On the construction of multiresolution analyses Associated to general subdivision schemes
Zhiqing Kui
,
Jean Baccou
,
Jacques Liandrat
Article dans une revue
hal-03377373v1
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A 3D model to solve U-tube steam generator secondary side thermal-hydraulics with coupled primary-to-secondary side heat transfer
Daniele Vivaldi
Article dans une revue
hal-03397632v1
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Experimental study of solid/liquid thermal shock in carbon dioxide
Jean Muller
,
Romuald Rulliere
,
Pierre Ruyer
,
Marc Clausse
5th International Conference on Multiphase Flow and Heat Transfer (ICMFHT'20), ICMFHT , Apr 2020, EN LIGNE, France.
⟨10.11159/icmfht20.11⟩
Communication dans un congrès
hal-03107893v1
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Mechanistic modeling of the thermal-hydraulics in polydispersed flow film boiling in LOCA conditions
A.V.S. Oliveira
,
J.D. Peña Carrillo
,
Alexandre Labergue
,
T. Glantz
,
Michel Gradeck
Article dans une revue
hal-02433846v1
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Gas-assisted discharge flow of granular media from silos
Yixian Zhou
,
Pierre-Yves Lagrée
,
Stéphane Popinet
,
P. Ruyer
,
P. Aussillous
Article dans une revue
hal-02390428v1
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Quantification of the uncertainty of the physical models in the systemthermal-hydraulic codes – PREMIUM benchmark
Tomasz Skorek
,
A. de Crecy
,
Andriy Kovtonyuk
,
Alessandro Petruzzi
,
Rafael Mendizabal
,
et al.
Article dans une revue
hal-02870743v1
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Expert system: a decision support tool for fire safety analysis in nuclear area
William Plumecocq
,
Eric Chojnacki
,
Jean Paul Joret
,
Jocelyne Lacoue
,
Jerome Richard
16th International Post-Conference Seminar on “FIRE SAFETY IN NUCLEAR POWER PLANTS AND INSTALLATI SMiRT Post-Conference Fire Seminar, SMIRT , Oct 2019, OTTAWA, Canada
Communication dans un congrès
hal-03739086v1
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EXPERT SYSTEM: A DECISION SUPPORT TOOL FOR FIRE SAFETY ANALYSIS IN NUCLEAR AREA
William Plumecocq
,
Eric Chojnacki
,
Laurent Audouin
International Workshop on Developments in Safety Assessment Approaches and Safety Management Practices of Fuel Cycle Facilities, OECD/NEA/CSNI/WGFCS , Oct 2019, PARIS, France
Communication dans un congrès
hal-02635642v1
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Étude expérimentale du transfert paroi/fluide dans le cas d’un écoulement vertical vapeur/gouttes dans une géométrie tubulaire
Juan David Peña Carrillo
Mécanique des fluides [physics.class-ph]. Université de Lorraine, 2018. Français.
⟨NNT : 2018LORR0193⟩
Thèse
tel-01984680v1
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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.
Article dans une revue
hal-02881798v1
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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.
Article dans une revue
hal-02881800v1
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Simulation of the OECD/NEA Sandia Fuel Project Phases I and II ignition tests with DRACCAR
O. de Luze
,
F. Jacq
,
G. Guillard
Article dans une revue
hal-02871806v1
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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-04474794v1
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Ejection de gaz et de grains suite à la rupture d'un crayon de combustible nucléaire : modélisation de la dynamique
Yixian Zhou
Mécanique des fluides [physics.class-ph]. Aix-Marseille Université, 2016. Français.
⟨NNT : 2016AIXM4731⟩
Thèse
tel-04387343v1
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Thermal hydraulics behavior of a rod bundle with partially blocked area during the reflooding phase of the Loss Of Cooling Accident
Georges Repetto
,
Benoit Bruyère
,
Stephane Eymery
,
Tony Glantz
NUTHOS-11: The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety , American Nuclear Society and Korean Nuclear Society, Oct 2016, Gyeongju, South Korea
Communication dans un congrès
irsn-04474648v1
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Modelling the dynamics of ambient dose rates induced by radiocaesium in the Fukushima terrestrial environment
M.-A. Gonze
,
C. Mourlon
,
P. Calmon
,
E. Manach
,
C. Debayle
,
et al.
Article dans une revue
hal-03121056v1
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CORE COOLABILITY IN LOSS OF COOLANT ACCIDENT: THE COAL EXPERIMENTS
Georges Repetto
,
Christophe Marquié
,
Benoit Bruyère
,
Tony Glantz
16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2016 , American Nuclear Society, Aug 2015, CHICAGO, United States
Communication dans un congrès
irsn-04474816v1
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Degradation and oxidation of B4C control rod segments at high temperatures. A review and code interpretation of the BECARRE program
O. de Luze
Article dans une revue
hal-03111580v1
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Interprétation des résultats de surveillance individuelle des expositions professionnelles au dioxyde d'uranium « Proposition de dosimétrie collective »
N. Blanchin
,
E. Davesne
,
E. Chojnacki
,
L. Touri
,
M. Ruffin
,
et al.
Article dans une revue
hal-02733858v1
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