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authFullName_s : Valérie Vandenberghe

Microstructure and Properties of a Three-Layer Nuclear Fuel Cladding Prototype Containing Erbium as a Neutronic Burnable Poison

Jean-Christophe Brachet , Patrick Olier , Valérie Vandenberghe , Sylvie Doriot , Stéphane Urvoy , et al.
17th International Symposium on Zirconium in the Nuclear Industry, Feb 2013, Hyderabad, India. pp.184-224, ⟨10.1520/STP154320130053⟩
Conference papers cea-01253623v1
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Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors

Jean-Christophe Brachet , Isabel Idarraga-Trujillo , Marion Le Flem , Matthieu Le Saux , Valérie Vandenberghe , et al.
Journal of Nuclear Materials, 2019, 517, pp.268-285. ⟨10.1016/j.jnucmat.2019.02.018⟩
Journal articles hal-02090215v1
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Mechanical behavior at high temperatures of highly oxygen- or hydrogen-enriched α and (Prior-) β phases of zirconium alloys

Isabelle Turque , Raphaël Chosson , Matthieu Le Saux , Jean-Christophe Brachet , Valérie Vandenberghe , et al.
18th International symposium on zirconium in the nuclear industry, May 2016, Hilton Head Island, SC, United States. pp.240-280, ⟨10.1520/STP159720160063⟩
Conference papers hal-01702107v1
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Breakaway oxidation of zirconium alloys exposed to steam around 1000 °C

Matthieu Le Saux , Jean-Christophe Brachet , Valérie Vandenberghe , Antoine Ambard , Raphaël Chosson
Corrosion Science, 2020, 176 (108936), pp.1-21. ⟨10.1016/j.corsci.2020.108936⟩
Journal articles hal-02924036v1