Effect of Chromium Content on the On-Cooling Phase Transformations and Induced Prior-β<sub>Zr</sub> Mechanical Hardening and Failure Mode (in Relation to Enhanced Accident-Tolerant Fuel Chromium-Coated Zirconium-Based Cladding Behavior upon and after High-Temperature Transients)-Reference-Cited by-同舟云学术

Effect of Chromium Content on the On-Cooling Phase Transformations and Induced Prior-β_Zr Mechanical Hardening and Failure Mode (in Relation to Enhanced Accident-Tolerant Fuel Chromium-Coated Zirconium-Based Cladding Behavior upon and after High-Temperature Transients)

Published:2023-11-01 Issue: Volume: Page:433-458
ISSN:
Container-title:Zirconium in the Nuclear Industry: 20th International Symposium
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Author:

Brachet Jean-Christophe¹^ORCID,Gokelaere Paul¹²,Guilbert Thomas¹,Toffolon-Masclet Caroline¹,Urvoy Stéphane¹³,Dumerval Marie¹,Nony Guillaume¹,Braun James¹,Palancher Hervé⁴,Buchanan Karl⁵,Pouillier Edouard⁶,Vu Tuan-Minh¹²,Joubert Jean-Marc²^ORCID

Affiliation:

1. Univ. Paris-Saclay, CEA, DES-ISAS/DMN, Service de Recherches Métallurgiques Appliquées, 91191 Gif-sur-Yvette, FR

2. Univ. Paris Est Créteil, CNRS, ICMPE, UMR 7182, 2 rue Henri Dunant, 94320 Thiais, FR

3. Univ. Paris-Saclay, CEA, DES-ISAS/DMN, Service d’Etudes des Matériaux Irradiés, 91191 Gif-sur-Yvette, FR

4. CEA, DES, IRESNE, F-13108 Saint-Paul-lez-Durance, FR

5. Framatome, 10 rue Juliette Récamier, 69456 Lyon, Cedex 06, FR

6. EDF R&D, MMC Dept., Avenue des Renardières, 77818 Moret-Sur-Loing, FR

Publisher

ASTM International

Reference45 articles.

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3. Application and Development Progress of Cr-Based Surface Coating in Nuclear Fuel Elements: II. Current Status and Shortcomings of Performance Studies;Chen;Coatings,2020

4. Early Studies on Cr-Coated Zircaloy-4 as Enhanced Accident Tolerant Nuclear Fuel Claddings for Light Water Reactors;Brachet;Journal of Nuclear Materials,2019

5. Protective Coatings on Zirconium-Based Alloys as Accident Tolerant Fuel (ATF) Claddings;Tang;Corrosion Reviews,2017