DIFFER

C.A. Orrico

First name
C.A.
Last name
Orrico
ORCID
0000-0001-8522-0974
Mazon, D., Vayakis, G., Walsh, M., Yun, G., Hong, S. H., de Baar, M., … team, W. (2025). Diagnostics: Chapter 8 of the special issue: on the path to tokamak burning plasma operation. Nuclear Fusion, 65(11), 113001. https://doi.org/10.1088/1741-4326/adfc7c
Orrico, C., Abate, D., van Berkel, M., Bosman, T., Ceelen, L., Heemels, W. P., … Krishnamoorthy, D. (2025). Predictive density profile control with discrete pellets, applied to integrated simulations of ITER. Nuclear Fusion, 65(7), 076041. https://doi.org/10.1088/1741-4326/ade54e
Tanke, V. F., Al, R. S., Alonso van der Westen, S., Brons, S., Classen, I. G. J., van Dommelen, J. A. W., … Morgan, T. W. (2023). LiMeS-Lab: An Integrated Laboratory for the Development of Liquid–Metal Shield Technologies for Fusion Reactors. Journal of Fusion Energy, 42(2), 44. https://doi.org/10.1007/s10894-023-00379-3 (Original work published 2023)
Orrico, C., van Berkel, M., Bosman, T., Heemels, W. P., & Krishnamoorthy, D. (2023). Mixed-integer MPC Strategies for Fueling and Density Control in Fusion Tokamaks. IEEE Control Systems Letters, 7(2023), 1897-1902. https://doi.org/10.1109/LCSYS.2023.3282891
Orrico, C., Ravensbergen, T., Pitts, R. A., Bonnin, X., Kaveeva, E., Park, J. S., … de Baar, M. (2023). Evaluation of ITER divertor shunts as a synthetic diagnostic for detachment control. Nuclear Fusion, 63(8), 086002. https://doi.org/10.1088/1741-4326/acd947