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 …
Fission gas release from UO2 nuclear fuel: A review
Gaseous fission product generation, transport, and release can have a large impact on
nuclear fuel performance, degrading fuel and fuel–cladding gap properties. Over the past …
nuclear fuel performance, degrading fuel and fuel–cladding gap properties. Over the past …
Reduced anharmonic phonon scattering cross-section slows the decrease of thermal conductivity with temperature
Without anharmonic phonon scattering, crystals could have infinite or “super” intrinsic bulk
thermal conductivity. Anharmonic phonon scattering rates usually increase with temperature …
thermal conductivity. Anharmonic phonon scattering rates usually increase with temperature …
Validating the BISON fuel performance code to integral LWR experiments
BISON is a modern finite element-based nuclear fuel performance code that has been under
development at Idaho National Laboratory (INL) since 2009. The code is applicable to both …
development at Idaho National Laboratory (INL) since 2009. The code is applicable to both …
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 …
Impact of irradiation induced dislocation loops on thermal conductivity in ceramics
Experimental work aimed at understanding the role of dislocation loops in limiting phonon
mediated thermal transport in ceramics is presented. Faulted dislocation loops, having …
mediated thermal transport in ceramics is presented. Faulted dislocation loops, having …
An integrated experimental and computational investigation of defect and microstructural effects on thermal transport in thorium dioxide
Advanced nuclear reactor concepts aim to use fuels that must withstand unprecedented
temperature and radiation extremes. In these fuels, thermal energy transport under …
temperature and radiation extremes. In these fuels, thermal energy transport under …
Mechanistic materials modeling for nuclear fuel performance
Fuel performance codes are critical tools for the design, certification, and safety analysis of
nuclear reactors. However, their ability to predict fuel behavior under abnormal conditions is …
nuclear reactors. However, their ability to predict fuel behavior under abnormal conditions is …