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

Journal Article · · Journal of Nuclear Materials
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 N2 partial pressure (pN2). 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. In conclusion, the contributions of various defects and clusters to non-stoichiometry, self-diffusivity, and Xe diffusivity are discussed.
Research Organization:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
Sponsoring Organization:
USDOE Laboratory Directed Research and Development (LDRD) Program; USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
89233218CNA000001
OSTI ID:
1998128
Alternate ID(s):
OSTI ID: 2369057
Report Number(s):
LA-UR--23-21397
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 587; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

References (59)

Molecular and solid-state tests of density functional approximations: LSD, GGAs, and meta-GGAs journal January 1999
Fast Parallel Algorithms for Short-Range Molecular Dynamics journal March 1995
Constants of diatomic molecules book January 1979
Thermal and mechanical properties of uranium nitride prepared by SPS technique journal October 2008
Cation self-diffusion in UN1+x journal February 1971
The fission gas bubble distribution in uranium dioxide from high temperature irradiated sghwr fuel pins journal May 1977
Self-diffusion of plutonium in uranium-plutonium mononitride journal July 1978
Swelling analysis of highly-rated MX-type LMFBR fuels: II. Microsopic swelling behaviour journal June 1978
Self-diffusion of plutonium in high burn-up simulated (U, Pu) (C, N) and (U, Pu) N journal June 1980
The diffusion coefficients of gaseous and volatile species during the irradiation of uranium dioxide journal June 1982
A new fission-gas release model journal August 1983
Microstructure and fission gas bubbles in irradiated mixed carbide fuels at 2 to 11 a/o burnup journal May 1984
Trapping and solution of fission Xe in UO2. journal January 1985
Material property correlations for uranium mononitride journal May 1990
Ion implantation studies of UO2 and UN journal June 1992
Point Defects and Transport Properties in Carbides and Nitrides book December 1988
Thermodynamic modelling of the N–U system journal July 2000
Thermophysical properties of uranium dioxide journal March 2000
Relations between the Concentrations of Imperfections in Crystalline Solids book January 1956
Phase and defect evolution in uranium-nitrogen-oxygen system under irradiation journal April 2021
TAF-ID: An international thermodynamic database for nuclear fuels applications journal March 2021
Bayesian calibration with summary statistics for the prediction of xenon diffusion in UO2 nuclear fuel journal June 2023
The diffusion of point defects in uranium mononitride: Combination of DFT and atomistic simulation with novel potential journal February 2016
Thermophysical and mechanical property assessment of UB2 and UB4 sintered via spark plasma sintering journal March 2020
Radiation stability of ZrN under 2.6MeV proton irradiation journal July 2009
Uranium nitride as LWR TRISO fuel: Thermodynamic modeling of U–C–N journal August 2012
Thermal conductivity of UO2+x and U4O9−y journal November 2013
GGA+U study of uranium mononitride: A comparison of the U-ramping and occupation matrix schemes and incorporation energies of fission products journal September 2016
Description of phase transitions through accumulation of point defects: UN, UO2 and UC journal November 2018
Density functional theory calculations of self- and Xe diffusion in U3Si2 journal March 2019
Atomistic modeling of out-of-pile xenon diffusion by vacancy clusters in UO2 journal July 2019
Cluster dynamics simulation of uranium self-diffusion during irradiation in UO2 journal December 2019
Cluster dynamics simulation of xenon diffusion during irradiation in UO2 journal November 2020
Improvement of the BISON U 3 Si 2 modeling capabilities based on multiscale developments to modeling fission gas behavior journal November 2021
Irradiation-enhanced diffusion and diffusion-limited creep in U3Si2 journal November 2021
First-principles investigation of uranium mononitride (UN): Effect of magnetic ordering, spin-orbit interactions and exchange correlation functional journal February 2022
Atomistic and cluster dynamics modeling of fission gas (Xe) diffusivity in TRISO fuel kernels journal April 2022
Development and application of a uranium mononitride (UN) potential: Thermomechanical properties and Xe diffusion journal April 2022
Properties and microstructure evolution of silicon nitride and zirconium nitride following Ni ion irradiation journal May 2022
An improved xenon equation of state for nanobubbles in UO2 journal December 2022
Finite temperature properties of uranium mononitride journal April 2023
Modeling of point defects and rare gas incorporation in uranium mono-carbide journal February 2007
Physics-based modelling of fission gas swelling and release in UO2 applied to integral fuel rod analysis journal March 2013
Determination of Krypton Diffusion Coefficients in Uranium Dioxide Using Atomic Scale Calculations journal December 2016
Some Phase Equilibria in the Uranium-Nitrogen System 1 journal January 1966
GULP: A computer program for the symmetry-adapted simulation of solids journal January 1997
Atomic mechanisms of mass transport in ceramic nuclear fuel materials journal January 1990
Diffusional Viscosity of a Polycrystalline Solid journal May 1950
A Model for Boundary Diffusion Controlled Creep in Polycrystalline Materials journal June 1963
First-principles study of intrinsic point defects and Xe impurities in uranium monocarbide journal October 2020
Theory of fission gas migration in UO 2 journal January 1980
Atomistic study of stability of xenon nanoclusters in uranium oxide journal May 2010
U and Xe transport in UO 2 ± x : Density functional theory calculations journal August 2011
First-principles calculations of uranium diffusion in uranium dioxide journal July 2012
Transport properties in dilute UN ( X ) solid solutions ( X = Xe , Kr ) journal November 2016
Nitrogen Diffusion in Uranium Nitride as Measured by Alpha Particle Activation of 15N journal December 1969
The Sodium-Bonding Pin Concept for Advanced Fuels Part I: Swelling of Carbide Fuel up to 12% Burnup journal December 1983
Notizen: Xe-133 Diffusion in UN Single Crystals journal January 1966
Multiscale Modeling of Uranium Mononitride: Point Defects Diffusion, Self-Diffusion, Phase Composition journal May 2017

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