TY - JOUR
T1 - New insights into the mechanical and thermal properties of UN1-xCx from first-principles calculations
AU - Di, Yaxin
AU - He, Zongbei
AU - Wang, Junjie
N1 - Publisher Copyright:
© 2022 Elsevier B.V.
PY - 2022/12/1
Y1 - 2022/12/1
N2 - Uranium nitride (UN) is considered to be a very promising candidate of accident-tolerant fuel. Since UN is commercially synthesized by carbothermic reduction-nitridation, the carbon in synthesized UN is unavoidable. Interestingly, UN1-xCx solid solutions obtained by isothermal conversion exhibit some more excellent properties, such as corrosion resistance. But the effect of composition on the mechanical and thermal properties is not clear yet. In this work, first-principles calculations were carried out to investigate the stabilities, mechanical and thermal properties of UN1-xCx (x = 0.00, 0.25, 0.50, 0.75 and 1.00). The impact of the on-site Coulomb repulsion term and spin-orbit coupling (SOC) on the properties of UN1-xCx were also discussed. The on-site Coulomb repulsion term is indispensable for the magnetic ground state, mechanical and thermal transport properties. Moreover, SOC has a negligible influence on the mechanical properties and can overestimate the thermal conductivities of UN1-xCx. Formation enthalpy, phonon dispersion and elastic constants calculations were preformed to prove the thermodynamic, dynamic and mechanical stability of UN1-xCx, respectively. The absence of a band gap in the density of states confirms the metallic nature of studied UN1-xCx. Theoretical analyses show that large-size carbon doping can induce lattice expansion and softening, resulting in the reduction of elastic moduli. The more localized density of states of UN1-xCx with carbon concentration demonstrate the weaker bond strength, which further verifies the variation of mechanical properties. The thermal conductivities of UN1-xCx calculated using PBE+U decrease firstly, then increase with the carbon concentration and increase with the temperature.
AB - Uranium nitride (UN) is considered to be a very promising candidate of accident-tolerant fuel. Since UN is commercially synthesized by carbothermic reduction-nitridation, the carbon in synthesized UN is unavoidable. Interestingly, UN1-xCx solid solutions obtained by isothermal conversion exhibit some more excellent properties, such as corrosion resistance. But the effect of composition on the mechanical and thermal properties is not clear yet. In this work, first-principles calculations were carried out to investigate the stabilities, mechanical and thermal properties of UN1-xCx (x = 0.00, 0.25, 0.50, 0.75 and 1.00). The impact of the on-site Coulomb repulsion term and spin-orbit coupling (SOC) on the properties of UN1-xCx were also discussed. The on-site Coulomb repulsion term is indispensable for the magnetic ground state, mechanical and thermal transport properties. Moreover, SOC has a negligible influence on the mechanical properties and can overestimate the thermal conductivities of UN1-xCx. Formation enthalpy, phonon dispersion and elastic constants calculations were preformed to prove the thermodynamic, dynamic and mechanical stability of UN1-xCx, respectively. The absence of a band gap in the density of states confirms the metallic nature of studied UN1-xCx. Theoretical analyses show that large-size carbon doping can induce lattice expansion and softening, resulting in the reduction of elastic moduli. The more localized density of states of UN1-xCx with carbon concentration demonstrate the weaker bond strength, which further verifies the variation of mechanical properties. The thermal conductivities of UN1-xCx calculated using PBE+U decrease firstly, then increase with the carbon concentration and increase with the temperature.
KW - Electronic structure
KW - First-principles calculation
KW - Mechanical property
KW - Thermal transport property
KW - Uranium alloys and compounds
UR - http://www.scopus.com/inward/record.url?scp=85137156659&partnerID=8YFLogxK
U2 - 10.1016/j.jnucmat.2022.153991
DO - 10.1016/j.jnucmat.2022.153991
M3 - 文章
AN - SCOPUS:85137156659
SN - 0022-3115
VL - 571
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 153991
ER -