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Void growth and coalescence in triaxial stress fields in irradiated FCC single crystals

Chao Ling , Benoît Tanguy , Jacques Besson , Samuel Forest , Félix Latourte
Journal of Nuclear Materials, 2017, 492, pp.157-170. ⟨10.1016/j.jnucmat.2017.04.013⟩
Journal articles hal-01540836v1
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Formation and characterization of hydride blisters in Zircaloy 4 cladding tubes

Arthur Hellouin de Menibus , Quentin Auzoux , Ousmane Dieye , Pascal Berger , Sophie Bosonnet , et al.
Journal of Nuclear Materials, 2014, 449, pp.132-147. ⟨10.1016/j.jnucmat.2014.03.006⟩
Journal articles hal-00980723v1
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Influence of grain size on the high-temperature creep behaviour of M5Framatome1 zirconium alloy under vacuum

G. Trego , J.C. Brachet , V. Vandenberghe , L. Portier , L. Gélébart , et al.
Journal of Nuclear Materials, 2022, 560, pp.153503. ⟨10.1016/j.jnucmat.2021.153503⟩
Journal articles hal-03517768v1

SIMS and TEM investigation of hydrogen trapping on implantation defects in a nickel-based superalloy

Fanny Jambon , Loïc Marchetti , Mohamed Sennour , François Jomard , Jacques Chêne
Journal of Nuclear Materials, 2015, 466, pp.120-133. ⟨10.1016/j.jnucmat.2015.07.045⟩
Journal articles hal-04161128v1
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Contribution to the understanding of brittle fracture conditions of zirconium alloy fuel cladding tubes during LOCA transient

Ronan Thieurmel , Jacques Besson , Édouard Pouillier , Aurore Parrot , Antoine Ambard , et al.
Journal of Nuclear Materials, 2019, 527, pp.151815. ⟨10.1016/j.jnucmat.2019.151815⟩
Journal articles hal-02455379v1

Effect of the thermal ageing on the tensile and impact properties of a 18%Cr ODS ferritic steel

A.L. Rouffié , J. Crépin , Mohamed Sennour , B. Tanguy , A. Pineau , et al.
Journal of Nuclear Materials, 2014, 445 (1-3), pp.37-42. ⟨10.1016/j.jnucmat.2013.10.030⟩
Journal articles hal-04161207v1

Characterization of a boron alloyed 9Cr3W3CoVNbBN steel and further improvement of its high-temperature mechanical properties by thermomechanical treatments

Stéphanie Hollner , Emma Piozin , P. Mayr , Christel Caës , Ivan Tournié , et al.
Journal of Nuclear Materials, 2013, 441, pp.15-23. ⟨10.1016/j.jnucmat.2013.05.018⟩
Journal articles hal-00841438v1

Microstructural evolutions and cyclic softening of 9%Cr martensitic steels

Benjamin Fournier , Maxime Sauzay , Alexandra Renault-Laborne , Françoise Barcelo , André Pineau
Journal of Nuclear Materials, 2009, 386-388, pp.71-74. ⟨10.1016/j.jnucmat.2008.12.061⟩
Journal articles istex hal-00379172v1

High-temperature mechanical properties improvement on modified 9Cr–1Mo martensitic steel through thermomechanical treatments

Stéphanie Hollner , Benjamin Fournier , J. Le Pendu , T. Cozzika , I. Tournié , et al.
Journal of Nuclear Materials, 2010, 405, pp.101-108. ⟨10.1016/j.jnucmat.2010.07.034⟩
Journal articles istex hal-00523277v1

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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The effect of strain biaxiality on the fracture of zirconium alloy fuel cladding

Ahmed Zouari , Matthew Bono , David Leboulch , Thomas Le Jolu , Jérôme Crepin , et al.
Journal of Nuclear Materials, 2021, pp.153070. ⟨10.1016/j.jnucmat.2021.153070⟩
Journal articles cea-03330340v1
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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

Advanced TEM characterization of stress corrosion cracking of Alloy 600 in pressurized water reactor primary water environment

Mohamed Sennour , P. Laghoutaris , C. Guerre , R. Molins
Journal of Nuclear Materials, 2009, 393 (2), pp.254-266. ⟨10.1016/j.jnucmat.2009.06.014⟩
Journal articles istex hal-04161298v1

Advanced TEM characterization of stress corrosion cracking of Alloy 600 in pressurized water reactor primary water environment

Mohamed Sennour , Pierre Laghoutaris , Catherine Guerre , Régine Molins
Journal of Nuclear Materials, 2009, 393, pp.254-266. ⟨10.1016/j.jnucmat.2009.06.014⟩
Journal articles istex hal-00423736v1

High temperature creep–fatigue–oxidation interactions in 9–12%Cr martensitic steels

Benjamin Fournier , Maxime Sauzay , Christel Caës , Michel Noblecourt , Véronique Rabeau , et al.
Journal of Nuclear Materials, 2009, 386-388, pp.418-421. ⟨10.1016/j.jnucmat.2008.12.139⟩
Journal articles istex hal-00379152v1

Microstructural influence on high temperature creep flow of Zr–1%NbO alloy in near-α, (α + β), and β temperature ranges in a high vacuum environment

Djillali Kaddour , Anne-Françoise Gourgues-Lorenzon , J.C. Brachet , Laurence Portier , André Pineau
Journal of Nuclear Materials, 2011, 408, pp.116-124. ⟨10.1016/j.jnucmat.2010.11.025⟩
Journal articles istex hal-00553181v1

Hydrogen trapping by irradiation-induced defects in 316 Lstainless steel: A combined experimental and modeling study

Anne-Cécile Bach , Frantz Martin , Cécilie Duhamel , Stéphane Perrin , François Jomard , et al.
Journal of Nuclear Materials, 2022, 562, pp.153603. ⟨10.1016/j.jnucmat.2022.153603⟩
Journal articles hal-03980437v1
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A detailed TEM and SEM study of Ni-base alloys oxide scales formed in primary conditions of pressurized water reactor

Mohamed Sennour , Loic Marchetti , Frantz Martin , Stéphane Perrin , Régine Molins , et al.
Journal of Nuclear Materials, 2010, 402 (2-3), pp.147-156. ⟨10.1016/j.jnucmat.2010.05.010⟩
Journal articles hal-00507516v1
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Effects of neutron irradiation and post-irradiation annealing on pop-in crack propagation instabilities in 6061 aluminium alloy

Tom Petit , Claire Ritter , Jacques Besson , Thilo F. Morgeneyer
Journal of Nuclear Materials, 2022, 569, pp.153909. ⟨10.1016/j.jnucmat.2022.153909⟩
Journal articles cea-03769978v1
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Hydrogen contribution to the thermal expansion of hydrided Zircaloy-4 cladding tubes

Arthur Hellouin de Menibus , Thomas Guilbert , Quentin Auzoux , Caroline Toffolon , Jean Christophe Brachet , et al.
Journal of Nuclear Materials, 2013, 440, pp.169-177. ⟨10.1016/j.jnucmat.2013.04.039⟩
Journal articles hal-00830844v1

TEM investigations on the effect of chromium content and of stress relief treatment on precipitation in Alloy 82

Mohamed Sennour , Elizabeth Chaumun , Jérôme Crépin , Cecilie Duhamel , Fabrice Gaslain , et al.
Journal of Nuclear Materials, 2013, 442, pp.262-289. ⟨10.1016/j.jnucmat.2013.09.002⟩
Journal articles hal-00874728v1

Effect of pre-strain on creep of three AISI 316 austenitic stainless steels in relation to reheat cracking of weld-affected zones

Quentin Auzoux , Lucien Allais , Christel Caës , I. Monnet , Anne-Françoise Gourgues , et al.
Journal of Nuclear Materials, 2010, 400, pp.127-137. ⟨10.1016/j.jnucmat.2010.02.021⟩
Journal articles istex hal-00488986v1
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Temperature increase of Zircaloy-4 cladding tubes due to plastic heat dissipation during tensile tests at 0.1-10 s−1 strain rates

Arthur Hellouin de Menibus , Quentin Auzoux , Jacques Besson , Jérôme Crépin
Journal of Nuclear Materials, 2014, 454 (1-3), pp.247-254
Journal articles hal-01059360v1

A detailed TEM and SEM study of Ni-base alloys oxide scales formed in primary conditions of pressurized water reactor

Mohamed Sennour , Loïc Marchetti , Frantz Martin , Stéphane Perrin , Régine Molins , et al.
Journal of Nuclear Materials, 2010, 402 (2-3), pp.147-156. ⟨10.1016/j.jnucmat.2010.05.010⟩
Journal articles hal-04161290v1

Influences of process parameters and microstructure on the fracture mechanisms of ODS steels

Anne Laure Rouffié , P. Wident , L. Ziolek , N. Delabrouille , Benoit Tanguy , et al.
Journal of Nuclear Materials, 2013, 433, pp.108-115. ⟨10.1016/j.jnucmat.2012.08.050,⟩
Journal articles hal-00751889v1

Effect of the thermal ageing on the tensile and impact properties of a 18%Cr ODS ferritic steel

Anne Laure Rouffié , Jérôme Crépin , Mohamed Sennour , Benoit Tanguy , André Pineau , et al.
Journal of Nuclear Materials, 2014, 445, pp.37-42. ⟨10.1016/j.jnucmat.2013.10.030⟩
Journal articles hal-00926575v1

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

SIMS and TEM investigation of hydrogen trapping on implantation defects in a nickel-based superalloy

Fanny Jambon , Loic Marchetti , Mohamed Sennour , François Jomard , Jacques Chene
Journal of Nuclear Materials, 2015, 466, pp.120-133. ⟨10.1016/j.jnucmat.2015.07.045⟩
Journal articles hal-01199632v1