Hydrothermal corrosion of PVD and cold spray Cr-coatings on Zircaloy-4 in hydrogenated and oxygenated LWR coolant environments
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,Materials Science (miscellaneous),Nuclear and High Energy Physics
Reference20 articles.
1. C.L. Withmarsh, Review of Zircaloy-2 and Zircaloy-4 Properties Relevant to N.S. Savannah Reactor Design, (No. ORNL-3281). Oak Ridge Natl. Lab., Tenn.. 4500 (1962) 70. https://doi.org/Report No. ORNL-3281, UC-80-Reactor Technology, TID-4500 (17th ed.).
2. The Fukushima Daiichi accident report by the director general;Agency;Dir. Gen.,2015
3. Phenomenology of BWR fuel assembly degradation;Kurata;J. Nucl. Mater.,2018
4. Accident Tolerant Materials for Light Water Reactor Fuels;Rebak,2020
5. Protective coatings on zirconium-based alloys as accident-Tolerant fuel (ATF) claddings;Tang;Corros. Rev.,2017
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1. Unveiling the latest progresses in chromium-coated Zircaloy cladding ATF materials: Fabrication techniques, performance metrics, and beyond;Alexandria Engineering Journal;2024-12
2. Corrosion behavior of additively manufactured FeCrAl in out-of-pile light water reactor environments;npj Materials Degradation;2024-08-28
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