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Compressive fatigue of carbon fibers/epoxy laminate: an approach combining residual strength and self-heating
Otavio Zimmermann de Almeida
,
Nicolas Carrère
,
Matthieu Le Saux
,
Sylvie Castagnet
,
Gurvan Moreau
et al.
International Conference on Composite Materials (ICCM 2023), Jul 2023, Belfast, Ireland
Communication dans un congrès
hal-04446797
v1
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Study of the evolution of stresses and associated mechanisms in zirconia growing at high temperature on Zircaloy-4 by use of synchrotron radiation
Adam Bouayoune
,
Raphaelle Guillou
,
Jean-Luc Bechade
,
Elodie Rouesne
,
Dominique Thiaudière
et al.
La Métallurgie, Quel Avenir !, Jun 2023, Grenoble, France
Communication dans un congrès
cea-04596655
v1
|
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Thermomechanical analysis of the high cycle fatigue behavior of a peek CF30 under compressive loadings
Vanessa Kwiatkowski
,
Matthieu Le Saux
,
V. Le Saux
,
S. Leclercq
,
Yann Marco
20th European Conference on Composite Materials: Composites Meet Sustainability, ECCM 2022, Jun 2022, Lausanne (CH), Switzerland. pp.921-925
Communication dans un congrès
hal-04045319
v1
|
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Comportement mécanique d'un revêtement de chrome déposé sur un substrat en alliage de zirconium
Vinh Duc Nguyen
,
Matthieu Le Saux
,
Lionel Gélébart
,
Jean-Christophe Brachet
Colloque Mecamat Aussois 2019 - Rupture des matériaux et des structures, Jan 2019, Aussois, France
Communication dans un congrès
hal-02493915
v1
|
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Etude par diffraction des rayons X in situ sous rayonnement synchrotron de l’oxydation à haute température d’un alliage de zirconium
R. Guillou
,
Matthieu Le Saux
,
René Guinebretière
,
O. Castelnau
,
Jl. Bechade
et al.
Colloque SF2M « La Métallurgie, Quel Avenir !, Apr 2019, Nancy, France
Communication dans un congrès
hal-02442069
v1
|
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Evolutions structurales au sein d'un alliage de zirconium oxyde a haute temperature en diffraction des rayons X in situ au rayonnement synchrotron
R. Guillou
,
Jl. Bechade
,
M. Lesaux
,
R. Guinebretière
,
Olivier Castelnau
et al.
La metallurgie, quel avenir, Apr 2019, Nancy, France
Communication dans un congrès
hal-02411055
v1
|
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Comportement mécanique d'un revêtement de chrome déposé sur un substrat en alliage de zirconium
Vinh Duc Nguyen
,
Matthieu Le Saux
,
Lionel Gélébart
,
Jean-Christophe Brachet
24e Congrès Français de Mécanique, Aug 2019, Brest, France
Communication dans un congrès
hal-02493904
v1
|
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A model to describe the cyclic anisotropic mechanical behavior of short fiber-reinforced thermoplastics
Libor Navratil
,
Louis Leveuf
,
V. Le Saux
,
Yann Marco
,
J. Olhagaray
et al.
24e Congrès Français de Mécanique, Aug 2019, Brest, France
Communication dans un congrès
hal-02493873
v1
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Effect of chromium grain size and morphology on the HT oxidation behavior of chromium coated Zr based alloys
Nihed Chaabane-Jebali
,
Jean-Chistophe Brachet
,
Matthieu Le Saux
,
Didier Hamon
,
Elodie Rouesne
et al.
Materials Science and Engineering - session Structural Materials and Metallurgy, Feb 2019, San Francisco, United States
Communication dans un congrès
cea-02394049
v1
|
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Fatigue criterion for short fiber reinforced thermoplastic (PA66 GF50) over a wide range of load ratios
Prashanth Santharam
,
Yann Marco
,
V. Le Saux
,
Matthieu Le Saux
,
Ida Raoult
et al.
24e Congrès Français de Mécanique, Aug 2019, Brest, France
Communication dans un congrès
hal-02493887
v1
|
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Effect of chromium grain size and morphology on the HT oxidation behavior of chromium coated Zr based alloys
N. Chaabane-Jebali
,
Jc. Brachet
,
M. Lesaux
,
D. Hamon
,
E. Rouesne
et al.
Materials Science and Engineering 2019, Feb 2019, San-Francisco, United States
Communication dans un congrès
hal-02411074
v1
|
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Structural evolutions and internal stresses in Zr alloys during oxidation at high temperature and subsequent cooling
R. Guillou
,
M. Lesaux
,
J.-C. Brachet
,
D. Hamon
,
E. Rouesne
et al.
Thermec 2018 - International Conference on PROCESSING & MANUFACTURING OF ADVANCED MATERIALS, Jul 2018, Paris, France
Communication dans un congrès
cea-02338566
v1
|
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Metallurgical evolutions of zirconium alloys containing high hydrogen contents during cooling from high temperature
T. Le Hong
,
Matthieu Le Saux
,
Jc. Brachet
,
J. Crepin
,
Q. Barres
et al.
Fontevraud 9 - International Symposium on Contribution of Materials Investigations and Operating Experience to Light Water NPPs' Safety, Performance and Reliability, Sep 2018, Avignon, France
Communication dans un congrès
cea-02417242
v1
|
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Behavior of cr-coated m5 claddings during and after high temperature steam oxidationfrom 800c up to 1500c
J.C. Brachet
,
T. Guilbert
,
M. Lesaux
,
J. Rousselot
,
G. Nony
et al.
Topfuel 2018, Sep 2018, Prague, Czech Republic
Communication dans un congrès
cea-02328975
v1
|
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Etude in-situ resolue en temps par diffraction des rayons X sous rayonnement synchrotron des evolutions structurales au sein d'un alliage de zirconium oxyde a haute temperature
R. Guillou
,
M. Lesaux
,
Jl. Bechade
,
R. Guinebretière
,
Olivier Castelnau
et al.
Materiaux 2018, Nov 2018, Strasbourg, France
Communication dans un congrès
cea-02400186
v1
|
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Secondary hydriding of zirconium-based fuel claddings at high temperature (LOCA conditions). Part 2: Effect of high hydrogen contents on metallurgical and mechanical properties. Part 1: Multi-scale study of hydrogen distribution
T. Le Hong
,
Matthieu Le Saux
,
J.-C. Brachet
,
J. Crepin
23rd QUENCH workshop 2017, Oct 2017, Karlsruhe, Germany
Communication dans un congrès
cea-02417311
v1
|
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Behavior of chromium coated M5TM claddings under loca conditions
Jc. Brachet
,
M. Dumerval
,
V. Lezaud-Chailioux
,
Matthieu Le Saux
,
E. Rouesne
et al.
WRFPM 2017 Water Reactor Fuel Performance Meeting, Sep 2017, Jeju, South Korea
Communication dans un congrès
hal-02419638
v1
|
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Evolution des contraintes internes generees au sein d'un alliage de Zr oxyde a haute temperature puis refroidi
R. Guillou
,
Matthieu Le Saux
,
Jc. Brachet
,
E. Rouesne
,
D. Hamon
et al.
12eme Colloque Rayons X et Matiere (RX - 2017), Nov 2017, Lille, France
Communication dans un congrès
hal-02417370
v1
|
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Structural evolutions in zr alloys during oxidation at high temperature andsubsequent cooling
R. Guillou
,
M. Lesaux
,
J.-C. Brachet
,
T. Guilbert
,
E. Rouesne
et al.
ICNMNE International Conference on Nuclear Materials and Nuclear Engineering, Jan 2017, Londres, United Kingdom
Communication dans un congrès
hal-02419674
v1
|
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behavior of chromium coated m5tm claddings under loca conditions
Jc. Brachet
,
M. Dumerval
,
V. Lezaud-Chaillioux
,
Matthieu Le Saux
,
E. Rouesne
et al.
WRFPM2017 Water Reactor Fuel Performance Meeting, Sep 2017, Jeju-do, South Korea
Communication dans un congrès
hal-02417726
v1
|
|
Mechanical behavior at high temperature of highly oxygen- or hydrogen-enriched $\alpha$ and (prior-)$\beta$ phases of zirconium alloys
I. Turque
,
R. Chosson
,
M. Le Saux
,
J. C. Brachet
,
V. Vandenberghe
et al.
18th International Symposium on Zirconium in the Nuclear Industry, May 2016, Hilton Head, United States
Communication dans un congrès
hal-02441977
v1
|
|
Mechanical behavior at high temperature of highly oxygen- or hydrogen-enriched α and (prior-) $\beta$ phases of zirconium alloys
I. Turque
,
R. Chosson
,
Matthieu Le Saux
,
J.-C. Brachet
,
V. Vandenberghe
et al.
18th International Symposium on Zirconium in the Nuclear Industry, May 2016, Hilton Head, United States
Communication dans un congrès
cea-02442337
v1
|
|
CEA studies on High temperature oxidation and hydriding of Zr based nuclear fuel claddings upon LOCA transients phenomenology, mechanisms and modelling => consequences on mechanical properties
J.-C. Brachet
,
Matthieu Le Saux
,
C. Toffolon-Masclet
Séminaire scientifique DEN sur la corrosion dans les REP - Corrosion in pressurized water reactors: phenomenology, mechanisms and modelling, Oct 2016, Saclay, France
Communication dans un congrès
cea-02438347
v1
|
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Out-of-pile RandD on chromium coated nuclear fuel zirconium based claddings for enhanced accident tolerance in LWRs
J.-C. Brachet
,
I. Idarraga
,
M. Le Flem
,
Matthieu Le Saux
,
F. Schuster
et al.
18th International Symposium on Zirconium in the Nuclear Industry, May 2016, Hilton Head, United States
Communication dans un congrès
cea-02500847
v1
|
|
Mechanical behavior at high temperatures of highly oxygen- or hydrogen-enriched α and (Prior-) β phases of zirconium alloys
Isabelle Turque
,
Raphaël Chosson
,
Matthieu Le Saux
,
Jean-Christophe Brachet
,
Valérie Vandenberghe
et al.
18th International symposium on zirconium in the nuclear industry, May 2016, Hilton Head Island, SC, United States. pp.240-280, ⟨10.1520/STP159720160063⟩
Communication dans un congrès
hal-01702107
v1
|
|
Internal stresses and structural evolutions in zr alloys during oxidation at high temperature and subsequent cooling
R. Guillou
,
M. Lesaux
,
J.-C. Brachet
,
T. Guilbert
,
D. Menut
et al.
NuMat2016 The Nuclear Materials Conference, Nov 2016, Montpellier, France
Communication dans un congrès
hal-02441982
v1
|
|
Behavior under LOCA conditions of Enhanced Accident Tolerant Chromium Coated Zircaloy-4 Claddings
J.-C. Brachet
,
Matthieu Le Saux
,
V. Lezaud-Chaillioux
,
M. Dumerval
,
Q. Houmaire
et al.
Topfuel 2016 - Light Water Reactor (LWR) Fuel Performance Meeting, Sep 2016, Boise, United States
Communication dans un congrès
cea-02438712
v1
|
|
On-going studies at CEA on chromium coated zirconium based nuclear fuel claddings for enhanced accident tolerant LWRS fuel
F. Schuster
,
F. Lomello
,
Alain Billard
,
G. Velisa
,
E. Monsifrot
et al.
TopFuel 2015 - Reactor Fuel Performance Meeting, Sep 2015, Zurich, Switzerland
Communication dans un congrès
cea-02492582
v1
|
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Influence of Steam Pressure on the High Temperature Oxidation and Post-Cooling Mechanical Properties of Zircaloy-4 and M5 Cladding (LOCA Conditions)
Matthieu Le Saux
,
Valérie Vandenberghe
,
Patrice Crébier
,
Jean-Christophe Brachet
,
Didier Gilbon
et al.
Communication dans un congrès
hal-04446274
v1
|
|
Chromium coated nuclear fuel claddings for enhanced Accident Tolerant LWRs Fuel (DBA-LOCA and slightly beyond DBA-LOCA conditions
J. C. Brachet
,
M. Le Saux
,
T. Guilbert
,
S. Urvoy
,
E. Rouesne
et al.
Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, IAEA, Oct 2014, Oak Ridge, United States
Communication dans un congrès
cea-02875113
v1
|
|
Assessment at CEA of coated nuclear fuel cladding for LWRs with increasing margins in LOCA and beyond LOCA conditions
Isabel Idarraga-Trujillo
,
Marion Le Flem
,
Jean-Christophe Brachet
,
Matthieu Le Saux
,
Didier Hamon
et al.
LWR Fuel Performance Meeting / TopFuel 2013, Sep 2013, Charlotte, NC, United States. pp.860-867
Communication dans un congrès
hal-04446951
v1
|
|
Loss of Coolant Accident Testing Round Robin
Ken Yueh
,
R.J. Comstock
,
B. Dunn
,
Matthieu Le Saux
,
Y.P. Lin
et al.
TopFuel 2013, Sep 2013, Charlotte, NC, United States. pp.550-556
Communication dans un congrès
hal-04447101
v1
|
|
Sensitivity to chemical composition variations and heating/oxidation mode of the breakaway oxidation in M5® cladding steam oxidized at 1000°C (LOCA conditions)
Valérie Vandenberghe
,
Jean-Christophe Brachet
,
Matthieu Le Saux
,
Didier Gilbon
,
Jean Paul Mardon
et al.
TopFuel 2012, Sep 2012, Manchester, United Kingdom
Communication dans un congrès
hal-04447119
v1
|
|
Influence of Pre-Transient Oxide on LOCA High Temperature Steam Oxidation and Post-Quench Mechanical Properties of Zircaloy-4 and M5™ cladding
Matthieu Le Saux
,
Jean-Christophe Brachet
,
Valérie Vandenberghe
,
Didier Gilbon
,
Jean Paul Mardon
et al.
2011 Water Reactor Fuel Performance Meeting, Sep 2011, Chengdu, China
Communication dans un congrès
hal-04447298
v1
|
|
Finite Element Modeling of Ring Compression Tests on Post-quenched Single Side Oxidized Zirconium-based Alloys (LOCA conditions)
Andrea Cabrera
,
Valérie Vandenberghe
,
Jacques Besson
,
Matthieu Le Saux
,
Jean-Christophe Brachet
et al.
International Topical Meeting on Light Water Reactor Fuel Performance, Sep 2010, Orlando, United States. pp.261-269
Communication dans un congrès
hal-04447331
v1
|
|
1D and 3D modelling of PCMI during a RIA with ALCYONE v1.1
Jérôme Sercombe
,
Éric Fédérici
,
Matthieu Le Saux
,
Bruno Michel
,
Christophe Poussard
International Topical Meeting on Light Water Reactor Fuel Performance, Sep 2010, Orlando, United States. pp.307-318
Communication dans un congrès
hal-04447310
v1
|
|
Influence of the Cooling Scenario on the Post-Quench Mechanical Properties of Pre-Hydrided Zircaloy-4 Fuel Claddings after high Temperature Steam Oxidation (LOCA Conditions)
Valérie Vandenberghe
,
Matthieu Le Saux
,
Jean-Christophe Brachet
,
Didier Gilbon
,
Jean-Paul Mardon
et al.
International Topical Meeting on Light Water Reactor Fuel Performance, Sep 2010, Orlando, United States. pp.270-277
Communication dans un congrès
hal-04447319
v1
|
|
Ductility and Failure Behaviour of both Unirradiated and Irradiated Zircaloy-4 Cladding Using Plane Strain Tensile Specimens
Sébastien Carassou
,
Matthieu Le Saux
,
J.P. Pizzanelli
,
Olivier Rabouille
,
Xavier Averty
et al.
OECD/NEA Workshop on the Behaviour of Nuclear Reactor Fuel during Reactivity Initiated Accidents, Sep 2009, Paris, France
Communication dans un congrès
hal-04447354
v1
|
|
Failure of hydrided zircaloy-4 fuel cladding tubes under RIA loading conditions
Matthieu Le Saux
,
Jacques Besson
,
Sébastien Carassou
,
Christophe Poussard
,
Xavier Averty
ECF 17, Sep 2008, Brno, Czech Republic. pp.2047-2054
Communication dans un congrès
hal-00329805
v1
|
|
High temperature expansion due to compression test for the determination of a cladding material failure criterion under RIA loading conditions
Matthieu Le Saux
,
Christophe Poussard
,
Xavier Averty
,
Claude Sainte Catherine
,
Jacques Besson
International Topical Meeting on Light Water Reactor Fuel Performance, Sep 2007, San Francisco, United States
Communication dans un congrès
hal-04447381
v1
|
|
A model to describe the anisotropic viscoplastic mechanical behavior of fresh and irradiated Zircaloy-4 fuel claddings under RIA loading conditions
Matthieu Le Saux
,
Christophe Poussard
,
Xavier Averty
,
Claude Sainte Catherine
,
Jacques Besson
9th International Conference on Structural Mechanics in Reactor Technology, Sep 2007, San Francisco, United States
Communication dans un congrès
hal-04447388
v1
|