Thermal energy transport in oxide nuclear fuel

DH Hurley, A El-Azab, MS Bryan, MWD Cooper… - Chemical …, 2021 - ACS Publications
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 …

Fission gas release from UO2 nuclear fuel: A review

J Rest, MWD Cooper, J Spino, JA Turnbull… - Journal of Nuclear …, 2019 - Elsevier
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 …

Reduced anharmonic phonon scattering cross-section slows the decrease of thermal conductivity with temperature

X Yang, J Tiwari, T Feng - Materials Today Physics, 2022 - Elsevier
Without anharmonic phonon scattering, crystals could have infinite or “super” intrinsic bulk
thermal conductivity. Anharmonic phonon scattering rates usually increase with temperature …

Validating the BISON fuel performance code to integral LWR experiments

RL Williamson, KA Gamble, DM Perez… - … Engineering and Design, 2016 - Elsevier
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 …

Fission gas diffusion and release for Cr2O3-doped UO2: From the atomic to the engineering scale

MWD Cooper, G Pastore, Y Che, C Matthews… - Journal of Nuclear …, 2021 - Elsevier
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 …

[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 …

[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 …

Impact of irradiation induced dislocation loops on thermal conductivity in ceramics

M Khafizov, J Pakarinen, L He… - Journal of the American …, 2019 - Wiley Online Library
Experimental work aimed at understanding the role of dislocation loops in limiting phonon
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

CA Dennett, WR Deskins, M Khafizov, Z Hua… - Acta Materialia, 2021 - Elsevier
Advanced nuclear reactor concepts aim to use fuels that must withstand unprecedented
temperature and radiation extremes. In these fuels, thermal energy transport under …

Mechanistic materials modeling for nuclear fuel performance

MR Tonks, D Andersson, SR Phillpot, Y Zhang… - Annals of nuclear …, 2017 - Elsevier
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 …