[HTML][HTML] On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM®: state of the art, lessons learned and perspectives
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 …
applications has grown from a sporadic use for exploratory studies to a widespread …
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 …
[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 …
[HTML][HTML] Towards coupling conventional with high-fidelity fuel behavior analysis tools
Multi-dimensional fuel performance codes have the potential to enhance the understanding
of complex phenomena affecting fuel integrity, but their application is often limited by the …
of complex phenomena affecting fuel integrity, but their application is often limited by the …
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 …
A mortar thermomechanical contact computational framework for nuclear fuel performance simulation
Nuclear fuel performance simulations involve the modeling of complex physical
phenomena, ranging from fission gas release to fuel swelling and other temperature …
phenomena, ranging from fission gas release to fuel swelling and other temperature …
Development of a point-kinetics model in OpenFOAM, integration in GeN-Foam, and validation against FFTF experimental data
Following the growing interest that we observe in the use of OpenFOAM for nuclear reactor
analysis, the current work presents a point-kinetics model and associated open-source code …
analysis, the current work presents a point-kinetics model and associated open-source code …
[HTML][HTML] Development of a novel two-phase flow solver for nuclear reactor analysis: algorithms, verification and implementation in OpenFOAM
A porous medium-based representation of nuclear reactors and complex engineering
systems more in general can significantly reduce simulation and modelling costs, while …
systems more in general can significantly reduce simulation and modelling costs, while …
Multiphysics analysis of heat pipe cooled microreactor core with adjusted heat sink temperature for thermal stress reduction using OpenFOAM coupled with neutronics …
MJ Jeong, J Im, S Lee, HK Cho - Frontiers in Energy Research, 2023 - frontiersin.org
Heat-pipe-cooled microreactors (HPRs) have advantages such as a compact design, easy
transportation, and improved system reliability and stability. The core of an HPR consists of …
transportation, and improved system reliability and stability. The core of an HPR consists of …
Assessing the PLEIADES/GERMINAL V3 fuel performance code against transmutation experiments in sodium fast reactors
T Barani, F Bernachy-Barbe, N Chauvin, C Fillaux… - Annals of Nuclear …, 2024 - Elsevier
We present the results of a first assessment of the multiphysics PLEIADES/GERMINAL V3
fuel performance code against integral irradiation experiments of americium-bearing MOX …
fuel performance code against integral irradiation experiments of americium-bearing MOX …