Uranium carbide properties for advanced fuel modeling – A review-Reference-Cited by-同舟云学术

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Uranium carbide properties for advanced fuel modeling – A review

Published:2022-01 Issue: Volume:558 Page:153145
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Vasudevamurthy Gokul,Nelson Andrew T.

Funder

U.S. Department of Energy

Publisher

Elsevier BV

Subject

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

Reference86 articles.

1. Finseth, "Rover Nuclear Rocket Engine Program", CR-184270, NASA, 1991.

2. Uranium Carbide Fuel For Organic Cooled Reactors;Jones,1973

3. Development Status of metallic, Dispersion and Non-Oxide Advanced and Alternative Fuels For Power and Research Reactors,2003

4. Fission Product Release and Transport in Liquid Metal Fast Breeder Reactors;Keilholtz,1969

5. Production of High Density Uranium Carbide compacts for use in Composite Nuclear Fuels;Vasudevamurthy;Nucl. Technol.,2008

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1. Thermophysical characterization of UFe3B2 and USiNi: An experimental study;Journal of Nuclear Materials;2024-07

2. First Structured Uranium‐Based Monoliths Produced via Vat Photopolymerization for Nuclear Applications;Advanced Functional Materials;2024-06-20

3. The Use of High-Density UN Fuel in Heat-Pipe Microreactors;Nuclear Technology;2024-06-14

4. Formation of uranium oxy-carbide and uranium carbide via conversion of polymer covered uranium dioxide by laser-based thermal processing;Journal of Nuclear Materials;2024-04

5. Distinguishing the Geometric and Electronic Structures of Actinide Carbides An_xC₈ (An = Th, U; x = 2, 3) through Exchange Interactions;The Journal of Physical Chemistry A;2024-01-24

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