Recherche - IRSN - Institut de radioprotection et de sûreté nucléaire Accéder directement au contenu

Filtrer vos résultats

43 résultats
Image document

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
Image document

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
Image document

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

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
Image document

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
Image document

Parametric study of phenomena influencing secondary hydriding during loca transients

Apou Martial Kpemou , Jean Desquines , Tatiana Taurines , Severine Guilbert , M C Baietto , et al.
The 2023 Water Reactor Fuel Performance Meeting, Jul 2023, Xi'an, China. pp.68-79, ⟨10.1007/978-981-99-7157-2_7⟩
Communication dans un congrès irsn-04594502v1
Image document

Fuel Cladding post-quench LOCA Embrittlement: Mechanical test Relevance

Severine Guilbert , Jean Desquines
The 2016 Light Water Reactor Fuel Performance Meeting, American Nuclear Society, Sep 2016, Boise Idaho, United States
Communication dans un congrès irsn-04594674v1
Image document

An experimental approach for the analytical study of secondary hydriding of *m5 framatome cladded fuel rods during a loca

Apou Martial Kpemou , M C Baietto , Jean Desquines , Tatiana Taurines , A Ambard , et al.
NuMat2022: The Nuclear Materials Conference, Oct 2022, Ghent, Belgium
Poster de conférence irsn-04594542v1
Image document

Experimental study of an adiabatic two-phase flow in a simulated PWR spent fuel bundle

Guillaume Brillant , Jimmy Martin , Benjamin Fourré
18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics - NURETH, ANS - American Nuclear Society, Aug 2019, Portland, United States. pp.Pages 2577 - 2586
Communication dans un congrès irsn-04074255v1
Image document

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
Image document

Hydrogen motion in Zircaloy-4 cladding during a LOCA transient

Elodie Torrès , Jean Desquines , Séverine Guilbert , Marie-Christine Baietto , Michel Coret , et al.
3rd International Conference on Competitive Materials and Technology Processes (IC-CMTP3), Oct 2014, Miskolc-Lillafüred, Hungary. pp.012020, ⟨10.1088/1757-899X/123/1/012020⟩
Communication dans un congrès irsn-04594714v1
Image document

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
Image document

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
Image document

An attempt for a unified description of mechanical testing on Zircaloy-4 cladding subjected to simulated LOCA transient

Jean Desquines , Doris Drouan , Elodie Torres , Séverine Guilbert , Pauline Lacote
EPJ N - Nuclear Sciences & Technologies, 2016, 2 (13), pp.9. ⟨10.1051/epjn/2016009⟩
Article dans une revue irsn-04594690v1
Image document

Validation of a multimodal set-up for the study of zirconium alloys claddings' behaviour under simulated LOCA conditions

Damien Campello , Nicolas Tardif , Jean Desquines , Marie-Christine Baietto , Michel Coret , et al.
Strain, 2018, 54 (5), ⟨10.1111/str.12279⟩
Article dans une revue hal-01862731v2
Image document

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

Hafnium Oxidation in steam at high Temperature

Severine Guilbert , Alice Viretto , Marc Barrachin , Céline Tanguy , Martin Steinbrueck , et al.
25th International QUENCH Workshop, QUENCH, Oct 2019, KARLSRUHE, Germany
Communication dans un congrès hal-02635626v1
Image document

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
Image document

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
Image document

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
Image document

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
Image document

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

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

Characterization of Oxygen Distribution in LOCA Situations

Christian Duriez , Severine Guilbert , Anthony Stern , Claude Grandjean , Ladislav Bělovský , et al.
Zirconium in the Nuclear Industry: 16th International Symposium, ASTM, May 2010, Chengdu, China. pp.993-1020, ⟨10.1520/STP152920120039⟩
Communication dans un congrès irsn-04594892v1

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
Image document

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
Image document

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
Image document

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