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 …
[HTML][HTML] SCIANTIX: a new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes
D Pizzocri, T Barani, L Luzzi - Journal of Nuclear Materials, 2020 - Elsevier
Bridging lower length-scale calculations with the engineering-scale simulations of fuel
performance codes requires the development of dedicated intermediate-scale codes. In this …
performance codes requires the development of dedicated intermediate-scale codes. In this …
[HTML][HTML] The SCIANTIX code for fission gas behaviour: Status, upgrades, separate-effect validation, and future developments
G Zullo, D Pizzocri, L Luzzi - Journal of Nuclear Materials, 2023 - Elsevier
SCIANTIX is a 0D, open-source code designed to model inert gas behaviour within nuclear
fuel at the scale of the grain. The code predominantly employs mechanistic approaches …
fuel at the scale of the grain. The code predominantly employs mechanistic approaches …
The TRANSURANUS fuel performance code
A Magni, A Del Nevo, L Luzzi, D Rozzia… - Nuclear Power Plant …, 2021 - Elsevier
TRANSURANUS is a computer program for the thermal and mechanical analysis of fuel rods
irradiated in nuclear reactors. It was originally developed at the Institute for Transuranium …
irradiated in nuclear reactors. It was originally developed at the Institute for Transuranium …
Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions
In this work, we present a model of fission gas behavior in U 3 Si 2 under light water reactor
(LWR) conditions for application in engineering fuel performance codes. The model includes …
(LWR) conditions for application in engineering fuel performance codes. The model includes …
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 …
[HTML][HTML] Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation
We propose a model describing the HBS formation and the progressive intra-granular xenon
depletion in UO2. The HBS formation is modeled employing the Kolmogorov-Johnson-Mehl …
depletion in UO2. The HBS formation is modeled employing the Kolmogorov-Johnson-Mehl …
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 …
An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution
Fission gas release and gaseous swelling in nuclear fuel are driven by the transport of
fission gas from within the fuel grains to grain boundaries (intra-granular fission gas …
fission gas from within the fuel grains to grain boundaries (intra-granular fission gas …
Microstructure modeling of nuclear structural materials: Recent progress and future directions
JH Ke - Computational Materials Science, 2023 - Elsevier
Modeling and simulation of microstructures are essential to understand the complex
responses and behaviors of nuclear materials in extreme environments. The needs to …
responses and behaviors of nuclear materials in extreme environments. The needs to …