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-04665848v1

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-05423866v1

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-04665606v1

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-02874505v1

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-02570473v1

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-02641702v1

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-02985065v1

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-04988404v1
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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-05445414v1

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-05423981v1

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-05424028v1

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-05423913v1

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-05424050v1