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Matthieu Le Saux

Enseignant-Chercheur / Lecturer-Researcher
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Presentation

Current research activities: characterisation and modelling of the thermomechanical behaviour and fatigue of organic materials (short or long fibre-reinforced organic matrix composites, polymer foams, etc.)

Research domains

Materials Mechanics [physics.med-ph]

Publications

Combined techniques and relevant image processing for quantitative statistical characterization of inclusions in elastomers

Thomas Glanowski , Matthieu Le Saux , V. Le Saux , Bertrand Huneau , Clément Champy
Rubber Chemistry and Technology, 2023, 96 (1), pp.59-89. ⟨10.5254/rct.22.22970⟩
Journal articles hal-04365898v1
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Fatigue of short carbon fiber reinforced PEEK under compression: Influence of the load ratio and predictions from heat buildup measurements

Vanessa Kwiatkowski , Matthieu Le Saux , Vincent Le Saux , Sylvain Leclercq , Yann Marco
Fatigue and Fracture of Engineering Materials and Structures, 2023, 46 (7), pp.2396-2410. ⟨10.1111/ffe.14003⟩
Journal articles hal-04077635v1

Statistical characterization of microcellular polyurethane foams microstructure based on 2D and 3D image analysis

Matthieu Le Saux , Jean-Baptiste Le Bail , Justin Becker , Célia Caër , Pierre Charrier
Journal of Cellular Plastics, 2023, 59 (5-6), pp.395-417. ⟨10.1177/0021955X231215773⟩
Journal articles hal-04402661v1

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
Corrosion Science, 2023, 221, pp.111328
Journal articles cea-04442846v1

Mechanical behavior of a chromium coating on a zirconium alloy substrate at room temperature

Duc Vinh Nguyen , Matthieu Le Saux , Lionel Gélébart , Jean-Christophe Brachet , Jean-Philippe Bonthonneau
Journal of Nuclear Materials, 2022, 558, pp.153332. ⟨10.1016/j.jnucmat.2021.153332⟩
Journal articles hal-04446231v1
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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
Journal of Nuclear Materials, 2021, 550, pp.152953. ⟨10.1016/j.jnucmat.2021.152953⟩
Journal articles hal-03212406v1
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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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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
International Journal of Fatigue, 2020, 135, pp.105574. ⟨10.1016/j.ijfatigue.2020.105574⟩
Journal articles hal-03270375v1
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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
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
Journal of Nuclear Materials, 2020, 533, pp.152106-1 - 152106-16. ⟨10.1016/j.jnucmat.2020.152106⟩
Journal articles hal-02639341v1

A model to describe the cyclic anisotropic mechanical behavior of short fiber-reinforced thermoplastics

Libor Navrátil , Louis Leveuf , V. Le Saux , Yann Marco , Jérôme Olhagaray
Mechanics of Time-Dependent Materials, 2020, ⟨10.1007/s11043-020-09445-1⟩
Journal articles hal-02461494v1
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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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High temperature steam oxidation of chromium-coated zirconium-based alloys: Kinetics and process

J.-C. Brachet , E. Rouesne , J. Ribis , T. Guilbert , S. Urvoy
Corrosion Science, 2020, ⟨10.1016/j.corsci.2020.108537⟩
Journal articles hal-02520055v1
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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
Journal of Nuclear Materials, 2019, 518, pp.386-399. ⟨10.1016/j.jnucmat.2019.03.023⟩
Journal articles hal-02149361v1
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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
Materials Characterization, 2019, 158, ⟨10.1016/j.matchar.2019.109971⟩
Journal articles hal-02431028v1

Effect of a pre-oxide on the high temperature steam oxidation of Zircaloy-4 andM5 alloys

M. Lesaux , Jc. Brachet , V. Vandenberghe , S. Urvoy , E. Rouesne
Journal of Nuclear Materials, 2019, ⟨10.1016/j.jnucmat.2019.03.023⟩
Journal articles cea-02340028v1
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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
Journal of Nuclear Materials, 2019, 517, pp.268-285. ⟨10.1016/j.jnucmat.2019.02.018⟩
Journal articles hal-02090215v1
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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
Surface and Coatings Technology, 2018, 349, pp.1048-1057. ⟨10.1016/j.surfcoat.2018.05.088⟩
Journal articles hal-02051246v1

An approach to study oxidation-induced stresses in Zr alloys oxidized at high temperature

M. Lesaux , T. Guilbert , Jc. Brachet
Corrosion Science, 2018, 140, ⟨10.1016/j.corsci.2018.06.016⟩
Journal articles cea-02339748v1

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
Journal of Nuclear Materials, 2017, 488, pp.267-286. ⟨10.1016/j.jnucmat.2017.03.009⟩
Journal articles cea-01488896v1
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Experimental investigation and theoretical modelling of induced anisotropy during stress-softening of rubber

Gilles Marckmann , Grégory Chagnon , Matthieu Le Saux , Pierre Charrier
International Journal of Solids and Structures, 2016, 97-98, pp.554-565. ⟨10.1016/j.ijsolstr.2016.06.028⟩
Journal articles hal-01377314v1

Études du CEA sur les gainages avancés de combustible nucléaire pour un combustible REL avec une tolérance aux accidents améliorée, en APRP et au-delà

J.-C. Brachet , C. Lorrette , A. Michaux , C. Sauder , I. Idarraga-Trujillo
Revue Generale Nucleaire, 2016, 1, pp.14-20. ⟨10.1051/rgn/20151014⟩
Journal articles hal-04446413v1

In-situ X-ray diffraction analysis of zirconia layer formed on zirconium alloys oxidized at high temperature

D. Gosset , Matthieu Le Saux
Journal of Nuclear Materials, 2015, 458, pp.245-252. ⟨10.1016/j.jnucmat.2014.12.067⟩
Journal articles cea-03190082v1

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

New insights in structural characterization of zirconium alloys oxidation at high temperature

Dominique Gosset , Matthieu Le Saux , David Simeone , Didier Gilbon
Journal of Nuclear Materials, 2012, 429 (1-3), pp.19-24. ⟨10.1016/j.jnucmat.2012.05.003⟩
Journal articles hal-04446259v1

Behavior and failure of uniformly hydrided Zircaloy-4 fuel claddings between 25 °C and 480 °C under various stress states, including RIA loading conditions

Matthieu Le Saux , Jacques Besson , Sébastien Carassou , Christophe Poussard , Xavier Averty
Engineering Failure Analysis, 2010, 17, pp.683-700. ⟨10.1016/j.engfailanal.2009.07.001⟩
Journal articles hal-00461500v1

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

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
International Conference on Composite Materials (ICCM 2023), Jul 2023, Belfast, Ireland
Conference papers hal-04446797v1

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
LWR Fuel Performance Meeting / TopFuel 2013, Sep 2023, Charlotte, NC, United States. pp.860-867
Conference papers hal-04446951v1

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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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
Conference papers hal-02493904v1
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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
24e Congrès Français de Mécanique, Aug 2019, Brest, France
Conference papers hal-02493873v1
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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
Materials Science and Engineering - session Structural Materials and Metallurgy, Feb 2019, San Francisco, United States
Conference papers cea-02394049v1

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
Conference papers hal-02493915v1

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
La metallurgie, quel avenir, Apr 2019, Nancy, France
Conference papers hal-02411055v1

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
Colloque SF2M « La Métallurgie, Quel Avenir !, Apr 2019, Nancy, France
Conference papers hal-02442069v1

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
Materials Science and Engineering 2019, Feb 2019, San-Francisco, United States
Conference papers hal-02411074v1
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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
24e Congrès Français de Mécanique, Aug 2019, Brest, France
Conference papers hal-02493887v1
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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
Thermec 2018 - International Conference on PROCESSING & MANUFACTURING OF ADVANCED MATERIALS, Jul 2018, Paris, France
Conference papers cea-02338566v1
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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
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

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
Materiaux 2018, Nov 2018, Strasbourg, France
Conference papers cea-02400186v1
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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
Topfuel 2018, Sep 2018, Prague, Czech Republic
Conference papers cea-02328975v1
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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
WRFPM2017 Water Reactor Fuel Performance Meeting, Sep 2017, Jeju-do, South Korea
Conference papers hal-02417726v1
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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
WRFPM 2017 Water Reactor Fuel Performance Meeting, Sep 2017, Jeju, South Korea
Conference papers hal-02419638v1

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
12eme Colloque Rayons X et Matiere (RX - 2017), Nov 2017, Lille, France
Conference papers hal-02417370v1

Structural evolutions in zr alloys during oxidation at high temperature andsubsequent cooling

R. Guillou , M. Lesaux , J.-C. Brachet , T. Guilbert , E. Rouesne
ICNMNE International Conference on Nuclear Materials and Nuclear Engineering, Jan 2017, Londres, United Kingdom
Conference papers hal-02419674v1
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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
Conference papers cea-02417311v1
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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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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
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
18th International Symposium on Zirconium in the Nuclear Industry, May 2016, Hilton Head, United States
Conference papers hal-02441977v1

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
NuMat2016 The Nuclear Materials Conference, Nov 2016, Montpellier, France
Conference papers hal-02441982v1
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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
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
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
Topfuel 2016 - Light Water Reactor (LWR) Fuel Performance Meeting, Sep 2016, Boise, United States
Conference papers cea-02438712v1
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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
TopFuel 2015 - Reactor Fuel Performance Meeting, Sep 2015, Zurich, Switzerland
Conference papers cea-02492582v1
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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
Technical Meeting on Accident Tolerant Fuel Concepts for Light Water Reactors, IAEA, Oct 2014, Oak Ridge, United States
Conference papers cea-02875113v1

Loss of Coolant Accident Testing Round Robin

Ken Yueh , R.J. Comstock , B. Dunn , Matthieu Le Saux , Y.P. Lin
TopFuel 2013, Sep 2013, Charlotte, NC, United States. pp.550-556
Conference papers hal-04447101v1
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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
TopFuel 2012, Sep 2012, Manchester, United Kingdom
Conference papers hal-04447119v1

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
2011 Water Reactor Fuel Performance Meeting, Sep 2011, Chengdu, China
Conference papers hal-04447298v1

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
International Topical Meeting on Light Water Reactor Fuel Performance, Sep 2010, Orlando, United States. pp.261-269
Conference papers hal-04447331v1

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
International Topical Meeting on Light Water Reactor Fuel Performance, Sep 2010, Orlando, United States. pp.270-277
Conference papers hal-04447319v1

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
Conference papers hal-04447310v1

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
OECD/NEA Workshop on the Behaviour of Nuclear Reactor Fuel during Reactivity Initiated Accidents, Sep 2009, Paris, France
Conference papers hal-04447354v1
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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
Conference papers hal-00329805v1

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
Conference papers hal-04447381v1

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
Conference papers hal-04447388v1