Séverine Guilbert
Compétences
Publications
Publications
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Metallograph interpretation for post-LOCA bending fracture modelingTopFuel 2025 – International LWR Fuel Performance Conference, American Nuclear Society (ANS), Oct 2025, Nashville (Tennessee), United States |
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Parametric study of phenomena influencing secondary hydriding during loca transientsThe 2023 Water Reactor Fuel Performance Meeting, Jul 2023, Xi'an, China. pp.68-79, ⟨10.1007/978-981-99-7157-2_7⟩ |
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Fatigue Behavior in Air of 316L Stainless Steel Obtained by Additive Manufacturing in the Frame of the NUCOBAM European ProjectASME 2024 Pressure Vessels & Piping Conference, ASME, Jul 2024, Bellevue, France. pp.V004T06A031, ⟨10.1115/PVP2024-123296⟩ |
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Experimental study of secondary hydriding during a LOCA transientTOPFUEL 2024 - WATER REACTOR FUEL PERFORMANCE, European Nuclear Society, Sep 2024, Grenoble, France |
Experimental contribution to the determination of the In-Zr system for severe nuclear accident assessment19e conférence "Thermodynamics of Alloys", Dr Olivier Dezellus, Président du comité d’organisation de TOFA 2024, Sep 2024, Lyon (Université Lumière Lyon 2), France |
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Hafnium Oxidation in steam at high Temperature25th International QUENCH Workshop, QUENCH, Oct 2019, KARLSRUHE, Germany |
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Fuel Cladding post-quench LOCA Embrittlement: Mechanical test RelevanceThe 2016 Light Water Reactor Fuel Performance Meeting, American Nuclear Society, Sep 2016, Boise Idaho, United States |
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Hydrogen motion in Zircaloy-4 cladding during a LOCA transient3rd International Conference on Competitive Materials and Technology Processes (IC-CMTP3), University of Miskolc (Hongrie), Oct 2016, Miskolc-Lillafüred, Hungary. pp.012020, ⟨10.1088/1757-899X/123/1/012020⟩ |
Effect of Pre-Oxide on Zircaloy-4 High-Temperature Steam Oxidation and Post-Quench Mechanical PropertiesZirconium in the Nuclear Industry: 17th International Symposium, ASTM, Feb 2013, Hyderabad, India. pp.952-978, ⟨10.1520/STP154320120166⟩ |
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Oxygen diffusion and partially blocked bundle reflooding simulation using DRACCARLWR Fuel Performance Meeting, Top Fuel 2013, American Nuclear Society - ANS, Sep 2013, Charlotte, United States. pp.535-542 |
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Characterization of Oxygen Distribution in LOCA SituationsZirconium in the Nuclear Industry: 16th International Symposium, ASTM, May 2010, Chengdu, China. 28 p., ⟨10.1520/STP152920120039⟩ |
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Formation of organic iodide in the containment in case of a severe accident2008 Annual Meeting on American Nuclear Society, Jun 2008, Anaheim (CA), United States. pp.261-292 |
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Radiolytic oxidation of iodine in the containment at high temperature and dose rateNuclear energy for New Europe, NENE, Sep 2007, Portorož, Slovenia |
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Steam Oxidation of M5 Framatome * in the 900-1200°C Temperature Range21th International Symposium on Zirconium in the Nuclear Industry, Apr 2025, Aix en Provence, France |
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Applications de l’imagerie SIMS au sein de la plateforme PATERSON de l’IRSNSEMINAIRE 60 ans de la CETAMA, CETAMA, Oct 2021, NIMES, France. 2021 |
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Comportement de l'interface UO2/eau argileuse : Approche spectroscopiqueChimie. Université Paris XI - Orsay, 2000. Français. ⟨NNT : ⟩ |