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  • R Wilbraham Revised Uranium Manuscript - final

    Rights statement: This is the author’s version of a work that was accepted for publication in Journal of Nuclear Materials. Changes resulting from the publishing process, such as peer review, editing, corrections, structural formatting, and other quality control mechanisms may not be reflected in this document. Changes may have been made to this work since it was submitted for publication. A definitive version was subsequently published in Journal of Nuclear Materials, 464, 2016 DOI: 10.1016/j.jnucmat.2015.04.007

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The effect of hydrogen peroxide on uranium oxide films on 316L stainless steel

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The effect of hydrogen peroxide on uranium oxide films on 316L stainless steel. / Wilbraham, Richard; Boxall, Colin; Goddard, David T.; Taylor, Robin J.; Woodbury, Simon E.

In: Journal of Nuclear Materials, Vol. 464, 09.2015, p. 86-96.

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Wilbraham, Richard ; Boxall, Colin ; Goddard, David T. ; Taylor, Robin J. ; Woodbury, Simon E. / The effect of hydrogen peroxide on uranium oxide films on 316L stainless steel. In: Journal of Nuclear Materials. 2015 ; Vol. 464. pp. 86-96.

Bibtex

@article{9814231ab32e4ddf80a93a913893101a,
title = "The effect of hydrogen peroxide on uranium oxide films on 316L stainless steel",
abstract = "For the first time the effect of hydrogen peroxide on the dissolution of electrodeposited uranium oxide films on 316L stainless steel planchets (acting as simulant uranium-contaminated metal surfaces) has been studied. Analysis of the H2O2-mediated film dissolution processes via open circuit potentiometry, alpha counting and SEM/EDX imaging has shown that in near-neutral solutions of pH 6.1 and at [H2O2] 0.1 mol dm(-3) the uranium oxide film, again in analogy to common corrosion processes, behaves as if in a transpassive state and begins to dissolve.This transition from passive to transpassive behaviour in the effect of peroxide concentration on UO2 films has not hitherto been observed or explored, either in terms of corrosion processes or otherwise. Through consideration of thermodynamic solubility product and complex formation constant data, we attribute the transition to the formation of soluble uranyl-peroxide complexes under mildly alkaline, high [H2O2] conditions - a conclusion that has implications for the design of both acid minimal, metal ion oxidant-free decontamination strategies with low secondary waste arisings, and single step processes for spent nuclear fuel dissolution such as the Carbonate-based Oxidative Leaching (COL) process. (C) 2015 Elsevier B.V. All rights reserved.",
keywords = "CHEMICAL DECONTAMINATION PROCESS, OXIDATIVE DISSOLUTION, NUCLEAR-FUEL, ELECTROCHEMICAL REDUCTION, SURFACE ELECTROCHEMISTRY, ANODIC-DISSOLUTION, AQUEOUS CORROSION, PART II, UO2, DIOXIDE",
author = "Richard Wilbraham and Colin Boxall and Goddard, {David T.} and Taylor, {Robin J.} and Woodbury, {Simon E.}",
note = "This is the author{\textquoteright}s version of a work that was accepted for publication in Journal of Nuclear Materials. Changes resulting from the publishing process, such as peer review, editing, corrections, structural formatting, and other quality control mechanisms may not be reflected in this document. Changes may have been made to this work since it was submitted for publication. A definitive version was subsequently published in Journal of Nuclear Materials, 464, 2016 DOI: 10.1016/j.jnucmat.2015.04.007",
year = "2015",
month = sep,
doi = "10.1016/j.jnucmat.2015.04.007",
language = "English",
volume = "464",
pages = "86--96",
journal = "Journal of Nuclear Materials",
issn = "0022-3115",
publisher = "Elsevier Science B.V.",

}

RIS

TY - JOUR

T1 - The effect of hydrogen peroxide on uranium oxide films on 316L stainless steel

AU - Wilbraham, Richard

AU - Boxall, Colin

AU - Goddard, David T.

AU - Taylor, Robin J.

AU - Woodbury, Simon E.

N1 - This is the author’s version of a work that was accepted for publication in Journal of Nuclear Materials. Changes resulting from the publishing process, such as peer review, editing, corrections, structural formatting, and other quality control mechanisms may not be reflected in this document. Changes may have been made to this work since it was submitted for publication. A definitive version was subsequently published in Journal of Nuclear Materials, 464, 2016 DOI: 10.1016/j.jnucmat.2015.04.007

PY - 2015/9

Y1 - 2015/9

N2 - For the first time the effect of hydrogen peroxide on the dissolution of electrodeposited uranium oxide films on 316L stainless steel planchets (acting as simulant uranium-contaminated metal surfaces) has been studied. Analysis of the H2O2-mediated film dissolution processes via open circuit potentiometry, alpha counting and SEM/EDX imaging has shown that in near-neutral solutions of pH 6.1 and at [H2O2] 0.1 mol dm(-3) the uranium oxide film, again in analogy to common corrosion processes, behaves as if in a transpassive state and begins to dissolve.This transition from passive to transpassive behaviour in the effect of peroxide concentration on UO2 films has not hitherto been observed or explored, either in terms of corrosion processes or otherwise. Through consideration of thermodynamic solubility product and complex formation constant data, we attribute the transition to the formation of soluble uranyl-peroxide complexes under mildly alkaline, high [H2O2] conditions - a conclusion that has implications for the design of both acid minimal, metal ion oxidant-free decontamination strategies with low secondary waste arisings, and single step processes for spent nuclear fuel dissolution such as the Carbonate-based Oxidative Leaching (COL) process. (C) 2015 Elsevier B.V. All rights reserved.

AB - For the first time the effect of hydrogen peroxide on the dissolution of electrodeposited uranium oxide films on 316L stainless steel planchets (acting as simulant uranium-contaminated metal surfaces) has been studied. Analysis of the H2O2-mediated film dissolution processes via open circuit potentiometry, alpha counting and SEM/EDX imaging has shown that in near-neutral solutions of pH 6.1 and at [H2O2] 0.1 mol dm(-3) the uranium oxide film, again in analogy to common corrosion processes, behaves as if in a transpassive state and begins to dissolve.This transition from passive to transpassive behaviour in the effect of peroxide concentration on UO2 films has not hitherto been observed or explored, either in terms of corrosion processes or otherwise. Through consideration of thermodynamic solubility product and complex formation constant data, we attribute the transition to the formation of soluble uranyl-peroxide complexes under mildly alkaline, high [H2O2] conditions - a conclusion that has implications for the design of both acid minimal, metal ion oxidant-free decontamination strategies with low secondary waste arisings, and single step processes for spent nuclear fuel dissolution such as the Carbonate-based Oxidative Leaching (COL) process. (C) 2015 Elsevier B.V. All rights reserved.

KW - CHEMICAL DECONTAMINATION PROCESS

KW - OXIDATIVE DISSOLUTION

KW - NUCLEAR-FUEL

KW - ELECTROCHEMICAL REDUCTION

KW - SURFACE ELECTROCHEMISTRY

KW - ANODIC-DISSOLUTION

KW - AQUEOUS CORROSION

KW - PART II

KW - UO2

KW - DIOXIDE

U2 - 10.1016/j.jnucmat.2015.04.007

DO - 10.1016/j.jnucmat.2015.04.007

M3 - Journal article

VL - 464

SP - 86

EP - 96

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

ER -