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 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
Journal articles
hal-02924036v1
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