论文标题
Fe2mo Laves阶段热膨胀路径的第一原理调子计算
First-principles phonon calculations of thermal expansion path of Fe2Mo Laves phase
论文作者
论文摘要
在核燃料和燃料元件覆盖层之间界面处的拓扑密封的Fe2mo Laves阶段的降水可以显着削弱覆层和燃料的强度特性。尽管为燃料杆的覆层设计材料的重要性,但Fe2MO的热力学特性和热膨胀路径的轨迹仍然鲜为人知。 Fe2MO的热力学特性已在准谐波近似值下使用密度功能理论的框架内使用有限温度量子机械计算进行了研究。使用声子计算获得了对自由能的振动贡献。通过在不同方向上计算的自由能之间比较Fe2MO的热膨胀路径。选择最少能量的路径作为热膨胀的轨迹。将获得的结果与以前的理论工作中计算的路径进行了比较,使用了Debye-Gruneisen方法,并考虑了磁性子系统来计算自由能的振动和磁贡献。这种比较表明,这两种方法彼此吻合。这项工作表明,Fe2MO具有非异型热膨胀。在恒压下的热容量和体积扩张进行了建模。分析的计算结果与实验数据达成了令人满意的一致性。获得的结果可用于进一步设计用于IV代反应堆的燃料元件覆层材料,其工作温度应高于873K。
Precipitation of the topologically close-packed Fe2Mo Laves phase at the interface between the nuclear fuel and the fuel element cladding can significantly weaken the strength characteristics of the cladding and fuel. Despite the importance of designing materials for the cladding of fuel rods, the thermodynamic properties and the trajectory of the thermal expansion path of the Fe2Mo remain poorly understood. The thermodynamic properties of the Fe2Mo have been studied using the finite-temperature quantum mechanical calculations within the frame of the density functional theory under the quasi-harmonic approximation. The vibrational contribution to the free energy was obtained using phonon calculations. The thermal expansion path of Fe2Mo was predicted by comparing between free energies calculated in different directions. A path with the least energy was chosen as the trajectory of thermal expansion. The obtained result was compared with the path calculated in previous theoretical work used the Debye-Gruneisen approach and accounted magnetic subsystem to calculate the vibrational and magnetic contributions to the free energy. This comparison reveals that these two approaches are in good agreement with each other. The work shows that the Fe2Mo possesses a non-isotropic thermal expansion. The heat capacity and volumetric expansion at constant pressure are modeled. The calculated results analyzed and are in satisfactory agreement with the experimental data. Obtained results can be useful for further design of fuel element cladding materials intended for generation IV reactors, the operating temperature of which should be above 873 K.