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

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

Published:2014-09-19 Issue: Volume: Page:438-478
ISSN:
Container-title:Zirconium in the Nuclear Industry: 17th Volume
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Author:

Tupin Marc¹,Hamann Joel²,Cuisinier Damien²,Bossis Philippe²,Blat Martine³,Ambard Antoine³,Miquet Alain⁴,Kaczorowski Damien⁵,Jomard François⁶

Affiliation:

1. DEN, Section for Research on Irradiated Material, CEA/Saclay, 91191 Gif-sur-Yvette Cedex, FR, e-mail: marc.tupin@cea.fr

2. DEN, Section for Research on Irradiated Material, CEA/Saclay, 91191 Gif-sur-Yvette Cedex, FR.

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

4. EDF, EDF/SEPTEN, 69628 Villeurbanne Cedex, FR.

5. AREVA, AREVA NP, SAS, Fuel Business Unit, 10 rue Juliette Récamier, 69456 Lyon Cedex 06, FR.

6. CNRS UMR 8635, Groupe d’Etude de la Matière Condensée, 92195 Meudon Cedex, FR.

Publisher

ASTM International

Cited by 3 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Corrosion and high-temperature steam oxidation of E110 alloy and its laser welds after ion irradiation;Corrosion Science;2019-05

2. Release and speciation of carbon from Zircaloy-4 in anaerobic and highly alkaline conditions: Comparison of simple immersion and potentiostatic corrosion tests;Radiocarbon;2018-10-03

3. Microstructure Evolution in Ion-Irradiated Oxidized Zircaloy-4 Studied with Synchrotron Radiation Microdiffraction and Transmission Electron Microscopy;Zirconium in the Nuclear Industry: 18th International Symposium;2018-01-01

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