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Thermophysical Properties of Liquid Zirconia Measured by Aerodynamic Levitation at High Temperature

International journal of thermophysics, 2023-08, Vol.44 (8), Article 127

2023

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Pyroreflectometry as a technique for the accurate measurement of very high temperatures in molten materials

Review of scientific instruments, 2022-09, Vol.93 (9)

2022

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High-Temperature Characterization of Melted Nuclear Core Materials: Investigating Corium Properties Through the Case Studies of In-Vessel and Ex-Vessel Retention

Frontiers in energy research, 2022-05, Vol.10

2022

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Cationic local composition fluctuations in rapidly cooled nuclear fuel melts

Nuclear Materials and Energy, 2022-06, Vol.31 (14), p.101183, Article 101183

2022

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The UO2-ZrO2 system at high temperature (T> 2000 K) : importance of the meta-stable phases under severe accident conditions

Journal of nuclear materials, 2005-09, Vol.344 (1-3), p.259-264

2005

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Experiments on interactions of molten steel with suboxidized corium crust for in-vessel melt retention

Nuclear engineering and design, 2019-12, Vol.355, p.110271, Article 110271

2019

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CONTRIBUTIONS OF THE VULCANO EXPERIMENTAL PROGRAMME TO THE UNDERSTANDING OF MCCI PHENOMENA

Nuclear engineering and technology, 2012-04, Vol.44 (3), p.261-272

2012

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Fukushima Daiichi fuel debris simulant materials for the development of cutting and collection technologies

Journal of nuclear science and technology, 2018-09, Vol.55 (9), p.985-995

2018

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Oxygen diffusion in liquid (over)stoichiometric corium

Nuclear engineering and design, 2018-10, Vol.337, p.148-160

2018

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Thermal convection of a liquid metal under an alternating magnetic field

European journal of mechanics, B, Fluids, 2024-11, Vol.108, p.180-186

2024

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Mass log-stable distribution of fragments in liquid–liquid jet fragmentation based on a two-step cascade between viscous shear instability and Rayleigh–Taylor instability

International journal of multiphase flow, 2023-10, Vol.167, p.104518, Article 104518

2023

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Trends in severe accident research in Europe: SARNET network from Euratom to NUGENIA

EPJ nuclear sciences & technologies, 2017-01, Vol.3, p.28

2017

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Mass log-stable distribution of fragments in liquid–liquid jet fragmentation based on a two-step cascade between viscous Kelvin-Helmholtz instability and Rayleigh-Taylor instability

International journal of multiphase flow, 2023-10, Vol.167

2023

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Overview of key thermal–hydraulic phenomena in severe accident unfolding: Current knowledge and further needs

Nuclear engineering and design, 2023-06, Vol.407, p.112256, Article 112256

2023

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Measurements of Liquid AISI 304L Steel Density and Surface Tension, and Influence of Surface‐Active Elements at High Temperatures

Steel research international, 2022-06, Vol.93 (6), p.n/a

2022

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Material characterization of the VULCANO corium concrete interaction test with concrete representative of Fukushima Daiichi Nuclear Plants

Journal of nuclear materials, 2020-01, Vol.528, p.151860, Article 151860

2020

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Corium behavior and steam explosion risks: A review of experiments

Annals of nuclear energy, 2018-11, Vol.121, p.162-176

2018

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Upgrading the PLINIUS platform toward smarter prototypic-corium experimental R&D

Nuclear engineering and design, 2022-01, Vol.386, p.111511, Article 111511

2022

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Analysis of material effect in molten fuel–coolant interaction, comparison of thermodynamic calculations and experimental observations

Annals of nuclear energy, 2012-08, Vol.46, p.197-203

2012

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Achievements of recent research on severe accidents at CEA/IRESNE in support of future nuclear fission technology

Nuclear engineering and design, 2024-05, Vol.421, p.113055, Article 113055

2024

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Induction heating of cylindrical loads of arbitrary skin-depth by “current-sheet” inductors

Electrical engineering, 2018-06, Vol.100 (2), p.811-822

2018

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Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: First outcomes

Annals of nuclear energy, 2023-08, Vol.188, p.109796, Article 109796

2023

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Steel oxidation phenomena during Molten Corium siliceous Concrete Interaction (MCCI)

Journal of alloys and compounds, 2015-02, Vol.622, p.1005-1012

2015

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Material Effect in the Nuclear Fuel-Coolant Interaction: Analyses of Prototypic Melt Fragmentation and Solidification in the KROTOS Facility

Nuclear technology, 2014-05, Vol.186 (2), p.229-240

2014

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Status of steam explosion understanding and modelling

Annals of nuclear energy, 2014-12, Vol.74 (C), p.125-133

2014

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Thermophysical Properties of Liquid Zirconia Measured by Aerodynamic Levitation at High Temperature

Pyroreflectometry as a technique for the accurate measurement of very high temperatures in molten materials

High-Temperature Characterization of Melted Nuclear Core Materials: Investigating Corium Properties Through the Case Studies of In-Vessel and Ex-Vessel Retention

Cationic local composition fluctuations in rapidly cooled nuclear fuel melts

The UO2-ZrO2 system at high temperature (T> 2000 K) : importance of the meta-stable phases under severe accident conditions

Experiments on interactions of molten steel with suboxidized corium crust for in-vessel melt retention

CONTRIBUTIONS OF THE VULCANO EXPERIMENTAL PROGRAMME TO THE UNDERSTANDING OF MCCI PHENOMENA

Fukushima Daiichi fuel debris simulant materials for the development of cutting and collection technologies

Oxygen diffusion in liquid (over)stoichiometric corium

Thermal convection of a liquid metal under an alternating magnetic field

Mass log-stable distribution of fragments in liquid–liquid jet fragmentation based on a two-step cascade between viscous shear instability and Rayleigh–Taylor instability

Trends in severe accident research in Europe: SARNET network from Euratom to NUGENIA

Mass log-stable distribution of fragments in liquid–liquid jet fragmentation based on a two-step cascade between viscous Kelvin-Helmholtz instability and Rayleigh-Taylor instability

Overview of key thermal–hydraulic phenomena in severe accident unfolding: Current knowledge and further needs

Measurements of Liquid AISI 304L Steel Density and Surface Tension, and Influence of Surface‐Active Elements at High Temperatures

Material characterization of the VULCANO corium concrete interaction test with concrete representative of Fukushima Daiichi Nuclear Plants

Corium behavior and steam explosion risks: A review of experiments

Upgrading the PLINIUS platform toward smarter prototypic-corium experimental R&D

Analysis of material effect in molten fuel–coolant interaction, comparison of thermodynamic calculations and experimental observations

Achievements of recent research on severe accidents at CEA/IRESNE in support of future nuclear fission technology

Induction heating of cylindrical loads of arbitrary skin-depth by “current-sheet” inductors

Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: First outcomes

Steel oxidation phenomena during Molten Corium siliceous Concrete Interaction (MCCI)

Material Effect in the Nuclear Fuel-Coolant Interaction: Analyses of Prototypic Melt Fragmentation and Solidification in the KROTOS Facility

Status of steam explosion understanding and modelling

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