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
Conference papers
cea-02500847v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
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⟩
Conference papers
hal-01702107v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
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
Conference papers
cea-02438712v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
High temperature steam oxidation of chromium-coated zirconium-based alloys: Kinetics and process
J.-C. Brachet
,
E. Rouesne
,
J. Ribis
,
T. Guilbert
,
S. Urvoy
,
et al.
Journal articles
hal-02520055v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
Breakaway oxidation of zirconium alloys exposed to steam around 1000 °C
Matthieu Le Saux
,
Jean-Christophe Brachet
,
Valérie Vandenberghe
,
Antoine Ambard
,
Raphaël Chosson
Journal articles
hal-02924036v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
Comportement et rupture de gaines en zircaloy-4 détendu vierges, hydrurées ou irradiées en situation accidentelle de type RIA
Matthieu Le Saux
Mécanique [physics.med-ph]. École Nationale Supérieure des Mines de Paris, 2008. Français.
⟨NNT : 2008ENMP1608⟩
Theses
tel-00395361v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
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
Conference papers
hal-02493887v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
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
Conference papers
hal-02442069v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
A model to describe the mechanical behavior and the ductile failure of hydrided Zircaloy-4 fuel claddings between 25 °C and 480 °C
Matthieu Le Saux
,
Jacques Besson
,
Sébastien Carassou
Journal articles
hal-01199626v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors
Jean-Christophe Brachet
,
Isabel Idarraga-Trujillo
,
Marion Le Flem
,
Matthieu Le Saux
,
Valérie Vandenberghe
,
et al.
Journal articles
hal-02090215v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
Combined effects of temperature and of high hydrogen and oxygen contents on the mechanical behavior of a zirconium alloy upon cooling from the βZr phase temperature range
Thai Le Hong
,
Jean-Christophe Brachet
,
Jérôme Crépin
,
Matthieu Le Saux
Journal articles
hal-03327638v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
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
Conference papers
cea-02438347v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
Fatigue criteria for short fiber-reinforced thermoplastic validated over various fiber orientations, load ratios and environmental conditions
Prashanth Santharam
,
Yann Marco
,
V. Le Saux
,
Matthieu Le Saux
,
Gilles Robert
,
et al.
Journal articles
hal-03270375v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
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
Conference papers
cea-02417242v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
Effect of a pre-oxide on the high temperature steam oxidation of Zircaloy-4 andM5 alloys
Matthieu Le Saux
,
J.C. Brachet
,
V. Vandenberghe
,
E. Rouesne
,
S. Urvoy
,
et al.
Journal articles
hal-02149361v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
Phase transformations during cooling from the βZr phase temperature domain in several hydrogen-enriched zirconium alloys studied by in situ and ex situ neutron diffraction
Thai Le Hong
,
Isabelle Turque
,
Jean-Christophe Brachet
,
Jérôme Crépin
,
Gilles André
,
et al.
Journal articles
hal-02956376v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
Evaluation of Equivalent Cladding Reacted parameters of Cr-coated claddings oxidized in steam at 1200 °C in relation with oxygen diffusion/partitioning and post-quench ductility
J. C. Brachet
,
Matthieu Le Saux
,
J. Bischoff
,
H. Palancher
,
Raphaël Chosson
,
et al.
Journal articles
hal-02639341v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
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
Conference papers
cea-02442337v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
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
Conference papers
hal-02441977v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
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
Conference papers
hal-04045319v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
High-temperature oxidation resistance of chromium-based coatings deposited by DLI-MOCVD for enhanced protection of the inner surface of long tubes
Alexandre Michau
,
Francis Maury
,
Frédéric Schuster
,
Fernando Lomello
,
Jean-Christophe Brachet
,
et al.
Journal articles
hal-02051246v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
Study of secondary hydriding at high temperature in zirconium based nuclear fuel cladding tubes by coupling information from neutron radiography/tomography, electron probe micro analysis, micro elastic recoil detection analysis and laser induced breakdown spectroscopy microprobe
J.C. Brachet
,
Didier Hamon
,
Matthieu Le Saux
,
V Vandenberghe
,
C C Toffolon-Masclet
,
et al.
Journal articles
cea-01488896v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
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
Conference papers
cea-02394049v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
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
Conference papers
hal-02493873v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
A model to describe the anisotropic viscoplastic mechanical behavior of fresh and irradiated Zircaloy-4 fuel claddings under RIA loading conditions
Matthieu Le Saux
,
Jacques Besson
,
S. Carassou
,
C. Poussard
,
X. Averty
Journal articles
hal-00311854v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
In-situ time-resolved study of structural evolutions in a zirconium alloy during high temperature oxidation and cooling
R. Guillou
,
Matthieu Le Saux
,
E. Rouesne
,
D. Hamon
,
C. Toffolon-Masclet
,
et al.
Journal articles
hal-02431028v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
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
Conference papers
cea-02875113v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
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
Conference papers
hal-02417726v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
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
,
R. Guillou
,
Béchade Jean-Luc
,
E. Rouesne
,
Jean-Luc Grosseau-Poussard
,
et al.
Journal articles
hal-04161374v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More
DLI-MOCVD Crx Cy coating to prevent Zr-based cladding from inner oxidation and secondary hydriding upon LOCA conditions
J.C. Brachet
,
S. Urvoy
,
E. Rouesne
,
G. Nony
,
M. Dumerval
,
et al.
Journal articles
hal-03212406v1
Actions
Share
Gmail
Facebook
Twitter
LinkedIn
More