Search Results - "Tellier, R. Le"

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  1. 1

    Three-dimensional numerical simulation of droplet formation by Rayleigh–Taylor instability in multiphase corium by Zanella, R., Tellier, R. Le, Plapp, M., Tegze, G., Henry, H.

    Published in Nuclear engineering and design (01-08-2021)
    “…•A pseudo-binary CFD model is proposed to simulate a corium pool.•Metal phase droplets during the stratification transitory are captured by the…”
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    Journal Article
  2. 2

    Experimental study of transient phenomena in the three-liquid oxidic-metallic corium pool by Almjashev, V.I., Granovsky, V.S., Khabensky, V.B., Kotova, S.Yu, Krushinov, E.V., Sulatsky, A.A., Vitol, S.A., Gusarov, V.V., Fichot, F., Michel, B., Piluso, P., Le Tellier, R., Fischer, M., Le Guennic, C., Bakouta, N.

    Published in Nuclear engineering and design (01-06-2018)
    “…•Physicochemical phenomena in 3-liquid corium pool are studied under IVR conditions.•3-liquid pool structure can stay stable for a certain period of…”
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    Journal Article
  3. 3

    A lumped parameter model of continuous/dispersed phases mass transfer for simulating in-vessel corium stratification transients by Le Tellier, R.

    Published in Annals of nuclear energy (01-02-2023)
    “…In the frame of in-vessel corium modelling, this paper proposes an enhanced integral model in order to simulate the liquid phases stratification transients…”
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    Journal Article
  4. 4

    Study of online measurements techniques of metallic phase spatial distribution into a corium pool by Tisseur, D., Cavaro, M., Rey, F., Paumel, K., Chikhi, N., Delacroix, J., Fouquart, P., Le Tellier, R., Bouyer, V.

    Published in EPJ Web of conferences (2020)
    “…In the context of in-vessel retention (IVR) strategy in order to better assess the risk of reactor vessel failure, the knowledge related to the kinetics of…”
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    Journal Article Conference Proceeding
  5. 5

    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 by Le Tellier, R.

    Published in Nuclear engineering and design (15-12-2021)
    “…In the frame of light water reactors’ severe accidents (SA), the success of a mitigation based on the core melt retention in the vessel lower head largely…”
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    Journal Article
  6. 6

    Modeling of the corium crust of a stratified corium pool during severe accidents in light water reactors by Viot, L., Le Tellier, R., Peybernes, M.

    Published in Nuclear engineering and design (01-11-2020)
    “…•Transient modeling of the mass, temperature and composition of the crust.•Modeling of the fusion of the crust or solidification of the pool.•Modeling of a…”
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    Journal Article
  7. 7

    On the treatment of plane fusion front in lumped parameter thermal models with convection by Le Tellier, R., Skrzypek, E., Saas, L.

    Published in Applied thermal engineering (25-06-2017)
    “…•Solid phase approximations for a two-phase Stefan fusion problem with convection are analyzed.•A reference solution combines integral conservation eqs and a…”
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    Journal Article
  8. 8

    Transient stratification modelling of a corium pool in a LWR vessel lower head by Le Tellier, R., Saas, L., Bajard, S.

    Published in Nuclear engineering and design (01-06-2015)
    “…•A kinetic stratification model is proposed for the simulation of the in-vessel corium behaviour during a LWR severe accident.•The different associated “modes”…”
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    Journal Article
  9. 9

    Phase-field modeling with the TAF-ID of incipient melting and oxygen transport in nuclear fuel during power transients by Introïni, C., Sercombe, J., Ramière, I., Le Tellier, R.

    Published in Journal of nuclear materials (01-12-2021)
    “…•Development of a phase-field model for a two-phase multicomponent system•Coupling of the phase-field model with the TAF-ID•Derivation of a partitioned…”
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    Journal Article
  10. 10

    Chemical Interactions of Molten Steel with (U-Zr-O) Corium: Main Outcomes of the CORDEB Program by Fichot, F., Michel, B., Almjashev, V., Le Guennic, C., Bakouta, N., Le Tellier, R., Piluso, P., Keim, T.

    Published in Nuclear engineering and design (01-03-2022)
    “…•Chemical interactions between (U-Zr-O) molten corium and molten steel are performed to study the impact of temperature difference and presence of crust…”
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    Journal Article
  11. 11

    On the use of CALPHAD-based enthalpy-temperature relations in suboxidized corium plane front solidification modelling by Tiwari, V., Le Tellier, R.

    Published in Annals of nuclear energy (01-07-2018)
    “…The knowledge of in-vessel corium behaviour and the associated risk of vessel failure are matters of prime interest within the framework of Severe Accident…”
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    Journal Article
  12. 12

    Modelling of liquid phase segregation in the Uranium–Oxygen binary system by Cardon, C., Le Tellier, R., Plapp, M.

    Published in Calphad (01-03-2016)
    “…In the uranium–oxygen (U–O) binary system, the existence of a miscibility gap induces the segregation between two immiscible liquid phases at thermodynamic…”
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    Journal Article
  13. 13

    Fast High-Energy X-Ray Imaging for Severe Accidents Experiments on the Future PLINIUS-2 Platform by Berge, L., Estre, N., Tisseur, D., Payan, E., Eck, D., Bouyer, V., Cassiaut-Louis, N., Journeau, C., Le Tellier, R., Singh, S., Pluyette, E.

    Published in IEEE transactions on nuclear science (01-09-2018)
    “…The future PLINIUS-2 platform of the Commissariat à l'Énergie Atomique (CEA) of Cadarache will be dedicated to the study of corium interactions in severe…”
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    Journal Article
  14. 14

    Space–time effects in the initiating phase of sodium fast reactors and their evaluation using a three-dimensional neutron kinetics model by Guyot, M., Gubernatis, P., Le Tellier, R.

    Published in Annals of nuclear energy (01-11-2015)
    “…•A space–time kinetics model has been coupled to a multiple-channel thermal–hydraulics model to simulate the initiating phase of a severe accident for sodium…”
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    Journal Article
  15. 15

    Analysis of an a posteriori error estimator for the transport equation with S N and discontinuous Galerkin discretizations by Fournier, D., Le Tellier, R., Suteau, C.

    Published in Annals of nuclear energy (01-02-2011)
    “…We present an error estimator for the S N neutron transport equation discretized with an arbitrary high-order discontinuous Galerkin method. As a starting…”
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    Journal Article
  16. 16

    Fast high-energy X-ray imaging for Severe Accidents experiments on the future PLINIUS-2 platform by Berge, L., Estre, N., Tisseur, D., Payan, E., Eck, D., Bouyer, V., Cassiaut-Louis, N., Journeau, C., Tellier, R.Le, Pluyette, E.

    Published in EPJ Web of conferences (01-01-2018)
    “…The future PLINIUS-2 platform of CEA Cadarache will be dedicated to the study of corium interactions in severe nuclear accidents, and will host innovative…”
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    Journal Article Conference Proceeding
  17. 17

    Modeling reactivity devices for advanced CANDU reactors using the code DRAGON by Dahmani, M., Marleau, G., Le Tellier, R.

    Published in Annals of nuclear energy (01-05-2008)
    “…Full core analysis of typical power reactors generally performed uses few group diffusion theory, it is necessary to generate beforehand, using a lattice code,…”
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    Journal Article
  18. 18

    Improvements of the reactivity devices modeling for the advanced CANDU reactor by Le Tellier, R., Marleau, G., Dahmani, M., Hébert, A.

    Published in Annals of nuclear energy (01-05-2008)
    “…In the context of the ACR™ (Advanced CANDU Reactor), 3D transport calculations are required in order to simulate the reactivity devices located perpendicularly…”
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    Journal Article
  19. 19

    An efficient preconditioning technique using Krylov subspace methods for 3D characteristics solvers by Dahmani, M., Le Tellier, R., Roy, R., Hébert, A.

    Published in Annals of nuclear energy (01-05-2005)
    “…The Generalized Minimal RESidual ( GMRES) method, using a Krylov subspace projection, is adapted and implemented to accelerate a 3D iterative transport solver…”
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    Journal Article
  20. 20

    Diffuse-interface modelling of multicomponent diffusion and phase separation in the U-O-Zr ternary system by Rasolofomanana, M.A., Cardon, C., Plapp, M., Philippe, Thomas, Henry, H., Le Tellier, R.

    Published in Computational materials science (01-07-2022)
    “…The ternary mixture of uranium, zirconium and oxygen is investigated as a minimal model for corium, the mixture that forms after the meltdown of a nuclear…”
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    Journal Article