Thermal energy transport in oxide nuclear fuel
To efficiently capture the energy of the nuclear bond, advanced nuclear reactor concepts
seek solid fuels that must withstand unprecedented temperature and radiation extremes. In …
seek solid fuels that must withstand unprecedented temperature and radiation extremes. In …
Impact of grain boundary and surface diffusion on predicted fission gas bubble behavior and release in UO2 fuel
In this work, we quantify the impact of grain boundary (GB) and surface diffusion on fission
gas bubble evolution and fission gas release in UO 2 nuclear fuel using simulations with a …
gas bubble evolution and fission gas release in UO 2 nuclear fuel using simulations with a …
Fission gas diffusion and release for Cr2O3-doped UO2: From the atomic to the engineering scale
The anticipated benefits of large grains in Cr 2 O 3-doped UO 2 pellets include improved
mechanical and fission gas retention properties. To support the assessment of fission gas …
mechanical and fission gas retention properties. To support the assessment of fission gas …
Accelerating nuclear fuel development and qualification: Modeling and simulation integrated with separate-effects testing
An approach to transform and accelerate nuclear fuel development and qualification is
outlined. The approach exploits advanced modeling and simulation at the outset to inform …
outlined. The approach exploits advanced modeling and simulation at the outset to inform …
Effect of grain size on irradiation-induced bubble evolution in high burn-up UO2: A phase-field study
Y Jiang, Y La, X Liu, W Liu - Journal of Nuclear Materials, 2024 - Elsevier
Due to economic reasons, uranium dioxide (UO 2) ceramic fuel needs to operate under high
burn-up conditions. The high burn-up structure (HBS) and micrometric irradiation-induced …
burn-up conditions. The high burn-up structure (HBS) and micrometric irradiation-induced …
Modeling mesoscale fission gas behavior in UO2 by directly coupling the phase field method to spatially resolved cluster dynamics
Fission gas release within uranium dioxide nuclear fuel occurs as gas atoms diffuse through
grains and arrive at grain boundary (GB) bubbles; these GB bubbles grow and interconnect …
grains and arrive at grain boundary (GB) bubbles; these GB bubbles grow and interconnect …
The role of irradiation-enhanced interstitial diffusion in over-pressurizing fission gas bubbles in UO2
Fission gas bubbles in UO 2 nuclear fuel have been observed to exhibit pressures in excess
of the equilibrium bubble pressure; however, the cause of bubble over-pressurization has …
of the equilibrium bubble pressure; however, the cause of bubble over-pressurization has …
Bayesian calibration with summary statistics for the prediction of xenon diffusion in UO2 nuclear fuel
The evolution and release of fission gas impacts the performance of UO 2 nuclear fuel. We
have created a Bayesian framework to calibrate a novel model for fission gas transport that …
have created a Bayesian framework to calibrate a novel model for fission gas transport that …
A combined theoretical-experimental investigation of thermal transport in low-dose irradiated thorium dioxide
During reactor operation, nuclear fuels are subject to extreme temperature and irradiation
conditions which can significantly degrade the fuel's thermal transport properties. The …
conditions which can significantly degrade the fuel's thermal transport properties. The …
TEM characterization of dislocation loops in proton irradiated single crystal ThO2
This work focuses on the full characterization of dislocation loops induced by proton
irradiation in single-crystal ThO 2. Irradiation was performed using 2 MeV H+ ions with …
irradiation in single-crystal ThO 2. Irradiation was performed using 2 MeV H+ ions with …