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 …
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 …
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 …
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 …
[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 …
Empirical and mechanistic transient fission gas release model for high-burnup LOCA conditions
In response to the nuclear industry desire to extend burnup beyond current licensing
practices, the US Nuclear Regulatory Commission (NRC) released a research information …
practices, the US Nuclear Regulatory Commission (NRC) released a research information …
Kriging-based inverse uncertainty quantification of nuclear fuel performance code BISON fission gas release model using time series measurement data
In nuclear reactor fuel performance simulation, fission gas release (FGR) and swelling
involve treatment of several complicated and interrelated physical processes, which …
involve treatment of several complicated and interrelated physical processes, which …
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 …