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. Dans, le temps caractéristique associé au transfert de masse à l'interface oxyde-métal (resp. à la relocalisation des gouttelettes au travers de l'oxyde) est évalué en ordre de grandeur à 1000s

, Dans la situation réacteur, les modélisations faites du bain de corium en fond de cuve considèrent en général, de par les hypothèses de ségrégation qui sont faites, qu'une croûte réfractaire à l'interface est présente. Son épaisseur estimée est millimétrique (au sens du bilan thermique stationnaire associé à ces modélisations du bain) et sa tenue mécanique incertaine mais pour autant, son potentiel rôle de "barrière" solide au transfert de masse interfacial pose question. C'est en ce sens que le programme expérimental CORDEB 5 mené dans l'installation RASPLAV-3 a inclus un volet (essais CD1-01 et CD1-02) consacré à l'étude de l'impact d'une croûte sous-oxydée (voir [12]) sur la stratification sous atmosphère neutre (tel que schématisé à la Figure B.5a). Ces essais ont montré qu'après une période d'incubation (voir Figure B.5b) de l'ordre de l'heure, le transfert de l'acier au travers de cette croûte a bien lieu amenant le système, Dans les essais du programme MASCA, les interactions entre l'acier et un bain oxyde ont été étudiées dans des configurations sans croûte à l'interface

, avancer des pistes sur les mécanismes d'interaction entre l'acier et la croûte : ? d'abord, l'acier diffuse dans la croûte par le biais des inclusions métalliques (enrichies en Zr) présentes dans cette croûte sous-oxydée

. ?-ensuite, interaction entre la phase métallique (acier-Zr) intergranulaire et les grains oxydes de la croûte conduit à la dissolution partielle des grains augmentant ainsi la fraction liquide dans la croûte oxyde, et permet la percolation de cette phase liquide à travers la croûte

. Ce, . Irsn, . Cea, and . Edf, AREVA a pris la forme d'un contrat bilatéral entre l'IRSN et le NITI pour réaliser cinq campagnes d

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S. Bakardjieva, M. Barrachin, S. Bechta, D. Bottomley, L. Brissoneau et al., Improvement of the european thermodynamic database NUCLEA, Progress in Nuclear Energy, vol.52, issue.1, pp.84-96, 2010.

M. Barrachin and F. Defoort, Thermophysical properties of in-vessel corium : MASCA programme related results, Proc. of MASCA Seminar, 2004.

C. Guéneau, S. Gossé, A. Quaini, N. Dupin, B. Sundman et al., Advanced computational tools to perform thermodynamic calculations on nuclear fuel materials, Proc. of the 7th European Review Meeting on Severe Accident Research ERMSAR-2015, 2015.

N. Moelans, B. Blanpain, and P. Wollants, An introduction to phase-field modeling in microstructure evolution, Computer Coupling of Phase Diagrams and Thermochemistry, vol.32, pp.268-294, 2008.

I. Singer-loginova and H. M. Singer, The phase field technique for modeling multiphase materials, Reports on Progress in Physics, vol.71, issue.10, pp.1-32, 2008.

J. Rowlinson and J. D. Translation, Van der Waals : The thermodynamik theory of capillarity under the hypothesis of a continuous variation of density, Journal of Statistical Physics, vol.20, issue.2, pp.200-244, 1978.

Q. Bronchart, Développement de méthodes de champs de phase quantitatives et applications à la précipitation homogène dans les alliages binaires, 2006.

J. W. Cahn and J. E. Hilliard, Free energy of a nonuniform system. I. interfacial free energy, The Journal of Chemical Physics, vol.28, issue.2, pp.258-267, 1958.

J. W. Cahn, Free energy of a nonuniform system, The Journal of Chemical Physics, vol.30, issue.5, pp.1121-1124, 1959.

A. A. Wheeler, W. J. Boettinger, and G. B. Mcfadden, Phase-field model for isothermal phase transitions in binary alloys, Physical Review A, vol.45, pp.7424-7439, 1992.

, AnnexeC Encadrement d'étudiants Sont données ici la liste des étudiants encadrés pour des travaux directement rapportés dans ce manuscrit (voir Tableau C.1) et la liste des principaux étudiants encadrés pour d'autres travaux menés au CEA Cadarache entre, 2007.

, Sont répertoriées ici les publications avec comité de lecture (dans des revues scientifiques ou

?. J. Delacroix, R. L. Tellier, and &. P. Piluso, Oxygen diffusion in liquid (over)stoichiometric corium, Nuclear Engineering and Design, vol.337, pp.148-160, 2018.

?. V. Tiwari-&-r.-le and . Tellier, On the use of CALPHAD-based enthalpy-temperature relations in suboxidized corium plane front solidification modelling, Annals of Nuclear Energy, vol.117, pp.175-182, 2018.

?. V. Almjashev, V. S. Granovsky, V. B. Khabensky, S. Y. Kotova, E. V. Krushinov et al., Experimental study of transient phenomena in the three-liquid oxidic-metallic corium pool, Nuclear Engineering and Design, vol.332, pp.31-37, 2018.

?. L. Berge, N. Estre, D. Tisseur, E. Payan, D. Eck et al., Fast high-energy X-ray imaging for Severe Accidents experiments on the future PLINIUS-2 platform, IEEE Transactions on Nuclear Science, 2018.

?. R. Tellier, E. Skrzypek, and &. Saas, On the treatment of plane fusion front in lumped parameter thermal models with convection, Applied Thermal Engineering, vol.120, pp.314-326, 2017.

?. L. Saas, R. L. Tellier, and &. S. Bajard, A simplified geometrical model for transient corium propagation in core for LWR with heavy reflector, EPJ Nuclear Sci. Technol, vol.3, p.20, 2017.

?. E. Skrzypek, M. Skrzypek, L. Saas, and &. Tellier, In vessel corium propagation sensitivity study of reactor pressure vessel rupture time with PROCOR platform, Journal of Power Technologies, vol.97, issue.2, pp.110-116, 2017.

?. B. Sundman, U. R. Kattner, C. Sigli, M. Stratmann, R. L. Tellier et al., The OpenCalphad thermodynamic software interface, Computational Materials Science, vol.125, pp.188-196, 2016.

?. C. Cardon, R. L. Tellier, and &. M. Plapp, Modelling of the Kinetics of Liquid Phase Segregation in the Uranium-Oxygen Binary System, CALPHAD : Computer Coupling of Phase Diagrams and Thermochemistry, vol.52, pp.47-56, 2016.

?. R. Tellier, L. Saas, and &. S. Bajard, Transient Stratification Modelling of a Corium Pool in a LWR Vessel Lower Head, Nuclear Engineering and Design, vol.287, pp.68-77, 2015.

?. A. Calloo, J. F. Vidal, R. L. Tellier, and &. G. Rimpault, Validation of the Legendre Expansion of the Collision Law for Light Water Reactor Calculations, Nuclear Science and Engineering, vol.180, pp.182-198, 2015.

?. M. Guyot, P. Gubernatis, and &. Tellier, Space-time Effects in the Initiating Phase of Sodium Fast Reactors and their Evaluation using a Three-dimensional Neutron Kinetics Model, Annals of Nuclear Energy, vol.85, pp.115-126, 2015.

?. M. Guyot, P. Gubernatis, C. Suteau, R. L. Tellier, and &. J. Lecerf, An Assessment of Corewide Coherency Effects in the Multichannel Modeling of the Initiating Phase of a Severe Accident in a Sodium Fast Reactor, Nuclear Technology, vol.185, pp.21-38, 2014.

?. D. Fournier, R. Herbin, and &. Tellier, Discontinuous Galerkin Discretization and hpRefinement for the Resolution of the Neutron Transport Equation, SIAM J. Sci. Comput, pp.936-956, 2013.
URL : https://hal.archives-ouvertes.fr/hal-00781329

?. R. Tellier, D. Fournier, and &. Suteau, Reactivity Perturbation Formulation for a Discontinuous Galerkin based Transport Solver and its Use with Adaptive Mesh Refinement, Nucl. Sc. Eng, vol.167, pp.209-220, 2011.

?. D. Fournier, R. L. Tellier, and &. C. Suteau, Analysis of an a posteriori Error Estimator for the Transport Equation with S N and Discontinuous Galerkin Discretizations, Ann. Nucl. Energy, vol.38, pp.221-231, 2011.

?. R. Tellier, C. Suteau, D. &. Fournier, and . Ruggieri, High-Order Discrete Ordinate Transport in Hexagonal Geometry : a New Capability in ERANOS, Il Nuovo Cimento B, vol.33, pp.121-128, 2010.

?. R. Tellier, D. &. Fournier, and . Ruggieri, A Wavelet-Based Finite Element Method for the Self-Shielding Issue in Neutron Transport, Nucl. Sc. Eng, vol.163, pp.34-65, 2009.

?. A. Santamarina, N. Hfaiedh, R. L. Tellier, V. Marotte, S. Misu et al., Advanced neutronics tools for BWR design calculations, Nucl. Eng. Design, vol.238, pp.1965-1974, 2008.

?. R. Tellier, G. Marleau, M. Dahmani, and &. Hébert, Improvements of the Reactivity Devices Modeling for the Advanced CANDU Reactor, Ann. Nucl. Energy, vol.35, pp.868-876, 2008.

?. M. Dahmani, G. Marleau-&-r.-le, and . Tellier, Modeling Reactivity Devices for Advanced CANDU Reactors Using the Code DRAGON, Ann. Nucl. Energy, vol.35, pp.804-812, 2008.

?. R. Tellier, A. Hébert, A. Santamarina, and &. Litaize, A Modeling of BWR-MOX Assemblies Based on the Characteristics Method Combined with Advanced Self-Shielding Models, Nucl. Sc. Eng, vol.158, pp.231-243, 2008.

?. R. Le-tellier and &. A. Hébert, Anisotropy and Particle Conservation for Trajectory-Based Deterministic Methods, Nucl. Sc. Eng, vol.158, pp.28-39, 2008.

?. R. Le-tellier and &. A. Hébert, An Improved Algebraic Collapsing Acceleration with General Boundary Conditions for the Characteristics Method, Nucl. Sc. Eng, vol.156, pp.1-18, 2007.

?. R. Le-tellier and &. A. Hébert, On the Integration Scheme along a Trajectory for the Characteristics Method, Ann. Nucl. Energy, vol.33, pp.1260-1269, 2006.

?. M. Dahmani, R. L. Tellier, R. Roy, and &. Hébert, An Efficient Preconditioning Technique Using Krylov Subspace Methods for 3D Characteristics Solvers, Ann. Nucl. Energy, vol.32, pp.876-896, 2005.

, Actes de conférences

?. D. Tisseur, M. Cavaro, F. Rey, K. Paumel, N. Chikhi et al., Consistent use of CALPHAD data for invessel corium pool modeling : some analytical and practical considerations, Int. Conf. on Advancements in Nuclear Instrumentation Measurement Methods and their, 2019.

?. L. Carénini, F. Fichot, N. Bakouta, H. Esmaili, L. Humphries et al., Elaboration of a PIRT for the modelling of In-Vessel Retention, The 9 th European Review Meeting on Severe Accident Research. ERMSAR-2019, 2019.

?. L. Carénini, F. Fichot, N. Bakouta, R. L. Tellier, L. Viot et al., Main outcomes from the IVR code benchmark performed in the IVMR project, The 9 th European Review Meeting on Severe Accident Research. ERMSAR-2019, 2019.

?. J. Delacroix, R. L. Tellier, and &. P. Piluso, Mass transfer inside oxidizing liquid corium droplets, The 9 th European Review Meeting on Severe Accident Research. ERMSAR-2019, 2019.

?. M. Peybernes, L. Saas, R. L. Tellier, and C. Dang, Thermalhydraulics DNS of a thin metallic layer : application to the evaluation of nuclear reactor severe accident mitigation strategy, The 9 th European Review Meeting on Severe Accident Research. ERMSAR-2019, 2019.

?. A. Pivano, P. Piluso, N. Chikhi, P. Fouquart, J. Delacroix et al., Experimental studies of molten steel -suboxidized corium crust interaction for IVR application, The 9 th European Review Meeting on Severe Accident Research. ERMSAR-2019, 2019.

?. M. Peybernes, R. L. Tellier, L. Viot, A. Drouillet, and &. Saas, Hybrid lumped/distributed parameter model for treating the vessel lower head ablation by corium during a LWR severe accident, The 27 th Int. Conf. Nuclear Energy for New Europe. NENE, 2018.

?. L. Saas, E. Skrzypek, and &. Tellier, Rayleigh-Bénard and Bénard-Marangoni convection in a thin metallic layer on top of corium pool, The 8 th European Review Meeting on Severe Accident Research

?. C. Le-guennic, L. Saas-&-r.-le, Y. Tellier, M. Wu, J. Guingo et al., Contribution of CFD studies to IVR assessment, The 8 th European Review Meeting on Severe Accident Research. ERMSAR-2017, 2017.

?. L. Saas, R. L. Tellier, and &. S. Bajard, A Simplified Geometrical Model for Transient Corium Propagation in Core for LWR with Heavy Reflector, ICAPP, 2015.

?. R. Tellier, L. Saas, and &. Payot, Phenomenological Analyses of Corium Propagation in LWRs : the PROCOR platform, The 7 th European Review Meeting on Severe Accident Research. ERMSAR-2015, 2015.

?. N. Bakouta, R. L. Tellier, and &. L. Saas, Assessment of Advanced Corium-In-Lower-Head Models in MAAP and PROCOR codes, The 7 th European Review Meeting on Severe Accident Research. ERMSAR-2015, 2015.

?. M. Guyot, R. L. Tellier, P. Archier, and &. Gabrielli, Improvement of Space-Time Kinetics Capability of the SNATCH Solver and Comparison to KIN3D/PARTISN Results

, Advances in Reactor Physics. PHYSOR 2014 -The Role of Reactor Physics toward a Sustainable Future, 2014.

?. J. Vidal, P. Archier, A. Calloo, P. Jacquet, J. Tommasi et al., An Improved EnergyCollapsing Method for Core-Reflector Modelization in SFR Core Calculations Using the Paris Platform, Int. Conf. on Advances in Reactor Physics and Linking Research, 2012.

?. A. Calloo, J. F. Vidal, R. L. Tellier, and &. G. Rimpault, Mixed Legendre Moments and Discrete Scattering Cross Sections for Anisotropy Representation, Int. Conf. on Advances in Reactor Physics and Linking Research, 2012.

?. D. Fournier, P. Archier, R. L. Tellier, and &. C. Suteau, Improvement of Neutronic Calculations on a MASURCA Core using Adaptive Mesh Refinement Capabilities, Int. Conf. on Mathematics and Computational Methods Applied to Nuclear Science and Engineering. M&C, 2011.

?. D. Fournier, R. L. Tellier, C. Suteau, and &. Herbin, Analysis of a hp-Refinement Method for Solving the Neutron Transport Equation using Two Error Estimators, Int. Conf. on Mathematics and Computational Methods Applied to Nuclear Science and Engineering. M&C, 2011.

?. A. Calloo, R. L. Tellier, and &. J. Vidal, Angular Finite Volume Method for Solving the Multigroup Transport Equation with Piecewise-Average Scattering Cross Sections, Int. Conf. on Mathematics and Computational Methods Applied to Nuclear Science and Engineering. M&C, 2011.

?. F. Alcaro, S. Dulla, P. Ravetto, R. L. Tellier, and &. C. Suteau, Implementation of the Quasi-Static Method for Neutron Transport, Int. Conf. on Mathematics and Computational Methods Applied to Nuclear Science and Engineering. M&C, 2011.

?. S. Schunert, Y. Y. Azmy, D. Fournier-&-r.-le, and . Tellier, Comparison of the Accuracy of Various Spatial Discretization Schemes of the Neutron Transport Equation, Int. Conf. on Mathematics and Computational Methods Applied to Nuclear Science and Engineering. M&C, 2011.

?. L. Gastaldo, R. L. Tellier, C. Suteau, D. &. Fournier, and . Ruggieri, High-Order Discrete Ordinate Transport in Non-Conforming 2D Cartesian Meshes, Int. Conf. on Mathematics, 2009.

?. D. Fournier-&-r.-le and . Tellier, Adaptive Algorithms For a Self-Shielding Treatment using a Wavelet-based Galerkin Method, Int. Conf. on Mathematics, 2009.

?. B. Arsenault, R. L. Tellier, and &. A. Hébert, Efficiency of the Delta-Tracking Technique for Monte Carlo Calculations Applied to Neutron-Transport Simulations of the Advanced CANDU Reactor Design, Int. Conf. on Reactor Physics, Nuclear Power : A Sustainable Resource. PHYSOR, 2008.

?. R. Tellier, G. Marleau, A. Hébert, D. Roubstov, D. Altiparmakov et al., Burnup Dependence of Coolant Void Reactivity for ACR-1000 Cell, Int. Conf. on Reactor Physics, Nuclear Power : A Sustainable Resource. PHYSOR, 2008.

?. A. Popov, R. Chambon, R. L. Tellier, G. Marleau, and &. A. Hebert, Models for Coolant Void Reactivity Evaluation in CANDU Generation II and III +, Int. Conf. on Reactor Physics, Nuclear Power : A Sustainable Resource. PHYSOR, 2008.

?. J. Vidal, R. L. Tellier, P. Blaise, G. Guillot, N. Huot et al., Analysis of the FLUOLE Experiment for the APOLLO2 Qualification of PWR Core Reflectors

. Int and . Conf, on Reactor Physics, Nuclear Power : A Sustainable Resource. PHYSOR, 2008.

?. R. Le-tellier, &. A. Hébert-;-r.-le, A. Tellier, A. Hébert, &. Santamarina et al., Benchmarking of the Characteristics Method Combined with Advanced Self-Shielding Models on BWR-MOX Assemblies, Int. Mtg. on the Physics of Fuel Cycles and Advanced Nuclear Systems : Advances in Nuclear Analysis and Simulation. PHYSOR, 2006.

?. R. Tellier, A. Hébert, and &. Marleau, The Implementation of a 3D Characteristics Solver for the Generation of Incremental Cross Sections for Reactivity Devices in a CANDU Reactor

. Mtg, the Physics of Fuel Cycles and Advanced Nuclear Systems : Advances in Nuclear Analysis and Simulation. PHYSOR, 2006.

?. R. Karthikeyan, R. L. Tellier, A. Hébert, and &. Marleau, Estimation of Coolant Void Reactivity for ACR-type Lattices using DRAGON and Validation using MCNP5 and TRIPOLI4.3, Int. Mtg. on the Physics of Fuel Cycles and Advanced Nuclear Systems : Advances in Nuclear Analysis and Simulation. PHYSOR, 2006.

?. C. Vaglio-gaudard, A. Sargeni, A. Santamarina, R. L. Tellier, and &. J. Vidal, Qualification of APOLLO2 BWR calculation scheme on the BASALA mock-up, Int. Mtg. on the Physics of Fuel Cycles and Advanced Nuclear Systems : Advances in Nuclear Analysis and Simulation. PHYSOR, 2006.

?. R. Le-tellier and &. A. Hébert, Spectral Analysis of an Algebraic Collapsing Acceleration for the Characteristics Method, Int. Mtg. in Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications. M&C 2005, 2005.

?. R. Le-tellier and &. A. Hébert, Application of the DSA Preconditioned GMRES Formalism to the