Influence of coating parameters on oxidation behavior of Cr-coated zirconium alloy for accident tolerant fuel claddings-Reference-Cited by-同舟云学术

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Influence of coating parameters on oxidation behavior of Cr-coated zirconium alloy for accident tolerant fuel claddings

Published:2022-07 Issue: Volume:203 Page:110359
ISSN:0010-938X
Container-title:Corrosion Science
language:en
Short-container-title:Corrosion Science

Author:

Kashkarov E.B.,Sidelev D.V.,Pushilina N.S.,Yang J.,Tang C.,Steinbrueck M.

Funder

Russian Science Foundation

Publisher

Elsevier BV

Subject

General Materials Science,General Chemical Engineering,General Chemistry

Reference39 articles.

1. Corrosion of zirconium alloys used for nuclear fuel cladding;Motta;Annu. Rev. Mater. Sci.,2015

2. V. Shishov, The evolution of microstructure and deformation stability in Zr-Nb-(Sn, Fe) alloys under neutron irradiation, in: Zirconium in the Nuclear Industry, in book: Zirconium in the Nuclear Industry: 16th International Symposium, ASTM International, 2012, pp. 37–66.

3. Accident tolerant fuel cladding development: promise, status, and challenges;Terrani;J. Nucl. Mater.,2018

4. Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings;Tang;Corros. Rev.,2017

5. Predicting oxide stability in high-temperature water vapor;Opila;JOM,2006

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1. Insights into 1200 °C steam oxidation behavior of Cr coatings with different microstructure on Zircaloy-4 alloys for enhanced accident tolerant fuel cladding;Annals of Nuclear Energy;2025-01

2. Degradation behavior of chromium-coated zirconium cladding under 1200 oC steam oxidation according to the coating microstructure;Journal of Nuclear Materials;2025-01

3. Unveiling the latest progresses in chromium-coated Zircaloy cladding ATF materials: Fabrication techniques, performance metrics, and beyond;Alexandria Engineering Journal;2024-12

4. Microstructural characteristics of multilayers and interfaces of Cr-coated Zircaloy-4 cladding based on elemental diffusion under high-temperature steam oxidation;Journal of Nuclear Materials;2024-10

5. High-temperature oxidation behavior and degradation mechanism of chromium-coated zirconium alloy cladding: a review;Tungsten;2024-09-05

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