Measuring Thermal Diffusivity and Gap Conductance in Uranium Nitride and Zircalloy Relevant for Microreactor Applications
Author:
Funder
Los Alamos National Laboratory
Laboratory Directed Research and Development
U.S. Department of Energy
National Nuclear Security Administration
Publisher
Elsevier BV
Reference48 articles.
1. A review of TRISO fuel performance models;Powers;Journal of Nuclear Materials,2010
2. Review of nuclear microreactors: Status, potentialities and challenges;Testoni;Progress in Nuclear Energy,2021
3. Implications of HALEU fuel on the design of SMRs and micro-reactors;Carlson;Nuclear Engineering and Design,2022
4. A review of uranium corrosion by hydrogen and the formation of uranium hydride;Banos;Corrosion Science,2018
5. Fabrication and Testing of Uranium Nitride Fuel for Space Power Reactors;Matthews;Journal of Nuclear Materials,1988
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