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James Dark
James Dark
CEA Cadarache
Verified email at cea.fr
Title
Cited by
Cited by
Year
Atomistic Simulations of the Defect Chemistry and Self-Diffusion of Li-ion in LiAlO2
N Kuganathan, J Dark, EN Sgourou, Y Panayiotatos, A Chroneos
Energies 12 (15), 2895, 2019
82019
Fuel retention in WEST and ITER divertors based on FESTIM monoblock simulations
R Delaporte-Mathurin, H Yang, J Denis, J Dark, EA Hodille, ...
Nuclear Fusion 61 (12), 126001, 2021
72021
Influence of hydrogen trapping on WCLL breeding blanket performances
J Dark, R Delaporte-Mathurin, Y Charles, EA Hodille, C Grisolia, ...
Nuclear Fusion 61 (11), 116076, 2021
52021
FESTIM: An open-source code for hydrogen transport simulations
R Delaporte-Mathurin, J Dark, G Ferrero, EA Hodille, V Kulagin, ...
International Journal of Hydrogen Energy 63, 786-802, 2024
2024
Hydrogen isotopes concentration profiles: Numerical assessments considering realistic trap sites distributions in tungsten divertor monoblock
A Durif, EA Hodille, JM Bergeaud, J Dark, Y Charles, J Mougenot, ...
21st International Conference on Fusion Reactor Materials (ICFRM), 2023
2023
Understanding Tritium Inventory And Permeation In Materials For Fusion Reactors: A Coupled Experimental And Modelling Approach
E Bernard, EA Hodille, F Montupet-Leblond, M Ialovega, M Payet, ...
29th IAEA Fusion Energy Conference (FEC 2023), 2023
2023
Multiphysics tritium transport modelling in WCLL breeding blankets: Influence of MHD effects and neutron damage
J Dark, J Mougenot, EA Hodille, Y Charles
15th International Symposium on Fusion Nuclear Technology (ISFNT-15), 2023
2023
2D Tritium retention prediction in the ITER/DEMO actively cooled divertor in the presence of neutron induced defects
EA Hodille, J Dark, R Delaporte-Mathurin, C Grisolia, Y Charles, ...
15th International Symposium on Fusion Nuclear Technology (ISFNT-15), 2023
2023
Modelling neutronic damage effects on tritium transport in tungten
J Dark, EA Hodille, R Delaporte-Mathurin, T Schwartz-Selinger, ...
30th Symposium on Fusion Engineering (SOFE), 2023
2023
Multi-physics modelling of nuclear fusion device sub-components: The tritium breeding blanket
J Dark, R Delaporte-Mathurin, EA Hodille, J Mougenot, Y Charles
FEniCS 2023, 2023
2023
Diffusion d’atomes assistée par les champs thermomécaniques dans les composants des tokamaks
S Bian, J Dark, R Delaporte-Mathurin, EA Hodille, C Grisolia, Y Charles, ...
Conférence internationale MATÉRIAUX 2022, 2022
2022
Modelling of tritium transport in WCLL breeding blankets: influence of neutron induced damage
J Dark, R Delaporte-Mathurin, EA Hodille, J Mougenot, Y Charles, ...
SOFT2022-32nd Symposium on Fusion Technology, 2022
2022
Transport d'hydrogène assisté par les champs thermomécaniques
A Coatmeur, F Hautem, S Bian, J Dark, Y Charles, S Queyreau, ...
5ème colloque de prospective de la FR-FCM, 2022
2022
Modelling hydrogen transport in breeding blankets: influence of trapping effects
J Dark, R Delaporte-Mathurin, J Mougenot, Y Charles, EA Hodille, ...
2nd Fusion HPC Workshop, 2021
2021
Modelling hydrogen transport in ITER divertor
R Delaporte-Mathurin, H Yang, J Denis, J Dark, EA Hodille, ...
16th European Vacuum Conference, 2021
2021
Modelling WCLL breeder blankets
J Dark, R Delaporte-Mathurin, Y Charles, EA Hodille, C Grisolia, ...
15th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials, 2021
2021
FESTIM, a modelling code for hydrogen transport in materials for nuclear fusion applications
R Delaporte-Mathurin, EA Hodille, J Dark, F Leblond, J Mougenot, ...
FEniCS 2021, 2021
2021
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