Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding-Reference-Cited by-同舟云学术

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Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding

Published:2019-06 Issue: Volume:519 Page:247-254
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Maier Benjamin^ORCID,Yeom Hwasung,Johnson Greg,Dabney Tyler,Walters Jorie,Xu Peng,Romero Javier,Shah Hemant,Sridharan Kumar

Funder

U.S. Department of Energy

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference32 articles.

1. In-reactor corrosion performance of ZIRLOTM and zircaloy-4;Sabol,1994

2. Material selection for accident tolerant fuel cladding;Pint;Metall. Mater. Trans. E.,2015

3. Accident tolerant fuels for LWRs: a perspective;Zinkle;J. Nucl. Mater.,2014

4. Development of Light Water Reactor Fuels with Enhanced Accident Tolerance;Lyons,2015

5. Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding;Maier;J. Nucl. Mater.,2015

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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. Mitigating ZrCr2 formation at the Cr/Zr interface through trace doping of Zn, Mg and Sn into Cr coatings: A combined first-principles computational and experimental investigation;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. Microstructure evolution and interdiffusion behaviour of Cr/Mo coated Zr-4 alloys at 1330 °C-1500 °C;Materials Today Communications;2024-12

5. 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

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