[HTML][HTML] On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM®: state of the art, lessons learned and perspectives

C Fiorina, I Clifford, S Kelm, S Lorenzi - Nuclear Engineering and Design, 2022 - Elsevier
In the last two decades, the use of OpenFOAM as a multi-physics library for nuclear
applications has grown from a sporadic use for exploratory studies to a widespread …

[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 …

Challenges of high-fidelity virtual reactor for exascale computing and research progress of China Virtual Reactor

X Lu, Y Li, D Chen, G Chu, A Wang - Nuclear Engineering and Design, 2023 - Elsevier
The virtual reactor is a sophisticated software system deployed on supercomputers to
simulate physics process or predict component behaviors inside real reactors. It highly relies …

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 …

[HTML][HTML] Analysis of the performance of driver MOX fuel in the MYRRHA reactor under Beam Power Jump transient irradiation conditions

A Magni, M Di Gennaro, E Guizzardi, D Pizzocri… - … Engineering and Design, 2023 - Elsevier
This work focuses on the performance analysis of driver fuel pins under transient irradiation
conditions in the MYRRHA reactor, which must be considered besides the normal operation …

[HTML][HTML] Towards simulations of fuel rod behaviour during severe accidents by coupling TRANSURANUS with SCIANTIX and MFPR-F

G Zullo, D Pizzocri, L Luzzi, F Kremer, R Dubourg… - Annals of Nuclear …, 2023 - Elsevier
Among the applications of the multiscale modelling approach in nuclear fuel rod
performance, the coupling of integral thermo-mechanical fuel performance codes with lower …

[HTML][HTML] Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data

A Magni, L Luzzi, D Pizzocri, A Schubert… - Journal of Nuclear …, 2021 - Elsevier
Recycling and burning minor actinides (MA, eg, americium, neptunium) in mixed-oxide
(MOX) nuclear fuel is a strategic option for fast reactor concepts of Generation IV, especially …

[HTML][HTML] Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation

T Barani, D Pizzocri, F Cappia, L Luzzi… - Journal of Nuclear …, 2020 - Elsevier
We propose a model describing the HBS formation and the progressive intra-granular xenon
depletion in UO2. The HBS formation is modeled employing the Kolmogorov-Johnson-Mehl …

[HTML][HTML] Performance analysis and helium behaviour of Am-bearing fuel pins for irradiation in the MYRRHA reactor

L Luzzi, A Magni, S Billiet, M Di Gennaro… - … Engineering and Design, 2024 - Elsevier
Minor actinides are the main contributors to medium-and long-term radiotoxicity and heat
production in spent nuclear fuels. Research efforts are currently ongoing to explore different …

Modeling high burnup structure in oxide fuels for application to fuel performance codes. Part II: Porosity evolution

T Barani, D Pizzocri, F Cappia, G Pastore… - Journal of Nuclear …, 2022 - Elsevier
We propose a model describing the high burnup structure inter-granular porosity evolution
under irradiation. The evolution of the porosity collecting the gas diffusing from the grains is …