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
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 …
nuclear fuel performance, degrading fuel and fuel–cladding gap properties. Over the past …
BISON: A flexible code for advanced simulation of the performance of multiple nuclear fuel forms
BISON is a nuclear fuel performance application built using the Multiphysics Object-Oriented
Simulation Environment (MOOSE) finite element library. One of its major goals is to have a …
Simulation Environment (MOOSE) finite element library. One of its major goals is to have a …
Unit mechanisms of fission gas release: Current understanding and future needs
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 …
degrading fuel and gap properties. While gaseous fission product behavior has been …
An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions
Abstract Iron-chromium-aluminum (FeCrAl) alloys are candidates to be used as nuclear fuel
cladding for increased accident tolerance. An analysis of the response of FeCrAl under …
cladding for increased accident tolerance. An analysis of the response of FeCrAl under …
[HTML][HTML] A review of fuel performance modelling
P Van Uffelen, J Hales, W Li, G Rossiter… - Journal of Nuclear …, 2019 - Elsevier
Dr. Paul Van Uffelen graduated from the Vrije Universiteit Brussel (Belgium) and the Ecole
Nationale Supérieure Polytechnique de Grenoble (France) with a master degree in …
Nationale Supérieure Polytechnique de Grenoble (France) with a master degree in …
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 …
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 …