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 …
[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 …
Ion irradiation and modification: The role of coupled electronic and nuclear energy dissipation and subsequent nonequilibrium processes in materials
Understanding material responses to energy deposition from energetic charged particles is
important for defect engineering, ion-beam processing, ion-beam analysis and modification …
important for defect engineering, ion-beam processing, ion-beam analysis and modification …
A critical review of high burnup fuel fragmentation, relocation, and dispersal under loss-of-coolant accident conditions
High burnup fuel in excess of~ 6268 GWd/MTU has been observed to severely fragment
when subjected to temperature transient conditions as in a loss-of-coolant accident. In the …
when subjected to temperature transient conditions as in a loss-of-coolant accident. In the …
[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 …
Cluster dynamics simulation of xenon diffusion during irradiation in UO2
Diffusion of fission gas in UO 2 nuclear fuel impacts several important performance metrics,
such as fission gas release, swelling, and thermal conductivity. Current empirical models of …
such as fission gas release, swelling, and thermal conductivity. Current empirical models of …
Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5%
Recent advances in nuclear fuel materials research, particularly on the topic of accident-
tolerant fuels, have brought up potential opportunities for expanding the operating envelope …
tolerant fuels, have brought up potential opportunities for expanding the operating envelope …
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 …