Recherche - IRSN - Institut de radioprotection et de sûreté nucléaire

46 résultats

	Pour les 46 documents Envoyer sur ORCID RSS ATOM Exporter BibTeX XML-TEI CSV RTF EndNote PDF HTML Export avancé	Page : Page précédente 1 2 Page suivante	triés par Pertinence Auteur A→Z Auteur Z→A Titre A→Z Titre Z→A Date de publication croissante Date de publication décroissante Date de dépôt croissante Date de dépôt décroissante

		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		Experimental study and modelling of the phase transformation of Zircaloy-4 alloy under high thermal transients T. Jailin , Nicolas Tardif , J. Desquines , Michel Coret , M.-C. Baietto , et al. Materials Characterization, 2020, 162, pp.110199. ⟨10.1016/j.matchar.2020.110199⟩ Article dans une revue hal-02489746v2	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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*	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		Coolability of a Corium Pool in a Debris Bed: Impact of Debris Size, Steam, and Liquid Flow Rate; Tilting Angle; and Pressure on Critical Heat Flux—First Numerical Evaluations C. Sartoris , Julie-Anne Zambaux , Florian Fichot Nuclear Science and Engineering, 2024, pp.1-16. ⟨10.1080/00295639.2024.2357943⟩ Article dans une revue irsn-04669226v1	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		An experimental study of the thermal-hydraulics of a spent nuclear fuel pool under loss-of-cooling accident conditions. Part II: a first interpretation of the MIDI tests Jimmy Martin , Benoît Migot Nuclear Engineering and Design, 2024, 426, pp.113406. ⟨10.1016/j.nucengdes.2024.113406⟩ Article dans une revue irsn-04665546v2	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		Influence of hydrogen on the oxygen solubility in Zircaloy-4 Séverine Guilbert-Banti , Pauline Lacote , Gaëlle Taraud , Pascal Berger , Jean Desquines , et al. Journal of Nuclear Materials, 2016, 469, pp.228-236. ⟨10.1016/j.jnucmat.2015.11.019⟩ Article dans une revue irsn-04594820v1	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		An experimental study of the thermal-hydraulics of a spent nuclear fuel pool under loss-of-cooling accident conditions. Part I: The MIDI facility and its main experimental results Benoît Migot , Jimmy Martin Nuclear Engineering and Design, 2024, 426, pp.113404. ⟨10.1016/j.nucengdes.2024.113404⟩ Article dans une revue irsn-04665545v2	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		Radial Hydride Precipitation in Fuel Cladding During Back-End Cooling Transient Under Decreasing Pressure J. Desquines , C. Sartoris , Marine Guemas , A. Gérard WRFPM 2023 - International Conference on Water Reactor Fuel Performance Meeting, Jul 2023, Xi'an, China. pp.80-86, ⟨10.1007/978-981-99-7157-2_8⟩ Communication dans un congrès irsn-04663609v1	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More
		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 , J. Desquines , Severine Guilbert Journal of Nuclear Materials, 2024, 597, pp.155147. ⟨10.1016/j.jnucmat.2024.155147⟩ Article dans une revue irsn-04645456v1	Envoyer sur ORCID Exporter BibTeX XML-TEI Dublin Core DC Terms EndNote DataCite Export avancé Partager More

Filtrer vos résultats

Parametric study of phenomena influencing secondary hydriding during loca transients

Fuel Cladding post-quench LOCA Embrittlement: Mechanical test Relevance

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

Pressure drop and average void fraction measurements for two-phase flow through highly permeable porous media

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

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

High temperature oxidation and room temperature axial strength of pre-oxidized zircaloy-4 cladding after a simulated LOCA

Experimental study and modelling of the phase transformation of Zircaloy-4 alloy under high thermal transients

Etude des mécanismes de dégradation sous air à haute température des gaines de combustible nucléaire en alliage de zirconium

Hydrogen motion in Zircaloy-4 cladding during a LOCA transient

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

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

Coolability of a Corium Pool in a Debris Bed: Impact of Debris Size, Steam, and Liquid Flow Rate; Tilting Angle; and Pressure on Critical Heat Flux—First Numerical Evaluations

Hafnium Oxidation at High Temperature in Steam

An experimental study of the thermal-hydraulics of a spent nuclear fuel pool under loss-of-cooling accident conditions. Part II: a first interpretation of the MIDI tests

Modeling diffusive phase transformation and fracture in viscoplastic materials

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

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

Revisiting weight-gain correlations for as-fabricated Zircaloy-4 cladding tubes during steam oxidation

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

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

Influence of hydrogen on the oxygen solubility in Zircaloy-4

Effect of pre-oxide on Zircaloy-4 high temperature steam oxidation

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)

Effect of pre-oxide and hydrogen on creep of Zircaloy-4 at 1123 K

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

Coolability of a corium pool in a debris bed – Critical heat flux (CHF) dependency with tilting angle, debris size and steam flowrate

An experimental study of the thermal-hydraulics of a spent nuclear fuel pool under loss-of-cooling accident conditions. Part I: The MIDI facility and its main experimental results

Radial Hydride Precipitation in Fuel Cladding During Back-End Cooling Transient Under Decreasing Pressure

A thermogravimetric comparative study of the high temperature steam oxidation of bare and pre-oxidized Zircaloy-4, M5Framatome and Optimized ZIRLO™

Effect of pre-oxide and hydrogen on creep of Zircaloy-4 at 1123 K