207
edits
LNF:Fuelling and Impurity Control Studies in the stellarators TJ-II and W7-X using Cryogenic Pellets and Tracer-Encapsulated Solid Pellets (TESPEL): Difference between revisions
Jump to navigation
Jump to search
LNF:Fuelling and Impurity Control Studies in the stellarators TJ-II and W7-X using Cryogenic Pellets and Tracer-Encapsulated Solid Pellets (TESPEL) (view source)
Revision as of 12:16, 7 November 2024
, 7 November→References
| Line 59: | Line 59: | ||
[4] The effect of pellet injection on turbulent transport in TJ-II, L. García, I. García-Cortés, B. A. Carreras, K. J. McCarthy, B. van Milligen and TJ-II team, Phys. Plasmas 30 (2023) 092303. https://doi.org/10.1063/5.0163832 | [4] The effect of pellet injection on turbulent transport in TJ-II, L. García, I. García-Cortés, B. A. Carreras, K. J. McCarthy, B. van Milligen and TJ-II team, Phys. Plasmas 30 (2023) 092303. https://doi.org/10.1063/5.0163832 | ||
[5] Using rational surfaces to improve pellet fuelling efficiency in stellarators, N. Panadero, K. J. McCarthy, B. Pégourié, R. Carrasco, I. García-Cortés, R. García, J. Hernández-Sánchez, F. Köchl, J. Mártinez-Fernández, and R. Sakamoto, J. Plasma Phys. 89 (2023) 955890601. https://doi:10.1017/S0022377823001010 | [5] Using rational surfaces to improve pellet fuelling efficiency in stellarators, N. Panadero, K. J. McCarthy, B. Pégourié, R. Carrasco, I. García-Cortés, R. García, J. Hernández-Sánchez, F. Köchl, J. Mártinez-Fernández, and R. Sakamoto, J. Plasma Phys. 89 (2023) 955890601. https://doi:10.1017/S0022377823001010. | ||
[6] | [6] Impact of the rotational transform on enhanced confinement in the TJ-II stellarator. Part 1: experimental results, B. Ph. van Milligen, I. García-Cortés, K. J. McCarthy, T. Estrada, A. Cappa, P. Pons-Villalonga, B. A. Carreras, L. García, O. S. Kozachok, O. O. Chmyga, J. L. de Pablos, J. M. Barcala, A Molinero, D. Tafalla, I. Pastor, A. de la Peña, F. Lapayese, (...) and the TJ-II Team, in preparation for Nucl. Fusion. | ||
[7] Experimental confirmation of efficient island divertor operation and successful neoclassical transport optimization in Wendelstein 7-X, T. S. Pedersen | [7] Commissioning of the Tracer-Encapsulated Solid Pellet (TESPEL) Injection system for Wendelstein 7-X and first results, R. Bussiahn, N. Tamura, K. J. McCarthy, B. Buttenschön, C. Brandt, A. Dinklage, A. Langenberg and the W7-X team, Plasma Phys. Control. Fusion, 66 (2024) 115020. https://doi.org/10.1088/1741-4326/ac2cf5. | ||
[7] Experimental confirmation of efficient island divertor operation and successful neoclassical transport optimization in Wendelstein 7-X, T. S. Pedersen, ..., I. García-Cortés, K. J. McCarthy, …, N. Panadero Alvarez, ..., N. Tamura, ..., Nucl Fusion 62, 042022 (2022). DOI: 10.1088/1741-4326/ac2cf5. | |||
[8] A comparison of the influence of plasmoid-drift mechanisms on plasma fuelling by cryogenic pellets in ITER and Wendelstein 7-X, N. Panadero, F. Koechl, A. R. Polevoi, J. Baldzuhn, C. D. Beidler, P. Lang, A. Loarte, A. Matsuyama, K. J. McCarthy, B. Pégourié, and Y. Turkin, Nucl. Fusion 63, 046022 (2023). https://doi.org/10.1088/1741-4326/acbc34 | [8] A comparison of the influence of plasmoid-drift mechanisms on plasma fuelling by cryogenic pellets in ITER and Wendelstein 7-X, N. Panadero, F. Koechl, A. R. Polevoi, J. Baldzuhn, C. D. Beidler, P. Lang, A. Loarte, A. Matsuyama, K. J. McCarthy, B. Pégourié, and Y. Turkin, Nucl. Fusion 63, 046022 (2023). https://doi.org/10.1088/1741-4326/acbc34 | ||
[9] Overview of the first Wendelstein 7-X long pulse campaign with fully water-cooled plasma facing components, O. Grulke, C. Albert, …, K. J. McCarthy, …, et al., Nucl Fusion 62 (2024) 112002. https://doi.org/10.1088/1741-4326/ad2f4d. | []9] Controlling performance bifurcations in stellarators - an inter-machine study of cryogenic-pellet fueling in helical devices, A. Dinklage, ..., I. García-Cortés, ..., K. McCarthy, D. Medina-Roque, ..., N. Tamura, ..., The Heliotron-J Team, The TJ-II Team, The LHD Experiment Team and the W7-X Team, sent to Nucl. Fusion, NF-107510. | ||
[9] Additional ECRH mitigates thermal quenches induced by tungsten TESPEL injection in LHD , H. Bouvain, A. Dinklage, N. Tamura, H. Igami, H. Kasahara, K. J. McCarthy, D. Medina Roque, I. García-Cortés and the LHD Experiment Group, enviado a Nucl. Fusion para su publicación, NF-106861. | |||
[10] Overview of the first Wendelstein 7-X long pulse campaign with fully water-cooled plasma facing components, O. Grulke, C. Albert, …, K. J. McCarthy, …, et al., Nucl Fusion 62 (2024) 112002. https://doi.org/10.1088/1741-4326/ad2f4d. | |||
[10] Overview of Large Helical Device experiments of basic plasma physics for solving crucial issues in reaching burning plasma conditions , K. Ida, ..., D. Medina-Roque, ..., I. García-Córtes, ... K. J. McCarthy, …, et al., Nucl. Fusion 64, 112009 (2024). https://doi.org/10.1088/1741-4326/ad3a7a | [10] Overview of Large Helical Device experiments of basic plasma physics for solving crucial issues in reaching burning plasma conditions , K. Ida, ..., D. Medina-Roque, ..., I. García-Córtes, ... K. J. McCarthy, …, et al., Nucl. Fusion 64, 112009 (2024). https://doi.org/10.1088/1741-4326/ad3a7a | ||
[11] | [11] Reduction of impurity confinement times in lithium-powder induced reduced-turbulence plasmas in the LHD, D. Medina-Roque, F. Nespoli, I. García-Cortés, K. J. McCarthy, N. Tamura, C. Suzuki, M. Goto, T. Kawate, Y. Kawamoto, M. Yoshinuma, K. Ida, K. Tanaka, T. Tokuzawa, H. Funaba, I. Yamada and the LHD team, en preparación para senviar a Nucl. Fusion Lett. | ||
<!-- DO NOT REMOVE THE FOLLOWING LINES --> | <!-- DO NOT REMOVE THE FOLLOWING LINES --> | ||