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bruno MICHEL
bruno MICHEL
CEA, DEN
Adresse e-mail validée de cea.fr
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Introducing the open-source mfront code generator: Application to mechanical behaviours and material knowledge management within the PLEIADES fuel element modelling platform
T Helfer, B Michel, JM Proix, M Salvo, J Sercombe, M Casella
Computers & Mathematics with Applications 70 (5), 994-1023, 2015
1402015
3D fuel cracking modelling in pellet cladding mechanical interaction
B Michel, J Sercombe, G Thouvenin, R Chatelet
Engineering fracture mechanics 75 (11), 3581-3598, 2008
1072008
Simulation of pellet-cladding interaction with the pleiades fuel performance software environment
B Michel, C Nonon, J Sercombe, F Michel, V Marelle
Nuclear Technology 182 (2), 124-137, 2013
842013
A new phenomenological criterion for pellet–cladding interaction rupture
B Michel, J Sercombe, G Thouvenin
Nuclear Engineering and Design 238 (7), 1612-1628, 2008
672008
GERMINAL, a fuel performance code of the PLEIADES platform to simulate the in-pile behaviour of mixed oxide fuel pins for sodium-cooled fast reactors
M Lainet, B Michel, JC Dumas, M Pelletier, I Ramière
Journal of Nuclear Materials 516, 30-53, 2019
652019
Formulation of a new intergranular creep damage model for austenitic stainless steels
B Michel
Nuclear Engineering and Design 227 (2), 161-174, 2004
392004
A16: guide for defect assessment at elevated temperature
B Drubay, S Marie, S Chapuliot, MH Lacire, B Michel, H Deschanels
International journal of pressure vessels and piping 80 (7-8), 499-516, 2003
362003
Power plant conceptual study—WCLL concept
P Sardain, B Michel, L Giancarli, AL Puma, Y Poitevin, J Szczepanski, ...
Fusion engineering and design 69 (1-4), 769-774, 2003
352003
Two fuel performance codes of the PLEIADES platform: ALCYONE and GERMINAL
B Michel, I Ramière, I Viallard, C Introini, M Lainet, N Chauvin, V Marelle, ...
Nuclear Power Plant Design and Analysis Codes, 207-233, 2021
302021
Modeling of pellet cladding interaction
B Michel, J Sercombe, C Nonon, O Fandeur
Comprehensive Nuclear Materials 3, 677-712, 2012
302012
Creep crack initiation and creep crack growth assessments in welded structures
A Assire, B Michel, M Raous
Nuclear Engineering and Design 206 (1), 45-56, 2001
302001
ALCYONE: the PLEIADES fuel performance code dedicated to multidimensional PWR studies
G Thouvenin, JM Ricaud, B Michel, D Plancq, P Thevenin
Proceedings of Top Fuel, 2006
292006
Multi-dimensional modeling of PCMI during base irradiation and ramp testing with ALCYONE V1. 1
J Sercombe, B Michel, B Petitprez, R Chatelet, C Nonon, G Thouvenin, ...
Top Fuel 2009, Paris, France, 2009
282009
Multidimensional modeling of a ramp test with the PWR fuel performance code ALCYONE
G Thouvenin, B Michel, J Sercombe, D Plancq, P Thévenin
Proceedings of the 2007 LWR Fuel Performance Meeting/TopFuel 2007'Zero by 2010', 2007
282007
Crystal viscoplastic modeling of UO2 single crystal
L Portelette, J Amodeo, R Madec, J Soulacroix, T Helfer, B Michel
Journal of Nuclear Materials 510, 635-643, 2018
222018
A new numerical methodology for simulation of unstable crack growth in time independent brittle materials
B Michel, T Helfer, I Ramière, C Esnoul
Engineering Fracture Mechanics 188, 126-150, 2018
212018
1D and 3D modeling of PCMI during a RIA with ALCYONE V1. 1
J Sercombe, E Fédérici, M Le Saux, B Michel, C Poussard
International Topical Meeting on Light Water Reactor Fuel Performance …, 2010
192010
Conceptual design of a high temperature water-cooled divertor for a fusion power reactor
L Giancarli, JP Bonal, AL Puma, B Michel, P Sardain, JF Salavy
Fusion engineering and design 75, 383-386, 2005
162005
Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment
L Luzzi, T Barani, B Boer, L Cognini, A Del Nevo, M Lainet, S Lemehov, ...
Nuclear Engineering and Technology 53 (10), 3367-3378, 2021
152021
D7. 2–Incorporation and verification of models and properties in fuel performance codes
P Van Uffelen, A Schubert, L Luzzi, T Barani, A Magni, D Pizzocri, ...
152020
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