Uranium nitride advanced fuel: an evaluation of the oxidation resistance of coated and doped grains-Reference-Cited by-同舟云学术

Uranium nitride advanced fuel: an evaluation of the oxidation resistance of coated and doped grains

Published:2021-12 Issue: Volume:556 Page:153249
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Mishchenko Yulia,Johnson Kyle D.,Jädernäs Daniel,Wallenius Janne,Lopes Denise Adorno

Publisher

Elsevier BV

Subject

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

Reference53 articles.

1. Impact of accident-tolerant fuels and claddings on the overall fuel cycle: a preliminary systems analysis;Youinou;Nucl. Technol.,2014

2. Lightbridge Corporation's advanced metallic fuel for light water reactors;Malone;Nucl. Technol.,2012

3. Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding;Dabney;Nucl. Mater. Energy,2019

4. Fuel residence time in BWRs with nitride fuels;Zakova;Ann. Nucl. Energy Oxf.,2012

5. Synthesis and sintering of UN-UO2 fuel composites;Jaques;J. Nucl. Mater.,2015

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