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Hafnium oxidation at high temperature in steam

Journal of nuclear materials, 2021-07, Vol.550, p.152901-14, Article 152901

2021

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Morphology and phase distributions of molten core in a reactor vessel

Journal of nuclear materials, 2020-12, Vol.542, p.152471, Article 152471

2020

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Diffusivity of hydrogen and properties of point defects in beryllium investigated by DFT

Journal of nuclear materials, 2019-10, Vol.524, p.323-329

2019

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A comparison of core degradation phenomena in the CORA, QUENCH, Phébus SFD and Phébus FP experiments

Nuclear engineering and design, 2015-03, Vol.283, p.8-20

2015

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Core Melt Composition at Fukushima Daiichi: Results of Transient Simulations with ASTEC

Nuclear technology, 2016-12, Vol.196 (3), p.489-498

2016

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Experimental study and thermodynamic modelling of the Ag-Cd-In system

Calphad, 2019-03, Vol.64, p.292-305

2019

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Progress on source term evaluation of accidental events in the experimental fusion installation ITER

Fusion engineering and design, 2015-10, Vol.98-99, p.2219-2222

2015

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Critical evaluation of experimental data of solution enthalpy of zirconium in liquid aluminum

The Journal of chemical thermodynamics, 2019-01, Vol.128, p.295-304

2019

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Enthalpy of mixing in the Ag-Cd-In ternary liquid phase

The Journal of chemical thermodynamics, 2017-04, Vol.107, p.207-215

2017

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Theoretical prediction of thermodynamic properties of tritiated beryllium molecules and application to ITER source term

Fusion engineering and design, 2014-10, Vol.89 (7-8), p.1544-1550

2014

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Fuel and fission product behaviour in early phases of a severe accident. Part II: Interpretation of the experimental results of the PHEBUS FPT2 test

Journal of nuclear materials, 2014-10, Vol.453 (1-3), p.355-374

2014

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Fission-product behaviour in irradiated TRISO-coated particles: Results of the HFR-EU1bis experiment and their interpretation

Journal of nuclear materials, 2011-08, Vol.415 (1), p.104-116

2011

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Oxidation effects during corium melt in-vessel retention

Nuclear engineering and design, 2016-08, Vol.305, p.389-399

2016

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Source Term Evaluation for Accident Transients in the Experimental Fusion Facility ITER

Fusion science and technology, 2015-04, Vol.67 (3), p.627-630

2015

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Theoretical investigation on the point defect formation energies in beryllium and comparison with experiments

Nuclear materials and energy, 2017-08, Vol.12, p.453-457

2017

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Energy landscape of hydrogen in the vicinity of monovacancy in beryllium

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 2024-04, Vol.549, p.165261, Article 165261

2024

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Adaptation of the ASTEC code system to accident scenarios in fusion installations

Fusion engineering and design, 2013-10, Vol.88 (9-10), p.2698-2703

2013

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Effect of temperature gradient on chemical element partitioning in corium pool during in-vessel retention

Nuclear engineering and design, 2018-02, Vol.327, p.82-91

2018

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Progress in understanding fission-product behaviour in coated uranium-dioxide fuel particles

Journal of nuclear materials, 2009-03, Vol.385 (2), p.372-386

2009

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Fission product release in the first two PHEBUS tests FPT0 and FPT1

Nuclear engineering and design, 2005-09, Vol.235 (20), p.2183-2208

2005

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New modelling of the U–O–Zr phase diagram in the hyper-stoichiometric region and consequences for the fuel rod liquefaction in oxidising conditions

Journal of nuclear materials, 2008-04, Vol.375 (3), p.397-409

2008

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Quality improvements of thermodynamic data applied to corium interactions for severe accident modelling in SARNET2

Annals of nuclear energy, 2014-12, Vol.74 (C), p.110-124

2014

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Oxidation effect on steel corrosion and thermal loads during corium melt in-vessel retention

Nuclear engineering and design, 2014-10, Vol.278, p.310-316

2014

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Improvement of the European thermodynamic database NUCLEA

Progress in nuclear energy (New series), 2010, Vol.52 (1), p.84-96

2010

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Reaction-diffusion modeling of hydrogen transport and surface effects in application to single-crystalline Be

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 2018-09, Vol.430, p.23-30

2018

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Hafnium oxidation at high temperature in steam

Morphology and phase distributions of molten core in a reactor vessel

Diffusivity of hydrogen and properties of point defects in beryllium investigated by DFT

A comparison of core degradation phenomena in the CORA, QUENCH, Phébus SFD and Phébus FP experiments

Core Melt Composition at Fukushima Daiichi: Results of Transient Simulations with ASTEC

Experimental study and thermodynamic modelling of the Ag-Cd-In system

Progress on source term evaluation of accidental events in the experimental fusion installation ITER

Critical evaluation of experimental data of solution enthalpy of zirconium in liquid aluminum

Enthalpy of mixing in the Ag-Cd-In ternary liquid phase

Theoretical prediction of thermodynamic properties of tritiated beryllium molecules and application to ITER source term

Fuel and fission product behaviour in early phases of a severe accident. Part II: Interpretation of the experimental results of the PHEBUS FPT2 test

Fission-product behaviour in irradiated TRISO-coated particles: Results of the HFR-EU1bis experiment and their interpretation

Oxidation effects during corium melt in-vessel retention

Source Term Evaluation for Accident Transients in the Experimental Fusion Facility ITER

Theoretical investigation on the point defect formation energies in beryllium and comparison with experiments

Energy landscape of hydrogen in the vicinity of monovacancy in beryllium

Adaptation of the ASTEC code system to accident scenarios in fusion installations

Effect of temperature gradient on chemical element partitioning in corium pool during in-vessel retention

Progress in understanding fission-product behaviour in coated uranium-dioxide fuel particles

Fission product release in the first two PHEBUS tests FPT0 and FPT1

New modelling of the U–O–Zr phase diagram in the hyper-stoichiometric region and consequences for the fuel rod liquefaction in oxidising conditions

Quality improvements of thermodynamic data applied to corium interactions for severe accident modelling in SARNET2

Oxidation effect on steel corrosion and thermal loads during corium melt in-vessel retention

Improvement of the European thermodynamic database NUCLEA

Reaction-diffusion modeling of hydrogen transport and surface effects in application to single-crystalline Be

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