Gaétan Guillard

12
Documents
Affiliation actuelle
  • Laboratoire d'étude et de modélisation du combustible (IRSN/PSN-RES/SEMIA/LEMC)
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Publications

Publications

Image document

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-02871806 v1
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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. Guillard et al.
Nuclear Engineering and Design, 2018, 339, pp.269-285. ⟨10.1016/j.nucengdes.2018.06.022⟩
Article dans une revue hal-02881798 v1
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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. Guillard et al.
Nuclear Engineering and Design, 2018, 339, pp.202-214. ⟨10.1016/j.nucengdes.2018.08.031⟩
Article dans une revue hal-02881800 v1

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-02572583 v1

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-02614037 v1

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-03113310 v1

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-02974264 v1

Recent advances in ASTEC validation on circuit thermal-hydraulic and core degradation

G. Bandini , M. Buck , W. Hering , L. Godin-Jacqmin , G. Ratel et al.
Progress in Nuclear Energy, 2010, 52 (1), pp.148-157. ⟨10.1016/j.pnucene.2009.09.008⟩
Article dans une revue istex hal-02972633 v1

Validation status of the ASTEC integral code for severe accident simulation

J.P. van Dorsselaere , P. Chatelard , M. Cranga , G. Guillard , N. Tregoures et al.
Nuclear Technology, 2010, 170 (3), pp.397-415. ⟨10.13182/NT10-A10326⟩
Article dans une revue hal-02974276 v1

ASTEC application to in-vessel corium retention

D. Tarabelli , G. Ratel , R. Pélisson , G. Guillard , M. Barnak et al.
Nuclear Engineering and Design, 2009, 239 (7), pp.1345-1353. ⟨10.1016/j.nucengdes.2009.02.021⟩
Article dans une revue istex hal-02988578 v1
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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-04474794 v1

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-05223548 v1