gabriele-ferrero / Titans_TT_codecomparison

A code comparison study between 3 different Tritium transport codes for the TITANS project
MIT License
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Titans_TT_codecomparison

A code comparison study between 3 different Tritium transport softwares for the TITANS project mHIT code is based on COMSOL: Candido, L., & Alberghi, C. (2021). Verification and validation of mHIT code over TMAP for hydrogen isotopes transport studies in fusion-relevant environments. Fusion Engineering and Design, 172, 112740. FESTIM code is open source

The employed FESTIM version is 1.1.1. How to install festim

To install all the dependencies for running FESTIM models and plotting scripts with Conda:

conda env create -f environment.yml

COMSOL version for this study is 6.1. Previous COMSOL versions won't work.

Delaporte-Mathurin, Rémi, et al. "FESTIM: An open-source code for hydrogen transport simulations." International Journal of Hydrogen Energy 63 (2024): 786-802

R. Delaporte-Mathurin, et al., Finite Element Analysis of Hydrogen Retention in ITER Plasma Facing Components using FESTIM. Nuclear Materials and Energy, 21, (2019).

R. Delaporte-Mathurin, et al.,Parametric Study of Hydrogenic Inventory in the ITER Divertor Based on Machine Learning. Scientific Reports, 10, (2020).

J. Dark, et al., Influence of hydrogen trapping on WCLL breeding blanket performances. Nuclear Fusion, 62, (2021). https://doi.org/10.1088/1741-4326/ac28b0.

MHIMS : Montupet-Leblond, F., Hodille, E. A., Payet, M., Delaporte-Mathurin, R., Bernard, E., Charles, Y., ... & Grisolia, C. (2022). Influence of traps reversibility on hydrogen permeation and retention in Eurofer97. Nuclear Fusion, 62(8), 086011.

Hodille, E. A., Markelj, S., Pecovnik, M., Ajmalghan, M., Piazza, Z. A., Ferro, Y., ... & Grisolia, C. (2020). Kinetic model for hydrogen absorption in tungsten with coverage dependent surface mechanisms. Nuclear Fusion, 60(10), 106011.

Bernard, Elodie, et al. "Tritium retention in W plasma-facing materials: Impact of the material structure and helium irradiation." Nuclear Materials and Energy 19 (2019): 403-410.