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XPS study of external α-radiolytic oxidation of UO2 in the presence of argon or hydrogen

Journal of nuclear materials, 2021-01, Vol.543, p.152604, Article 152604

2021

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Spent fuel corrosion and the impact of iron corrosion – The effects of hydrogen generation and formation of iron corrosion products

Journal of nuclear materials, 2020-12, Vol.542, p.152423, Article 152423

2020

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Leaching of spent nuclear fuels in aerated conditions: Influences of sample preparation on radionuclide release patterns

Journal of nuclear materials, 2019-12, Vol.527, p.151789, Article 151789

2019

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Reductive precipitation of neptunium on iron surfaces under anaerobic conditions

Journal of nuclear materials, 2017-12, Vol.496, p.109-116

2017

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Corrosion of high burn-up structured UO2 fuel in presence of dissolved H2

Journal of nuclear materials, 2009-10, Vol.394 (1), p.1-8

2009

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Rapid aqueous release of fission products from high burn-up LWR fuel: Experimental results and correlations with fission gas release

Journal of nuclear materials, 2012, Vol.420 (1), p.54-62

2012

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Corrosion of irradiated MOX fuel in presence of dissolved H2

Journal of nuclear materials, 2009-07, Vol.392 (1), p.45-54

2009

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Release of 108Ag from Irradiated PWR Control Rod Absorbers under Deep Repository Conditions

MRS proceedings, 2015-01, Vol.1744 (1), p.217-222

2015

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Comment on “Nanometer-Scale Corrosion of Copper in De-Aerated Deionized Water” [ J. Electrochem. Soc. , 161, C107 (2014)]

Journal of the Electrochemical Society, 2016-01, Vol.163 (3), p.Y3-Y4

2016

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Characterization of alloy particles extracted from spent nuclear fuel

Journal of nuclear materials, 2012, Vol.420 (1), p.328-333

2012

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Hydrogen catalytic effects of nanostructured alloy particles in spent fuel on radionuclide immobilization

Applied catalysis. B, Environmental, 2010-02, Vol.94 (1-2), p.173-178

2010

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Modelling radiation-induced oxidative dissolution of UO2-based spent nuclear fuel on the basis of the hydroxyl radical mediated surface mechanism

Journal of nuclear materials, 2023-05, Vol.578, p.154369, Article 154369

2023

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Determination of dissolution rates of spent fuel in carbonate solutions under different redox conditions with a flow-through experiment

Journal of nuclear materials, 2001-09, Vol.297 (3), p.231-243

2001

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Modelling radiation-induced oxidative dissolution of UO 2 -based spent nuclear fuel on the basis of the hydroxyl radical me diate d surface mechanism Exploring the impact of surface reaction mechanism and spatial and temporal resolution

Journal of nuclear materials, 2023-05, Vol.578, p.154369

2023

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Very high burnup spent fuel corrosion & leaching under hydrogen conditions

Journal of nuclear materials, 2022-12, Vol.572, p.154027, Article 154027

2022

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Geometrical aspects of alpha dose rates from UO 2 based fuels

Radiation physics and chemistry (Oxford, England : 1993), 2022, Vol.199, p.110336

2022

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Influence of groundwater composition on the reductive precipitation of U(VI) on corroding iron foil surfaces

Journal of nuclear materials, 2023-04, Vol.577, p.154324, Article 154324

2023

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Geometrical aspects of alpha dose rates from UO2 based fuels

Radiation physics and chemistry (Oxford, England : 1993), 2022-10, Vol.199, p.110336, Article 110336

2022

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Reductive immobilization of Se by iron canister under simulated repository environment

Journal of radioanalytical and nuclear chemistry, 2009-11, Vol.282 (2), p.349-354

2009

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Alpha dose rate calculations for UO2 based materials using stopping power models

Nuclear materials and energy, 2020-01, Vol.22, p.100734, Article 100734

2020

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The influence of near field hydrogen on actinide solubilities and spent fuel leaching

Radiochimica acta, 2000-09, Vol.88 (9-11), p.507-512

2000

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Corrosion of high burn-up structured UO2 fuel in presence of dissolved H-2

Journal of nuclear materials, 2009-10, Vol.394 (1), p.1

2009

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Corrosion of irradiated MOX fuel in presence of dissolved H 2

Journal of nuclear materials, 2009, Vol.392 (1), p.45-54

2009

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Effects of matrix composition and sample preparation on instant release fractions from high burnup nuclear fuel

MRS proceedings, 2014, Vol.1665 (1), p.261-266

2014

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On Weak Complex Formation: Re-interpretation of Literature Data on the Np and Pu Nitrate Complexation

Radiochimica acta, 1998-12, Vol.82 (s1), p.413-420

1998

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XPS study of external α-radiolytic oxidation of UO2 in the presence of argon or hydrogen

Spent fuel corrosion and the impact of iron corrosion – The effects of hydrogen generation and formation of iron corrosion products

Leaching of spent nuclear fuels in aerated conditions: Influences of sample preparation on radionuclide release patterns

Reductive precipitation of neptunium on iron surfaces under anaerobic conditions

Corrosion of high burn-up structured UO2 fuel in presence of dissolved H2

Rapid aqueous release of fission products from high burn-up LWR fuel: Experimental results and correlations with fission gas release

Corrosion of irradiated MOX fuel in presence of dissolved H2

Release of 108Ag from Irradiated PWR Control Rod Absorbers under Deep Repository Conditions

Comment on “Nanometer-Scale Corrosion of Copper in De-Aerated Deionized Water” [ J. Electrochem. Soc. , 161, C107 (2014)]

Characterization of alloy particles extracted from spent nuclear fuel

Hydrogen catalytic effects of nanostructured alloy particles in spent fuel on radionuclide immobilization

Modelling radiation-induced oxidative dissolution of UO2-based spent nuclear fuel on the basis of the hydroxyl radical mediated surface mechanism

Determination of dissolution rates of spent fuel in carbonate solutions under different redox conditions with a flow-through experiment

Modelling radiation-induced oxidative dissolution of UO 2 -based spent nuclear fuel on the basis of the hydroxyl radical me diate d surface mechanism Exploring the impact of surface reaction mechanism and spatial and temporal resolution

Very high burnup spent fuel corrosion & leaching under hydrogen conditions

Geometrical aspects of alpha dose rates from UO 2 based fuels

Influence of groundwater composition on the reductive precipitation of U(VI) on corroding iron foil surfaces

Geometrical aspects of alpha dose rates from UO2 based fuels

Reductive immobilization of Se by iron canister under simulated repository environment

Alpha dose rate calculations for UO2 based materials using stopping power models

The influence of near field hydrogen on actinide solubilities and spent fuel leaching

Corrosion of high burn-up structured UO2 fuel in presence of dissolved H-2

Corrosion of irradiated MOX fuel in presence of dissolved H 2

Effects of matrix composition and sample preparation on instant release fractions from high burnup nuclear fuel

On Weak Complex Formation: Re-interpretation of Literature Data on the Np and Pu Nitrate Complexation

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