Dissolution of spent nuclear fuel in carbonate–peroxide solution (original) (raw)
Effect of H2O2, NaClO and Fe on the dissolution of unirradiated UO2 in NaCl 5 mol kg−1. Comparison with spent fuel dissolution experiments
Ignasi Casas
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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Effect of external gamma irradiation on dissolution of the spent UO2 fuel matrix
BROUDIC KERIGUY
Journal of Nuclear Materials, 2005
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A multiphase interfacial model for the dissolution of spent nuclear fuel
James Jerden
Journal of Nuclear Materials, 2015
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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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Radiation Induced Spent Nuclear Fuel Dissolution under Deep Repository Conditions
KAZI MD MOSHARROF HOSSAIN
Environmental Science & Technology, 2007
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Dissolution of irradiated fuel: a radiolytic mass balance study
Lars Werme
Journal of Nuclear Materials, 1995
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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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Chapter 11: Chemistry/Electrochemistry of Spent Nuclear Fuel as a Wasteform
David Shoesmith
2013
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The oxidative dissolution mechanism of uranium dioxide. I. The effect of temperature in hydrogen carbonate medium
Javier Giménez
Geochimica Et Cosmochimica Acta, 1999
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Coprecipitation phenomena during spent fuel dissolution. Part 1: Experimental procedure and initial results on trivalent ion behaviour
Bernd Grambow
Journal of Nuclear Materials, 1996
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Dissolution of Zirconium-Bonded, Monolithic, Uranium-Molybdenum Fuel for Uranium Recovery
James Jerden
2013
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Spent nuclear fuel management, characterisation, and dissolution behaviour: progress and achievement from SFC and DisCo
Márton Király
EPJ Nuclear Sciences & Technologies
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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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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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Chemical Effects at the Reaction Front in Corroding Spent Nuclear Fuel
James Jerden
MRS Proceedings, 2006
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Incorporation of radionuclides in the alteration phases of spent nuclear fuel
David Wronkiewicz
1999
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Calculation of used nuclear fuel dissolution rates under anticipated Canadian waste vault conditions
Dennis LENEVEU, M. Kolar
Journal of Nuclear Materials, 1997
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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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Composition of Insoluble Residues Generated During Spent Fuel Dissolution
G F Novikov
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Determination of fission gas release of spent nuclear fuel in puncturing test and in leaching experiments under anoxic conditions
Thierry Wiss
Journal of Nuclear Materials, 2016
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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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Investigation of secondary phases formed during long-term aqueous leaching of spent nuclear fuel
Anders Puranen
MRS Advances, 2021
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The effect of fuel chemistry on UO2 dissolution
Brady Hanson
Journal of Nuclear Materials, 2016
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Modelling Oxidative Dissolution of Spent Fuel
Ivars Neretnieks
MRS Proceedings, 1996
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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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Sorption of strontium on uranyl peroxide: Implications for a high-level nuclear waste repository
Joan de Pablo
Journal of Hazardous Materials, 2010
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The effects of alpha-radiolysis on UO2 dissolution determined from batch experiments with 238Pu-doped UO2
Simcha Stroes-Gascoyne
Journal of Nuclear Materials, 2005
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Reprocessing spent nuclear fuel using molten carbonates and subsequent precipitation of rare earth fission products using phosphate
Clint Sharrad
Journal of Alloys and Compounds, 2006
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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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Water corrosion of spent nuclear fuel: radiolysis driven dissolution at the UO2/water interface
Leila Costelle
Faraday Discuss., 2015
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Spent fuel performance under repository conditions: A model for use in SR-Can
Kastriot Spahiu, Lars Werme, David Shoesmith
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