Mathematical model of the oxidation of a uranium carbide fuel pellet including an adherent product layer
Sign Up to like & getrecommendations! Published in 2017 at "Applied Mathematical Modelling"
DOI: 10.1016/j.apm.2017.01.041
Abstract: Abstract Uranium carbide is a candidate fuel for Generation IV nuclear reactors. However, like any candidate fuel, a reprocessing route should be established before implementation. One proposed method involves a pre-oxidation step, where the carbide… read more here.
Keywords: carbide; oxidation; carbide fuel; uranium carbide ... See more keywords
On the Stability of Uranium Carbide in Aqueous Solution—Effects of HCO3– and H2O2
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DOI: 10.1021/acsomega.1c04581
Abstract: Uranium carbide (UC) is a candidate fuel material for future Generation IV nuclear reactors. As part of a general safety assessment, it is important to understand how fuel materials behave in aqueous systems in the… read more here.
Keywords: uranium carbide; fuel; aqueous solution; hco3 h2o2 ... See more keywords
Uranium Carbide Fibers with Nano-Grains as Starting Materials for ISOL Targets
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DOI: 10.3390/nano10122458
Abstract: This paper presents an experimental study about the preparation, by electrospinning, of uranium carbide fibers with nanometric grain size. Viscous solutions of cellulose acetate and uranyl salts (acetate, acetylacetonate, and formate) on acetic acid and… read more here.
Keywords: nano grains; starting materials; uranium carbide; grains starting ... See more keywords