original ) (raw )The effect of fuel chemistry on UO2 dissolution
Brady Hanson
Journal of Nuclear Materials, 2016
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UO2 dissolution in Boom Clay conditions
Karel Lemmens
Journal of Nuclear Materials, 2003
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Radiolytic modelling of spent fuel oxidative dissolution mechanism. Calibration against UO2 dynamic leaching experiments
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Journal of Nuclear Materials, 2005
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Effect of H2O2, NaClO and Fe on the dissolution of unirradiated UO2 in NaCl 5 mol kg−1. Comparison with spent fuel dissolution experiments
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Journal of Nuclear Materials, 1996
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Oxidation and dissolution of UO2 in bicarbonate media: Implications for the spent nuclear fuel oxidative dissolution mechanism
F. Clarens
Journal of Nuclear Materials, 2005
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The effects of alpha-radiolysis on UO2 dissolution determined from batch experiments with 238Pu-doped UO2
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Journal of Nuclear Materials, 2005
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Uranium secondary phase formation during anoxic hydrothermal leaching processes of UO2 nuclear fuel
Herbert Thiele
Journal of Nuclear Materials, 2005
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Leaching patterns and secondary phase formation during unsaturated leaching of UO{sub 2} at 90{degrees}C
David Wronkiewicz
1991
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Effect of external gamma irradiation on dissolution of the spent UO2 fuel matrix
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Journal of Nuclear Materials, 2005
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The effect of ion irradiation on the dissolution of UO2 and UO2-based simulant fuel
Ian Farnan
Journal of Alloys and Compounds, 2018
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Effects of colloidal and dissolved silica on the dissolution of UO 2 nuclear fuel in groundwater leaching tests
Laura Aldave de las Heras
Journal of Radioanalytical and Nuclear Chemistry, 2000
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Interlaboratory comparison of UO {sub 2} dissolution rates
David Shoesmith
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Ten-year results from unsaturated drip tests with UO2 at 90°C: implications for the corrosion of spent nuclear fuel
David Wronkiewicz
Journal of Nuclear Materials, 1996
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Effect of cement water on UO2 solubility
Karel Lemmens
MRS Proceedings, 2014
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From Laboratory Experiments to a Geological Disposal Vault: Calculation of Used Nuclear Fuel Dissolution Rates
Miroslav Kolar
MRS Proceedings, 1997
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Leaching behaviour of unirradiated high temperature reactor (HTR) UO2–ThO2 mixed oxides fuel particles
Cyrille Alliot
Journal of Nuclear Materials, 2005
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Uranium release and secondary phase formation during unsaturated testing of UO2 at 90°C
David Wronkiewicz
Journal of Nuclear Materials, 1992
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Uraninite and UO2 in spent nuclear fuel: a comparison
Rodney C Ewing
Journal of Nuclear Materials, 1996
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A kinetic model for the stability of spent fuel matrix under oxic conditions
Lars Werme
Journal of Nuclear Materials, 1996
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Evolution of the uranium concentration in dissolution experiments with Cr-(Pu) doped UO2 in reducing conditions at SCK CEN
Aldo Naim
MRS Advances, 2021
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Solid surface evolution model to predict uranium release from unirradiated UO 2 and nuclear spent fuel dissolution under oxidizing conditions
Vicens Martí
Journal of Nuclear Materials, 1996
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Surface Mediated Processes in the Interaction of Spent Fuel or {alpha}-doped UO{sub 2} with H{sub 2}
Patrik Fors
2008
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Kinetics of dissolution of thorium and uranium doped britholite ceramics
Renaud Podor
Journal of Nuclear Materials, 2010
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The oxidative dissolution of unirradiated UO2 by hydrogen peroxide as a function of pH
F. Clarens
Journal of Nuclear Materials, 2005
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Surface Mediated Processes in the Interaction of Spent Fuel or alpha-doped UO2 with H2
Patrik Fors
MRS Proceedings, 2008
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Grain Boundary Corrosion and Alteration Phase Formation During the Oxidative Dissolution of UO2 Pellets
David Wronkiewicz
MRS Proceedings, 1996
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Effect of the thorium oxide content on the leaching of a mixed thorium-uranium oxide fuel
Mattias Thuvander
Journal of Radioanalytical and Nuclear Chemistry, 2022
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Release of Radiotoxic Elements from High Burn-Up UO2 and MOX Fuel in a Repository
joaquin cobos
MRS Proceedings, 2000
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Leaching of 53 MW/d kg U spent nuclear fuel in a flow-through reactor
J. Pablo
Radiochimica Acta, 2009
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Dissolution of intact UO2 pellet in batch and rotary dissolver conditions
jayendra gelatar
Journal of Radioanalytical and Nuclear Chemistry, 2014
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Oxidation and dissolution rates of UO 2 (s) in carbonate-rich solutions under external alpha irradiation and initially reducing conditions
Bernd Grambow
Radiochimica Acta, 2006
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Leaching Experiments on UOX and MOX Spent Fuel: Results and Prospects of the SF-ALE Project at SCK CEN
Karel Lemmens
2021
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Radiation induced dissolution of UO2 based nuclear fuel – A critical review of predictive modelling approaches
David Shoesmith
Journal of Nuclear Materials, 2012
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