Publications
Research powered by FESTIM. If your paper uses FESTIM and is not listed here, let us know.
Coupled CFD and Tritium Transport Modeling of a Permeator Probe for Tritium Concentration in Liquids
Zenodo (CERN European Organization for Nuclear Research), 2026
FESTIM v2.0: Upgraded framework for multi-species hydrogen transport and enhanced performance
International Journal of Hydrogen Energy, 2026
Hydrogen Inventory Simulations for PFCs (HISP)
arXiv (Cornell University), 2026
Modeling and analysis of Tritium trapping in breeding blankets.
MSc thesis, Politecnico di Torino, 2026
Modeling hydrogen isotope transport behavior in the first wall: role of the bonding region in W-RAFM steel with an improved evaluation of transport coefficients
Nuclear Fusion, 2026
Permeation behaviour of hydrogen isotopes in molten FLiBe (2LiF-BeF2): Identifying sources of uncertainty and associated measurement challenges
arXiv (Cornell University), 2026
Physics-informed tritium fuel cycle modelling workflow for fusion reactors
arXiv (Cornell University), 2026
Tritium retention in the ITER/DEMO actively cooled tungsten monoblock in the presence of neutron-induced defects
International Journal of Hydrogen Energy, 2026
Impact of trapping on tritium self-sufficiency and tritium inventories in fusion power plant fuel cycles
Nuclear Fusion, 2025
Verification, validation, and cross-comparison of tritium transport codes FESTIM, MHIMS, and mHIT
Nuclear Materials and Energy, 2025
FESTIM: An open-source code for hydrogen transport simulations
International Journal of Hydrogen Energy, 2024
Kinetic surface model in FESTIM: Verification and validation
International Journal of Hydrogen Energy, 2024
Modeling Hydrogen Transport in BABY
BSc thesis, DSpace@MIT (Massachusetts Institute of Technology), 2024
Modelling neutron damage effects on tritium transport in tungsten
Nuclear Fusion, 2024
Multiphysics tritium transport simulations of the WCLL breeding blanket for DEMO
PhD thesis, 2024
3D effects on hydrogen transport in ITER-like monoblocks
Nuclear Fusion, 2023
Hydrogen transport in tokamaks: estimation of the ITER divertor tritium inventory and influence of helium exposure
PhD thesis, theses.fr (ABES), 2022
Fuel retention in WEST and ITER divertors based on FESTIM monoblock simulations
Nuclear Fusion, 2021
Influence of hydrogen trapping on WCLL breeding blanket performances
Nuclear Fusion, 2021
Influence of interface conditions on hydrogen transport studies
Nuclear Fusion, 2021
Modelling of hydrogen isotopes trapping, diffusion and permeation in divertor monoblocks under ITER-like conditions
Nuclear Fusion, 2021
Parametric optimisation based on TDS experiments for rapid and efficient identification of hydrogen transport materials properties
Nuclear Materials and Energy, 2021
Parametric study of hydrogenic inventory in the ITER divertor based on machine learning
Scientific Reports, 2020
Finite element analysis of hydrogen retention in ITER plasma facing components using FESTIM
Nuclear Materials and Energy, 2019