Bénédicte MICHEL

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Publications

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Publications

Chemical Interactions of Molten Steel with (U-Zr-O) Corium: Main Outcomes of the CORDEB Program

Florian Fichot , Bénédicte Michel , V. Almjashev , C. Le Guennic , N. Bakouta et al.
Nuclear Engineering and Design, 2022, 388, pp.111588. ⟨10.1016/j.nucengdes.2021.111588⟩
Article dans une revue irsn-04665848 v1

Morphology and phase distributions of molten core in a reactor vessel

Jinho Song , Sangmo An , Jong-Yun Kim , M. Barrachin , B. Piar et al.
Journal of Nuclear Materials, 2020, 542, pp.152471. ⟨10.1016/j.jnucmat.2020.152471⟩
Article dans une revue hal-05423866 v1

Experimental study of oxidic-metallic melt oxidation

Andrey Sulatsky , Viacheslav Almjashev , Vladimir Granovsky , Vladimir Khabensky , Evgeniy Krushinov et al.
Nuclear Engineering and Design, 2020, 363, pp.110618. ⟨10.1016/j.nucengdes.2020.110618⟩
Article dans une revue irsn-04665606 v1

Experimental study of transient phenomena in the three-liquid oxidic-metallic corium pool

V.I. Almjashev , V.S. Granovsky , V.B. Khabensky , S.Y. Kotova , E.V. Krushinov et al.
Nuclear Engineering and Design, 2018, 332, pp.31-37. ⟨10.1016/j.nucengdes.2018.03.004⟩
Article dans une revue istex hal-02874505 v1

New set of convective heat transfer coefficients established for pools and validated against CLARA experiments for application to corium pools

B. Michel
Nuclear Engineering and Design, 2015, 286, pp.278-285. ⟨10.1016/j.nucengdes.2015.02.013⟩
Article dans une revue istex hal-02570473 v1

Towards an European consensus on possible causes of MCCI ablation anisotropy in an oxidic pool

M. Cranga , C. Spengler , K. Atkhen , A. Fargette , M. Fischer et al.
Annals of Nuclear Energy, 2014, 74 (C), pp.72-88. ⟨10.1016/j.anucene.2014.07.017⟩
Article dans une revue istex hal-02641702 v1

Interpretation and calculations for the first series of tests for the ARTEMIS program (corium-concrete interaction with simulating materials)

B. Michel , M. Cranga
Nuclear Engineering and Design, 2009, 239 (3), pp.600-610. ⟨10.1016/j.nucengdes.2008.11.011⟩
Article dans une revue istex hal-02985065 v1

Experimental contribution to the determination of the In-Zr system for severe nuclear accident assessment

Sandra Gyasi , Marc Lomello-Tafin , Pierre Benigni , Marc Barrachin , Caroline Antion et al.
19e conférence "Thermodynamics of Alloys", Dr Olivier Dezellus, Président du comité d’organisation de TOFA 2024, Sep 2024, Lyon (Université Lumière Lyon 2), France
Communication dans un congrès hal-04988404 v1
Image document

Steam Oxidation of M5 Framatome * in the 900-1200°C Temperature Range

Severine Guilbert , Jean Desquines , Benedicte Michel , Pauline Lacote , Alice Viretto
21th International Symposium on Zirconium in the Nuclear Industry, Apr 2025, Aix en Provence, France
Poster de conférence hal-05445414 v1

A SARNET Benchmark on two VULCANO Molten Core Concrete Interaction Tests

Christophe Journeau , Jean-François Haquet , B Letexier , A Greco , Bertrand Spindler et al.
5th European Review meeting on Severe Accident Research (ERMSAR-2012), Mar 2012, Cologne, Allemagne, Germany. 2012
Proceedings/Recueil des communications hal-05423981 v1

Outcome of the available 2D MCCI database for the reactor case in dry conditions

Michel Cranga , Bénédicte Michel , Christian Mun , Marc Barrachin
MCCI-OECD seminar, Nov 2010, Cadarache, France. 2010
Proceedings/Recueil des communications hal-05424028 v1

Interpretation of real material 2D MCCI experiments in homogeneous oxidic pool with the ASTEC/MEDICIS code

Michel Cranga , Christian Mun , Bénédicte Michel , Fabien Duval , Marc Barrachin
2008 International Congress on Advances in Nuclear Power Plants - ICAPP '08, Jun 2008, Anaheim (California), United States. 2008
Proceedings/Recueil des communications hal-05423913 v1

Relative impact of MCCI modeling uncertainties on reactor basemat ablation kinetics

Michel Cranga , Christian Mun , Bénédicte Michel , Fabien Duval
OECD-MCCI seminar, Oct 2007, Cadarache, France. 2007
Proceedings/Recueil des communications hal-05424050 v1