[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 …
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 …
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 …
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 …
ALCYONE: the fuel performance code of the PLEIADES platform dedicated to PWR fuel rods behavior
The aim of this contribution is to deeply introduce the ALCYONE Fuel Performance Code.
ALCYONE is being implemented within the PLEIADES numerical framework and is …
ALCYONE is being implemented within the PLEIADES numerical framework and is …
Full core LOCA safety analysis for a PWR containing high burnup fuel
For economic reasons, the US nuclear industry is renewing efforts to build a technical basis
to extend peak rod average burnup limits above the current regulatory burnup limit of 62 …
to extend peak rod average burnup limits above the current regulatory burnup limit of 62 …
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 OFFBEAT multi-dimensional fuel behavior solver
Abstract The OpenFOAM Fuel BEhavior Analysis Tool, or OFFBEAT, is a multi-dimensional
fuel performance code under collaborative development at the Laboratory for Reactor …
fuel performance code under collaborative development at the Laboratory for Reactor …
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 …
Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS
The modelling of fission gas behaviour is a crucial aspect of nuclear fuel performance
analysis in view of the related effects on the thermo-mechanical performance of the fuel rod …
analysis in view of the related effects on the thermo-mechanical performance of the fuel rod …