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Influence of temperature and hydrogen content on stress-induced radial hydride precipitation in Zircaloy-4 cladding

 J. Desquines , D. Drouan , M. Billone , M.P. Puls , P. March , et al.
Journal of Nuclear Materials, 2014, 453 (1-3), pp.131-150. ⟨10.1016/j.jnucmat.2014.06.049⟩
Article dans une revue hal-02641725v1
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Pressure drop and average void fraction measurements for two-phase flow through highly permeable porous media

 N. Chikhi , R. Clavier , J.-P. Laurent , F. Fichot , Michel Quintard
Annals of Nuclear Energy, 2016, 94, pp.422 - 432. ⟨10.1016/j.anucene.2016.04.007⟩
Article dans une revue hal-02558462v1
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Modeling diffusive phase transformation and fracture in viscoplastic materials

 Ethel Djeumen , Gergely Molnár , Nicolas Tardif , Michel Coret , Jean Desquines , et al.
International Journal of Solids and Structures, 2022, 252, pp.111757. ⟨10.1016/j.ijsolstr.2022.111757⟩
Article dans une revue hal-03709190v2
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Hafnium Oxidation at High Temperature in Steam

 Severine Guilbert , Alice Viretto , Marc Barrachin , Céline Tanguy , Martin Steinbrueck , et al.
Journal of Nuclear Materials, 2021, 550, pp.1-14. ⟨10.1016/j.jnucmat.2021.152901⟩
Article dans une revue hal-03208869v1
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Etude des mécanismes de dégradation sous air à haute température des gaines de combustible nucléaire en alliage de zirconium

 Isabel Idarraga Trujillo Idarraga Trujillo
Autre. Université de Grenoble, 2011. Français. ⟨NNT : 2011GRENI066⟩
Thèse tel-00680800v1
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Coolability of a corium pool in a debris bed – Critical heat flux (CHF) dependency with tilting angle, debris size and steam flowrate

 C. Sartoris , Thierry Garcin , Florian Fichot
Nuclear Engineering and Design, 2023, 403, pp.112146. ⟨10.1016/j.nucengdes.2022.112146⟩
Article dans une revue irsn-04112431v1

Development of a manufacturing process for a simulating fuel for the study of fine fragmentation in LOCA

 Mehdi Belqat , Fabrice Rossignol , Tatiana Taurines , Jean Desquines
2022 Nuclear Materials Conference (NuMAT 2022), NuMat organizing committee and IAEA, Oct 2022, Ghent, Belgium
Communication dans un congrès irsn-04023786v1
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THE R&D PERFROI PROJECT ON THERMAL MECHANICAL AND THERMAL HYDRAULICS BEHAVIORS OF A FUEL ROD ASSEMBLY DURING A LOSS OF COOLANT ACCIDENT

 Georges Repetto , Cristina Dominguez , Benoît Durville , Stéphane Carnemolla , Damien Campello , et al.
16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2016, American Nuclear Society, Aug 2015, Chicago (Il), United States
Communication dans un congrès irsn-04474840v1
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Effect of pre-oxide and hydrogen on creep of Zircaloy-4 at 1123 K

 C. Dominguez
Journal of Nuclear Materials, 2018, 511, pp.446-458. ⟨10.1016/j.jnucmat.2018.09.047⟩
Article dans une revue hal-02881782v1

The use of micro-Raman imaging to measure 18O tracer distribution in thermally grown zirconia scales

 M. Guerain , M. Mermoux , C. Duriez
Corrosion Science, 2015, 98, pp.140-149. ⟨10.1016/j.corsci.2015.05.020⟩
Article dans une revue hal-02572545v1
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A thermogravimetric comparative study of the high temperature steam oxidation of bare and pre-oxidized Zircaloy-4, M5Framatome and Optimized ZIRLO™

 Christian Duriez , H Richez , C Eymery , Severine Guilbert
2024
Pré-publication, Document de travail irsn-04500986v1
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Coolability of a Corium Pool in a Debris Bed -Impact of Debris Size, Steam and Liquid Flowrate, Tilting Angle and Pressure on Critical Heat Flux (CHF)

 C. Sartoris , T. Garcin , F. Fichot
NURETH-20, Aug 2023, Washington DC, United States
Communication dans un congrès irsn-04112787v1
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Revisiting weight-gain correlations for as-fabricated Zircaloy-4 cladding tubes during steam oxidation

 Jean Desquines , Tatiana Taurines , Séverine Guilbert , Christian Duriez , Antoine Ambard
Journal of Nuclear Materials, 2022, 569, pp.153908. ⟨10.1016/j.jnucmat.2022.153908⟩
Article dans une revue irsn-03992948v1
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Identification of the steady-state creep behavior of Zircaloy-4 claddings under simulated Loss-Of-Coolant Accident conditions based on a coupled experimental/numerical approach

 Damien Campello , Nicolas Tardif , Marwa Moula , Marie-Christine Baietto , Michel Coret , et al.
International Journal of Solids and Structures, 2017, 115-116, pp.190-199. ⟨10.1016/j.ijsolstr.2017.03.016⟩
Article dans une revue hal-01544673v2
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Effect of pre-oxide on Zircaloy-4 high temperature steam oxidation

 Severine Guilbert , Alice Viretto , Jean Desquines , Christian Duriez
Journal of Nuclear Materials, 2021, 548, pp.1-15. ⟨10.1016/j.jnucmat.2021.152854⟩
Article dans une revue hal-03194902v1
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Core coolability in loss of coolant accident: the PERFROI project

 Georges Repetto , Philippe March , Christophe Marquié , Nicolas Waekel , Marie-Christine Baietto , et al.
Top Fuel 14, American Nuclear Society, Sep 2014, Sendai (Japan), Japan
Communication dans un congrès irsn-04474876v1
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Étude expérimentale et modélisation du comportement d’un tube de gainage lors d’un accident de réactivité en phase post-crise ébullition

 Thomas Jailin
Mécanique [physics.med-ph]. Université de Lyon, 2020. Français. ⟨NNT : 2020LYSEI032⟩
Thèse tel-03125761v1
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Measuring both thermal and kinematic full-fields using a single CMOS camera during high temperature tests

 T. Jailin , Nicolas Tardif , P. Chaudet , J. Desquines , Michel Coret , et al.
Optics and Lasers in Engineering, 2022, 158, pp.107107. ⟨10.1016/j.optlaseng.2022.107107⟩
Article dans une revue hal-03709173v2
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Identification de lois de fluage par FEMU sur une ROI sans bord libre

 T Jailin , Nicolas Tardif , J Desquines , Michel Coret , Marie-Christine Baietto , et al.
14ème Colloque National en Calcul des Structures CSMA 2019, May 2019, Presqu'île de Giens, France
Communication dans un congrès hal-02443409v1
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A new research program on accidents in spent fuel pools: the DENOPI project

 Hervé Mutelle , Isabelle Tamburini , Christian Duriez , Sylvie Tillard , Nicolas Trégourès , et al.
WRFPM 2014, Sep 2014, Sendai, Japan. Paper No. 100071
Communication dans un congrès hal-01098163v1

HT cladding oxidation in SFP-LOCA conditions examined with microRaman imaging and 18O tracer techniques

 Michel Mermoux , Isabel Idarraga , Mathieu Guerain , Anne Kasperski , Mathilde Gestin , et al.
25th International QUENCH Workshop, QUENCH, Oct 2019, KARLSRUHE, Germany
Communication dans un congrès hal-02982045v1

Etude des phénomènes de corrosion sous air des gaines en zircaloy-4 des centrales nucléaires en situations accidentelles

 Marina Lasserre , Michèle Pijolat , Olivia Coindreau , Véronique Peres , Christian Duriez , et al.
44° Journées d'Etude sur la Cinétique Hétérogène (JECH 44), Apr 2013, Saclay, France
Communication dans un congrès hal-00811944v1
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High temperature oxidation and room temperature axial strength of pre-oxidized zircaloy-4 cladding after a simulated LOCA

 Jean Desquines , Christian Duriez , Severine Guilbert , Tatiana Taurines
Journal of Nuclear Materials, 2020, 543, pp.152559. ⟨10.1016/j.jnucmat.2020.152559⟩
Article dans une revue hal-03371773v1
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Characterization of austenitic Stainless steels with regard to environmentally assisted fatigue in simulated light water reactor conditions

 Matthias Bruchhausen , Gintautas Dundulis , Alec Mclennan , Sergio Arrieta , Tim Austin , et al.
Metals, 2021, 11 (307), pp.20. ⟨10.3390/met11020307⟩
Article dans une revue hal-03191106v1
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Viktoria experiments investigating the filtering system in the sump of a pwr after a loss of coolant accident : Part I Physical /chemical effects on strainer head loss evolution

 Georges Repetto , Benoit Migot , Jean-François Trigeol , Vojtech Soltesz
NURETH 2019 - 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Aug 2019, PORTLAND, United States. pp.407-420
Communication dans un congrès irsn-04111911v1
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Étude du comportement au fluage des gaines en alliage de zirconium pré-oxydées sous sollicitations thermomécaniques représentatives d’un accident de perte de réfrigérant primaire

 Ethel-Borel Djeumen Nkwechen
Mécanique [physics.med-ph]. Université de Lyon, 2022. Français. ⟨NNT : 2022LYSEI036⟩
Thèse tel-03860745v1

High temperature oxidation of zirconium alloys cladding material in sfp-loca conditions examined with micro raman imaging and 18o tracer techniques

 Anne Kasperski , Christian Duriez , Michel Mermoux
High Temperature Corrosion and Protection Materials, HTCPM, Mar 2021, ON LINE, France
Communication dans un congrès hal-03211624v1
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FEMU based identification of the creep behavior of Zircaloy-4 claddings under simulated RIA thermo-mechanical conditions

 T. Jailin , Nicolas Tardif , J. Desquines , Philippe Chaudet , Michel Coret , et al.
Journal of Nuclear Materials, 2022, 561, pp.153542. ⟨10.1016/j.jnucmat.2022.153542⟩
Article dans une revue hal-03555525v2
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Thermo-mechanical behavior of Zircaloy-4 claddings under simulated post-DNB conditions

 T. Jailin , Nicolas Tardif , J. Desquines , P. Chaudet , Michel Coret , et al.
Journal of Nuclear Materials, 2020, pp.151984. ⟨10.1016/j.jnucmat.2020.151984⟩
Article dans une revue hal-02437246v3
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Raman spectra analysis of ZrO 2 thermally grown on Zircaloy substrates irradiated with heavy ion: Effects of oxygen isotopic substitution

 Clément Ciszak , Michel Mermoux , Gaëlle Gutierrez , Frédéric Leprêtre , Christian Duriez , et al.
Journal of Raman Spectroscopy, 2019, 50 (3), pp.425-435. ⟨10.1002/jrs.5513⟩
Article dans une revue hal-02105028v1
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