Oxide Layers in Ni-doped FeCrAl Alloy in 320°C Radioactive Hydrogenated Water-Reference-Cited by-同舟云学术

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Oxide Layers in Ni-doped FeCrAl Alloy in 320°C Radioactive Hydrogenated Water

Published:2024-05 Issue: Volume:593 Page:154987
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Joyce Logan^ORCID,Wang Peng^ORCID,Umretiya Rajnikant V.^ORCID,Hoffman Andrew,Xie Yi^ORCID

Funder

Office of Nuclear Energy

U.S. Department of Energy

U.S. Nuclear Regulatory Commission

National Research Council

Publisher

Elsevier BV

Reference27 articles.

1. Metrics for the technical performance evaluation of light water reactor accident-tolerant fuel;Bragg-Sitton;Nucl. Technol.,2017

2. Improving nuclear power plant safety with FeCrAl alloy fuel cladding;Rebak;MRS Adv.,2017

3. Uniform corrosion of FeCrAl alloys in LWR coolant environments;Terrani;J. Nucl. Mater.,2016

4. Effect of radiation damage and water radiolysis on corrosion of FeCrAl alloys in hydrogenated water;Wang;J. Nucl. Mater.,2020

5. Versatile oxide films protect FeCrAl alloys under normal operation and accident conditions in light water power reactors;Rebak;JOM,2018

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