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A simplified geometrical model for transient corium propagation in core for LWR with heavy reflector

EPJ nuclear sciences & technologies, 2017-01, Vol.3, p.20

2017

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The OpenCalphad thermodynamic software interface

Computational materials science, 2016-12, Vol.125, p.188-196

2016

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Design and Application of DG-FEM Basis Functions for Neutron Transport on Two-Dimensional and Three-Dimensional Hexagonal Meshes

Journal of Nuclear Engineering, 2024-03, Vol.5 (1), p.74-90

2024

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Efficient sweep kernels on shared-memory architectures for the discrete ordinates neutron transport equation on Cartesian and hexagonal geometries

EPJ Web of conferences, 2024, Vol.302, p.2009

2024

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HIGH-ORDER FINITE ELEMENTS FOR THE NEUTRON TRANSPORT EQUATION ON HONEYCOMB MESHES

EPJ Web of conferences, 2021-01, Vol.247, p.3002

2021

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COMPARISON OF CHEBYSHEV AND ANDERSON ACCELERATIONS FOR THE NEUTRON TRANSPORT EQUATION

EPJ Web of conferences, 2021-01, Vol.247, p.3001

2021

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Multi-dimensional Simulation of Phase Change by a 0D-2D Model Coupling via Stefan Condition

Communications on Applied Mathematics and Computation (Online), 2023-06, Vol.5 (2), p.853-884

2023

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Mathematical Modeling and Associated Numerical Simulation of Fusion/Solidification Front Evolution in the Context of Severe Accident of Nuclear Power Engineering

Mathematics (Basel), 2022-01, Vol.10 (1), p.116

2022

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Experimental study of oxidic-metallic melt oxidation

Nuclear engineering and design, 2020-07, Vol.363, p.110618, Article 110618

2020

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Butler‐based thermodynamic modeling of interfacial energies for in‐vessel corium systems

Journal of nuclear materials, 2022-10, Vol.569, p.153935, Article 153935

2022

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High-order Wachspress functions on convex polygons through computer algebra

Journal of computational physics, 2022-12, Vol.470, p.111545, Article 111545

2022

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Validation of the Legendre Expansion of the Collision Law for Light Water Reactor Calculations

Nuclear science and engineering, 2015-06, Vol.180 (2), p.182-198

2015

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Mass transfer between a continuous oxide phase (U-O-Zr) and a steel droplet at liquid state: Potential impact on corium pool behaviour during in-vessel melt retention

Nuclear engineering and design, 2021-12, Vol.385, p.111525, Article 111525

Le Tellier, R.

2021

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Anderson acceleration and linear diffusion for accelerating the k-eigenvalue problem for the transport equation

Annals of nuclear energy, 2023-01, Vol.180, p.109406, Article 109406

2023

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Numerical simulations of the Rayleigh-Bénard-Marangoni convections in a thin metallic layer

Annals of nuclear energy, 2021-01, Vol.150, p.107848, Article 107848

2021

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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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Efficient and Portable Vectorized Sweep Kernels for the Transport Equation on 3D Cartesian Grids Using the Kokkos Framework

Nuclear science and engineering, 2024-05, p.1-17

2024

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Phase-field modeling with the TAF-ID of incipient melting and oxygen transport in nuclear fuel during power transients

Journal of nuclear materials, 2021-12, Vol.556, p.153173, Article 153173

2021

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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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Numerical simulations of the Rayleigh-Bénard-Marangoni convections in a thin metallic laye

Annals of nuclear energy, 2021-01, Vol.150, p.107848

2021

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Diffuse-interface modelling of multicomponent diffusion and phase separation in the U-O-Zr ternary system

Computational materials science, 2022-11, Vol.214, p.111650, Article 111650

2022

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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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Main outcomes from the IVR code benchmark performed in the IVMR European project

Annals of nuclear energy, 2020-10, Vol.146

2020

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Discontinuous Galerkin Discretization and $hp$-Refinement for the Resolution of the Neutron Transport Equation

SIAM journal on scientific computing, 2013-01, Vol.35 (2), p.A936-A956

2013

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Probing Corium in severe nuclear accident experiments: Development of acoustic techniques resisting very high temperatures

Proceedings of Meetings on Acoustics, 2019, Vol.38 (1)

2019

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A simplified geometrical model for transient corium propagation in core for LWR with heavy reflector

The OpenCalphad thermodynamic software interface

Design and Application of DG-FEM Basis Functions for Neutron Transport on Two-Dimensional and Three-Dimensional Hexagonal Meshes

Efficient sweep kernels on shared-memory architectures for the discrete ordinates neutron transport equation on Cartesian and hexagonal geometries

HIGH-ORDER FINITE ELEMENTS FOR THE NEUTRON TRANSPORT EQUATION ON HONEYCOMB MESHES

COMPARISON OF CHEBYSHEV AND ANDERSON ACCELERATIONS FOR THE NEUTRON TRANSPORT EQUATION

Multi-dimensional Simulation of Phase Change by a 0D-2D Model Coupling via Stefan Condition

Mathematical Modeling and Associated Numerical Simulation of Fusion/Solidification Front Evolution in the Context of Severe Accident of Nuclear Power Engineering

Experimental study of oxidic-metallic melt oxidation

Butler‐based thermodynamic modeling of interfacial energies for in‐vessel corium systems

High-order Wachspress functions on convex polygons through computer algebra

Validation of the Legendre Expansion of the Collision Law for Light Water Reactor Calculations

Mass transfer between a continuous oxide phase (U-O-Zr) and a steel droplet at liquid state: Potential impact on corium pool behaviour during in-vessel melt retention

Anderson acceleration and linear diffusion for accelerating the k-eigenvalue problem for the transport equation

Numerical simulations of the Rayleigh-Bénard-Marangoni convections in a thin metallic layer

Oxygen diffusion in liquid (over)stoichiometric corium

Efficient and Portable Vectorized Sweep Kernels for the Transport Equation on 3D Cartesian Grids Using the Kokkos Framework

Phase-field modeling with the TAF-ID of incipient melting and oxygen transport in nuclear fuel during power transients

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

Numerical simulations of the Rayleigh-Bénard-Marangoni convections in a thin metallic laye

Diffuse-interface modelling of multicomponent diffusion and phase separation in the U-O-Zr ternary system

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

Main outcomes from the IVR code benchmark performed in the IVMR European project

Discontinuous Galerkin Discretization and $hp$-Refinement for the Resolution of the Neutron Transport Equation

Probing Corium in severe nuclear accident experiments: Development of acoustic techniques resisting very high temperatures

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