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P: Fachverband Plasmaphysik
P 9: HEPP III
P 9.2: Vortrag
Dienstag, 27. Februar 2024, 14:25–14:50, ELP 6: HS 3
Shattered pellet injection experiments performed at ASDEX Upgrade — •Paul Heinrich1, G. Papp1, M. Bernert1, P. de Marné1, M. Dibon2, S. Jachmich2, M. Lehnen2, T. Peherstorfer3, N. Schwarz1, U. Sheikh4, B. Sieglin1, J. Svoboda5, and the ASDEX Upgrade team6 — 1Max-Planck-Institut für Plasmaphysik, Garching, Germany — 2ITER, St. Paul-lez-Durance, France — 3TU Wien, Wien, Austria — 4EPFL, Lausanne, Switzerland — 5IPP CAS, Prague, Czech Republic — 6See author list of U. Stroth et al. 2022 NF 62 042006
Future fusion devices like ITER, which are based on the tokamak concept, require a disruption mitigation system (DMS) to ensure machine protection. While the fusion reactions will naturally come to a hold within a fraction of a second in an unforeseen event causing a disruption, this can cause large forces and heat loads on the structure which might damage the device. In order to support the design of the ITER disruption mitigation system, a highly flexible shattered pellet injection (SPI) system was installed at the tokamak ASDEX Upgrade. Hereby, frozen pellets of deuterium, neon or a mixture thereof, are injected into the plasma to isotropically radiate the confined energy. Optimized mitigation is investigated by variation of the pellet parameters (e.g. size, velocity) or shatter geometry. The injection parameters are found to have a stronger impact on material assimilation, while the radiation characteristics are dominated by the pellet composition. A system overview as well as first analysis results for the experimental campaign -- with focus on the radiation characteristics -- are presented.
Keywords: Fusion research; ASDEX Upgrade; plasma disruption mitigation; shattered pellet injections (SPI); radiation analysis