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 …

Unit mechanisms of fission gas release: Current understanding and future needs

M Tonks, D Andersson, R Devanathan… - Journal of Nuclear …, 2018 - Elsevier
Gaseous fission product transport and release has a large impact on fuel performance,
degrading fuel and gap properties. While gaseous fission product behavior has been …

Physics-based modelling of fission gas swelling and release in UO2 applied to integral fuel rod analysis

G Pastore, L Luzzi, V Di Marcello… - Nuclear Engineering and …, 2013 - Elsevier
A physics-based model is developed for analysing the coupled phenomena of fission gas
swelling and release in UO2 fuel during irradiation. The model is featured by a level of …

Uncertainty and sensitivity analysis of fission gas behavior in engineering-scale fuel modeling

G Pastore, LP Swiler, JD Hales, SR Novascone… - Journal of Nuclear …, 2015 - Elsevier
The role of uncertainties in fission gas behavior calculations as part of engineering-scale
nuclear fuel modeling is investigated using the BISON fuel performance code with a recently …

Atomistic modeling of intrinsic and radiation-enhanced fission gas (Xe) diffusion in UO2±x: Implications for nuclear fuel performance modeling

DA Andersson, P Garcia, XY Liu, G Pastore… - Journal of Nuclear …, 2014 - Elsevier
Based on density functional theory (DFT) and empirical potential calculations, the diffusivity
of fission gas atoms (Xe) in UO 2 nuclear fuel has been calculated for a range of non …

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 …

A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools

D Pizzocri, G Pastore, T Barani, A Magni, L Luzzi… - Journal of Nuclear …, 2018 - Elsevier
The description of intra-granular fission gas behaviour is a fundamental part of any model for
the prediction of fission gas release and swelling in nuclear fuel. In this work we present a …

An improved xenon equation of state for nanobubbles in UO2

L Yang, BD Wirth - Journal of Nuclear Materials, 2022 - Elsevier
To understand the thermodynamic behavior of xenon (Xe) bubbles in uranium dioxide (UO
2), the pressure of Xe nanobubbles as a function of temperature was systematically …

Understanding xenon and vacancy behavior in UO 2, UN and U 3 Si 2: a comparative DFT+ U study

J Zhao, D Sun, L Xi, P Chen, J Zhao… - Physical Chemistry …, 2023 - pubs.rsc.org
Extensive attention has been paid to accident tolerant fuels (ATFs), such as uranium
mononitride (UN) and uranium sesquisilicide (U3Si2), which are regarded as potential …

Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients

T Barani, G Pastore, A Magni, D Pizzocri… - Journal of Nuclear …, 2020 - Elsevier
The description of intra-granular fission gas behavior during irradiation is a fundamental part
of models used for the calculation of fission gas release and gaseous swelling in nuclear …