In situ X-ray computed micro-tomography imaging of failure processes in Cr-coated Zircaloy nuclear fuel cladding materials
Author:
Funder
Engineering and Physical Sciences Research Council
University of Bristol
U.S. Department of Energy
Office of Science
Publisher
Elsevier BV
Subject
Mechanical Engineering,Mechanics of Materials,General Materials Science
Reference48 articles.
1. Accident tolerant fuel cladding development: Promise, status, and challenges;Terrani;Journal of Nuclear Materials,2018
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3. Mechanical and chemical properties of PVD and cold spray cr-coatings on Zircaloy-4;Umretiya;Journal of Nuclear Materials,2020
4. Cold sprayed cr-coating on optimized ZIRLOTM claddings: The Cr / Zr interface and its microstructural and chemical evolution after autoclave corrosion testing;Fazi;Journal of Nuclear Materials,2022
5. Effect of irradiation swelling on the mechanical properties of unidirectional SiC/SiC composites: A numerical investigation at microstructural level;Chen;Journal of Nuclear Materials,2022
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