2 matrix and increased its aqueous durability. Secondary phases were also observed on the surface of the UO2 films after the dissolution experiment.

Original language	English
Pages (from-to)	586-592
Journal	Journal of Alloys and Compounds
Volume	721
Early online date	10 May 2017
DOIs	https://doi.org/10.1016/j.jallcom.2017.05.084
Publication status	E-pub ahead of print - 10 May 2017

Keywords

UO2
Ion irradiation
Radiation damage
Ion-beam-induced mixing
Dissolution
Secondary phases

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10.1016/j.jallcom.2017.05.084

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title = "The effect of fission-energy Xe ion irradiation on dissolution of UO2 thin films",

abstract = "Abstract The aim of this work was to study the effect of fission fragment damage on the dissolution of UO2 thin films in water. For this purpose, thin films of UO2 on LSAT (Al10La3O51Sr14Ta7) substrates were produced and irradiated by 92 MeV 129Xe23+ ions to a fluence of 4.8 × 1015 ions/cm2 to simulate the fission damage and induce chemical mixing that occur within nuclear fuels. The dissolution experiment was conducted under a nitrogen atmosphere (200–900 O2 ppm in N2) to study the effect of the induced irradiation damage and mixing on the dissolution of the UO2 matrix. The irradiated samples showed a decrease in the amount of dissolved uranium, as compared to the corresponding unirradiated samples. This was ascribed to the irradiation-induced chemical mixing of the UO2 films with the substrate elements, which resulted in stabilisation of the UO2 matrix and increased its aqueous durability. Secondary phases were also observed on the surface of the UO2 films after the dissolution experiment.",

keywords = "UO2, Ion irradiation, Radiation damage, Ion-beam-induced mixing, Dissolution, Secondary phases",

author = "A.J. Popel and V.G. Petrov and V.A. Lebedev and J. Day and S.N. Kalmykov and R. Springell and T.B. Scott and I. Farnan",

year = "2017",

month = may,

day = "10",

doi = "10.1016/j.jallcom.2017.05.084",

language = "English",

volume = "721",

pages = "586--592",

journal = "Journal of Alloys and Compounds",

issn = "0925-8388",

publisher = "Amsterdam:Elsevier",

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TY - JOUR

T1 - The effect of fission-energy Xe ion irradiation on dissolution of UO2 thin films

AU - Popel, A.J.

AU - Petrov, V.G.

AU - Lebedev, V.A.

AU - Day, J.

AU - Kalmykov, S.N.

AU - Springell, R.

AU - Scott, T.B.

AU - Farnan, I.

PY - 2017/5/10

Y1 - 2017/5/10

N2 - Abstract The aim of this work was to study the effect of fission fragment damage on the dissolution of UO2 thin films in water. For this purpose, thin films of UO2 on LSAT (Al10La3O51Sr14Ta7) substrates were produced and irradiated by 92 MeV 129Xe23+ ions to a fluence of 4.8 × 1015 ions/cm2 to simulate the fission damage and induce chemical mixing that occur within nuclear fuels. The dissolution experiment was conducted under a nitrogen atmosphere (200–900 O2 ppm in N2) to study the effect of the induced irradiation damage and mixing on the dissolution of the UO2 matrix. The irradiated samples showed a decrease in the amount of dissolved uranium, as compared to the corresponding unirradiated samples. This was ascribed to the irradiation-induced chemical mixing of the UO2 films with the substrate elements, which resulted in stabilisation of the UO2 matrix and increased its aqueous durability. Secondary phases were also observed on the surface of the UO2 films after the dissolution experiment.

AB - Abstract The aim of this work was to study the effect of fission fragment damage on the dissolution of UO2 thin films in water. For this purpose, thin films of UO2 on LSAT (Al10La3O51Sr14Ta7) substrates were produced and irradiated by 92 MeV 129Xe23+ ions to a fluence of 4.8 × 1015 ions/cm2 to simulate the fission damage and induce chemical mixing that occur within nuclear fuels. The dissolution experiment was conducted under a nitrogen atmosphere (200–900 O2 ppm in N2) to study the effect of the induced irradiation damage and mixing on the dissolution of the UO2 matrix. The irradiated samples showed a decrease in the amount of dissolved uranium, as compared to the corresponding unirradiated samples. This was ascribed to the irradiation-induced chemical mixing of the UO2 films with the substrate elements, which resulted in stabilisation of the UO2 matrix and increased its aqueous durability. Secondary phases were also observed on the surface of the UO2 films after the dissolution experiment.

KW - UO2

KW - Ion irradiation

KW - Radiation damage

KW - Ion-beam-induced mixing

KW - Dissolution

KW - Secondary phases

U2 - 10.1016/j.jallcom.2017.05.084

DO - 10.1016/j.jallcom.2017.05.084

M3 - Article (Academic Journal)

VL - 721

SP - 586

EP - 592

JO - Journal of Alloys and Compounds

JF - Journal of Alloys and Compounds

SN - 0925-8388

ER -