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

Understanding xenon and vacancy behavior in UO2, UN and U3Si2: a comparative DFT+Ustudy

“…1,2 Different from UO 2 , UN and U 3 Si 2 can lower the centreline temperature during operation and increase the melting margin. 3 In particular, UN exhibits low fission gas release and good irradiation stability, [4][5][6][7] and U 3 Si 2 may have favourable swelling characteristics 8,9 due to its long potential fuel cycle benefit. However, rapid oxidation of UN and U 3 Si 2 occurs when they are exposed to a steam/water environment, leading to fuel dispersal along with cladding integrity loss.…”

Distinguishing the Geometric and Electronic Structures of Actinide Carbides AnxC8 (An = Th, U; x = 2, 3) through Exchange Interactions

“…Due to the potential fuel application of actinide carbides (U and Th) in high-temperature gas-cooled reactors and breeder fast reactors, − the chemical behavior and electronic properties of uranium carbide and thorium carbide are particularly important for their safe use . In particular, it is necessary to fully understand the composition and the corresponding structures of these systems. − Under the high temperatures that may be encountered in such accidents, the contribution of secondary polyatomic species to steam composition may become quite significant.…”