2021
DOI: 10.1007/s11837-021-04844-2
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Thermophysical Properties of Mixtures of Thorium and Uranium Nitride

Abstract: The miscibility, lattice parameter, and thermophysical properties of (Th0.2U0.8)N and (Th0.5U0.5)N have been investigated. It is shown that additions of thorium nitride (ThN) to uranium nitride (UN) increases the thermophysical performance of the mixed nitride fuel form in comparison to reference UN. In the more dilute limit, additions of ThN serve as a burnable neutronic poison and reduces the change in keff over the lifecycle of the fuel. At higher concentrations, additions of ThN serve as a significant fert… Show more

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Cited by 7 publications
(15 citation statements)
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“…Uranium carbide is considered as a promising material for fuel of fast nuclear reactors due to its unique properties [2]. Actinide nitrides are of interest as the fuel of nuclear power plants, since nitrides have a higher thermal conductivity compared to actinide oxides, which reduces the thermal degradation of reactors [3]. For these nuclear materials, the problem of describing their thermal conductivity has not yet been solved.…”
Section: Introductionmentioning
confidence: 99%
“…Uranium carbide is considered as a promising material for fuel of fast nuclear reactors due to its unique properties [2]. Actinide nitrides are of interest as the fuel of nuclear power plants, since nitrides have a higher thermal conductivity compared to actinide oxides, which reduces the thermal degradation of reactors [3]. For these nuclear materials, the problem of describing their thermal conductivity has not yet been solved.…”
Section: Introductionmentioning
confidence: 99%
“…It is here where photothermal approaches offer a viable option for studying samples with small physical dimensions without damage to the sample or the need for destructive sample preparation approaches [95]. Several comprehensive reviews have been recently published on the thermophysical properties of actinide oxides [4], nitrides [96], and carbides [97,98] due to the importance of these compounds to nuclear science and industry.…”
Section: B Characterization Of Thin Filmsmentioning
confidence: 99%
“…Thermal conductivities have been measured for ThO 2 [141], UO 2 [142], NpO 2 [143], and PuO 2 [144]. The heat capacities of select actinide nitride systems have been measured, including ThN [145], and more recently for the UN-ThN mixtures used in nuclear fuels [96]. Among these properties, thermal diffusivity and conductivity have been recently studied as important factors in determining the properties of a nuclear fuel candidate material [4].…”
Section: Thermophysical Magnetic and Topological Properties Of Actini...mentioning
confidence: 99%
“…The commercialization of molten salt reactor (MSR) technology based on a thorium cycle is on the fast track in China, with a 2 MW experimental reactor currently being tested [ 10 ]. Thorium nitride is under development as a fuel component for compact nuclear reactors, including space reactors [ 11 , 12 ].…”
Section: Introductionmentioning
confidence: 99%