Simulations of self- and Xe diffusivity in uranium mononitride including chemistry and irradiation effects

被引:6
|
作者
Cooper, M. W. D. [1 ]
Rizk, J. [1 ]
Matthews, C. [1 ]
Kocevski, V. [1 ]
Craven, G. T. [2 ]
Gibson, T. [2 ]
Andersson, D. A. [1 ]
机构
[1] Los Alamos Natl Lab, Mat Sci & Technol Div, POB 1663, Los Alamos, MN 87545 USA
[2] Los Alamos Natl Lab, Theoret Div, POB 1663, Los Alamos, MN USA
关键词
POINT-DEFECTS; XENON DIFFUSION; FUEL; UO2; NITRIDE; COEFFICIENTS; PLUTONIUM; DIOXIDE; RELEASE; UN;
D O I
10.1016/j.jnucmat.2023.154685
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
A combination of density functional theory and empirical potential atomic scale simulations have been used to determine a model for defect stability and mobility in uranium mononitride (UN), as a function of temperature (T) and N-2 partial pressure (P-N2). Using the model, predictions of hypo-stoichiometry under U-rich conditions compare favorably to CALPHAD calculations using the TAF-ID database. Furthermore, our predictions of U and N self-diffusivity are in good agreement with experiments carried out as a function of T at specific partial pressures under thermal equilibrium. The validated atomic scale data have then been implemented within a cluster dynamics method to simulate irradiation-enhanced defect concentrations. All defects and clusters studied have significantly enhanced concentrations, with respect to thermal equilibrium, as T is lowered. The irradiation-enhanced Xe diffusivity is compared to post-irradiation annealing and in-pile experiments. The contributions of various defects and clusters to non-stoichiometry, self-diffusivity, and Xe diffusivity are discussed.
引用
收藏
页数:15
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