Understanding of Corrosion Mechanisms after Irradiation: Effect of Ion Irradiation of the Oxide Layers on the Corrosion Rate of M5-Reference-Cited by-同舟云学术

Understanding of Corrosion Mechanisms after Irradiation: Effect of Ion Irradiation of the Oxide Layers on the Corrosion Rate of M5

Published:2018-01-01 Issue: Volume: Page:415-447
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Container-title:Zirconium in the Nuclear Industry: 18th International Symposium
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Author:

Tupin Marc¹,Verlet Romain¹,Wolski Krzysztof²,Miro Sandrine³,Baldacchino Gérard⁴,Jublot Michael¹,Colas Kimberly¹,Bossis Philippe¹,Ambard Antoine⁵,Kaczorowski Damien⁶,Blat-Yrieix Martine⁵,Idarraga Isabel⁷

Affiliation:

1. CEA, Université Paris-Saclay, DEN-Service d'Etudes des Matériaux Irradiés, 91191, Gif-sur-Yvette Cedex, FR

2. Ecole des Mines de Saint Etienne, Centre SMS, 158, cours Fauriel, 42023 Saint Etienne Cedex, FR

3. CEA, Université Paris-Saclay, DEN-Service de Recherches de Metallurgie Physique, 91191 Gif-sur-Yvette Cedex, FR

4. CEA PARIS-SACLAY, LIDYL, UMR 9222 CEA-CNRS, 91191 Gif-sur-Yvette Cedex, FR

5. EDF, EDF R&D, Centre des Renardières, Ecuelles, 77818 Moret-sur-Loing Cedex, FR

6. AREVA NP, 10 rue Juliette Récamier, 69456 Lyon Cedex 06, FR

7. EDF, SEPTEN, 12-14 avenue Dutrievoz, 69628 Villeurbanne Cedex, FR

Publisher

ASTM International

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1. Peculiarities of interaction between oxygen and solute/vacancy in commercial-type zirconium-based alloys: A first-principles study;Materials Today Communications;2024-03

2. Ion irradiation of the metal matrix and its effects on the oxidation of the M5Framatome alloy;Corrosion Science;2023-08

3. Interactions of hydrogen with zirconium alloying elements and oxygen vacancies in monoclinic zirconia;Acta Materialia;2022-02

4. High-energy surface processing of zirconium alloys for fuel claddings of water-cooled nuclear reactors;Nuclear Engineering and Design;2021-10

5. Understanding the corrosion processes of fuel cladding in pressurized water reactors;Nuclear Corrosion;2020