Gaétan Guillard

Identifiants chercheurs

IdHAL :

gaetan-guillard

ORCID :

0000-0003-0654-7253

Publications

Article dans une revue (10)

Simulation of the OECD/NEA Sandia Fuel Project Phases I and II ignition tests with DRACCAR O. de Luze,F. Jacq,G. Guillard Nuclear Engineering and Design, 2018, 330, pp.524-537. ⟨10.1016/j.nucengdes.2018.01.047⟩ Article dans une revue hal-02871806v1
DRACCAR A multi-physics code for computational analysis of multi-rod ballooning and fuel relocation during LOCA transients Part one General modeling description T. Glantz,T. Taurines,O. de Luze,S. Belon,G. Guillardet al. Nuclear Engineering and Design, 2018, 339, pp.269-285. ⟨10.1016/j.nucengdes.2018.06.022⟩ Article dans une revue hal-02881798v1
DRACCAR A multi-physics code for computational analysis of multi-rod ballooning and fuel relocation during LOCA transients. Part Two Overview of modeling capabilities for LOCA T. Glantz,T. Taurines,O. de Luze,S. Belon,G. Guillardet al. Nuclear Engineering and Design, 2018, 339, pp.202-214. ⟨10.1016/j.nucengdes.2018.08.031⟩ Article dans une revue hal-02881800v1
Development and validation of the multi-physics DRACCAR code S. Bascou,O. de Luze,S. Ederli,G. Guillard Annals of Nuclear Energy, 2015, 84, pp.1-18. ⟨10.1016/j.anucene.2014.09.040⟩ Article dans une revue hal-02572583v1
ASTEC adaptation for PHWR limited core damage accident analysis P. Majumdar,B. Chatterjee,H.G. Lele,G. Guillard,F. Fichot Nuclear Engineering and Design, 2014, 272, pp.273-286. ⟨10.1016/j.nucengdes.2013.10.011⟩ Article dans une revue istex hal-02614037v1
Multi-pin ballooning during LOCA transient: A three-dimensional analysis J.-M. Ricaud,N. Seiler,G. Guillard Nuclear Engineering and Design, 2013, 256, pp.45-55. ⟨10.1016/j.nucengdes.2012.11.013⟩ Article dans une revue istex hal-03113310v1
Reactor cooling systems thermal-hydraulic assessment of the ASTEC V1.3 code in support of the French IRSN PSA-2 on the 1300 MWe PWRs N. Tregoures,M. Philippot,L. Foucher,G. Guillard,J. Fleurot Nuclear Engineering and Design, 2010, 240 (6), pp.1468-1486. ⟨10.1016/j.nucengdes.2010.02.010⟩ Article dans une revue istex hal-02974264v1
Recent advances in ASTEC validation on circuit thermal-hydraulic and core degradation G. Bandini,M. Buck,W. Hering,L. Godin-Jacqmin,G. Ratelet al. Progress in Nuclear Energy, 2010, 52 (1), pp.148-157. ⟨10.1016/j.pnucene.2009.09.008⟩ Article dans une revue istex hal-02972633v1
Validation status of the ASTEC integral code for severe accident simulation J.P. van Dorsselaere,P. Chatelard,M. Cranga,G. Guillard,N. Tregoureset al. Nuclear Technology, 2010, 170 (3), pp.397-415. ⟨10.13182/NT10-A10326⟩ Article dans une revue hal-02974276v1
ASTEC application to in-vessel corium retention D. Tarabelli,G. Ratel,R. Pélisson,G. Guillard,M. Barnaket al. Nuclear Engineering and Design, 2009, 239 (7), pp.1345-1353. ⟨10.1016/j.nucengdes.2009.02.021⟩ Article dans une revue istex hal-02988578v1

Communication dans un congrès (2)

CORE COOLABILITY IN LOSS OF COOLANT ACCIDENT: THE COAL EXPERIMENTS INVESTIGATING THE THERMAL HYDRAULICS OF A ROD BUNDLE WITH BLOCKED AREA DURING THE REFLOODING Georges Repetto,Tony Glantz,Gaétan Guillard,Benoit Bruyère,Quentin Grando 2017 International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), American Nuclear Society, Sep 2017, Xi’an, China Communication dans un congrès irsn-04474794v1
Oxygen diffusion and partially blocked bundle reflooding simulation using DRACCAR Sophie Bascou,Severine Guilbert,Gaétan Guillard LWR Fuel Performance Meeting, Top Fuel 2013, American Nuclear Society - ANS, Sep 2013, Charlotte, United States. pp.535-542 Communication dans un congrès hal-05223548v1