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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
Conference papers cea-02500847v1
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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
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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
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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.
Corrosion Science, 2020, ⟨10.1016/j.corsci.2020.108537⟩
Journal articles hal-02520055v1
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Breakaway oxidation of zirconium alloys exposed to steam around 1000 °C

Matthieu Le Saux , Jean-Christophe Brachet , Valérie Vandenberghe , Antoine Ambard , Raphaël Chosson
Corrosion Science, 2020, 176 (108936), pp.1-21. ⟨10.1016/j.corsci.2020.108936⟩
Journal articles hal-02924036v1
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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
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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
Conference papers hal-02493887v1

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

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 of Nuclear Materials, 2015, 466, pp.43-55. ⟨10.1016/j.jnucmat.2015.07.026⟩
Journal articles hal-01199626v1
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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 of Nuclear Materials, 2019, 517, pp.268-285. ⟨10.1016/j.jnucmat.2019.02.018⟩
Journal articles hal-02090215v1
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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 of Nuclear Materials, 2021, 554 (554), pp.153069. ⟨10.1016/j.jnucmat.2021.153069⟩
Journal articles hal-03327638v1
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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
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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.
International Journal of Fatigue, 2020, 135, pp.105574. ⟨10.1016/j.ijfatigue.2020.105574⟩
Journal articles hal-03270375v1
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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
Conference papers cea-02417242v1
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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 of Nuclear Materials, 2019, 518, pp.386-399. ⟨10.1016/j.jnucmat.2019.03.023⟩
Journal articles hal-02149361v1
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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.
Acta Materialia, 2020, 199, pp.453-468. ⟨10.1016/j.actamat.2020.08.061⟩
Journal articles hal-02956376v1
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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 of Nuclear Materials, 2020, 533, pp.152106-1 - 152106-16. ⟨10.1016/j.jnucmat.2020.152106⟩
Journal articles hal-02639341v1
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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
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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

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
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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.
Surface and Coatings Technology, 2018, 349, pp.1048-1057. ⟨10.1016/j.surfcoat.2018.05.088⟩
Journal articles hal-02051246v1

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 of Nuclear Materials, 2017, 488, pp.267-286. ⟨10.1016/j.jnucmat.2017.03.009⟩
Journal articles cea-01488896v1
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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
Conference papers cea-02394049v1
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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
Conference papers hal-02493873v1

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 of Nuclear Materials, 2008, 378, pp.60-69. ⟨10.1016/j.jnucmat.2008.04.017⟩
Journal articles hal-00311854v1
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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.
Materials Characterization, 2019, 158, ⟨10.1016/j.matchar.2019.109971⟩
Journal articles hal-02431028v1
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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
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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
Conference papers hal-02417726v1

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.
Corrosion Science, 2023, 221, pp.111328. ⟨10.1016/j.corsci.2023.111328⟩
Journal articles hal-04161374v1
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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 of Nuclear Materials, 2021, 550, pp.152953. ⟨10.1016/j.jnucmat.2021.152953⟩
Journal articles hal-03212406v1