Modelling intra-granular bubble movement and fission gas release during post-irradiation annealing of UO2 using a meso-scale and spatialized approach

Thermal behaviour of caesium implanted in UO2: A comparative study with the xenon behaviour

“…Walker et al [12]. In our experimental conditions, no significant release or diffusion of Xe could be numerically addressed the migration of the fission gas bubbles in [51] and showed that the influx of vacancies from the surface towards the bulk would create a vacancy concentration gradient. The consequence is a directed diffusion of bubbles towards the surface accelerating the release of the gas.…”

Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling

“…Some fission gas models used in fuel performance codes account for meso-scale phenomena. Examples of such models are GRSW-A [37] or a recent model developed by Verma et al [38] . The Henry's law correlations derived by Cognini et al have been compared to experimental measurements in Fig.…”

Multiscale Modeling of Radiation Damage in UO₂ under Accelerated Burnup Conditions

“…The fuel models available in the engineering-scale fuel performance code BISON can be highly sensitive to microstructural features such as fuel porosity and grain size [4]. Modeling the microstructural evolution of UO 2 has been the subject of much research [5,6,7,8,9,10]. The phase field method is a powerful tool to predict a material's microstructural evolution [11] and has been applied to radiation damage problems [8,12,13,6].…”