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Evolution of SPI-induced disruptions in ASDEX Upgrade

Fuente: arXiv

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Détails bibliographiques
Auteurs principaux:	Heinrich, P., Papp, G., Jachmich, S., Artola, J., Bernert, M., de Marné, P., Dibon, M., Dux, R., Eberl, T., Ficker, O., Halldestam, P., Hobirk, J., Hoelzl, M., Klossek, F., Lehnen, M., Lunt, T., Maraschek, M., Patel, A., Peherstorfer, T., Schwarz, N., Sheikh, U., Sieglin, B., Svoboda, J., Tang, W., Team, the ASDEX Upgrade, Team, the EUROfusion Tokamak Exploitation
Format:	Preprint
Publié:	2026
Sujets:	Plasma Physics
Accès en ligne:	Acceder al recurso
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_version_	1866915920173072384
author	Heinrich, P. Papp, G. Jachmich, S. Artola, J. Bernert, M. de Marné, P. Dibon, M. Dux, R. Eberl, T. Ficker, O. Halldestam, P. Hobirk, J. Hoelzl, M. Klossek, F. Lehnen, M. Lunt, T. Maraschek, M. Patel, A. Peherstorfer, T. Schwarz, N. Sheikh, U. Sieglin, B. Svoboda, J. Tang, W. Team, the ASDEX Upgrade Team, the EUROfusion Tokamak Exploitation
author_facet	Heinrich, P. Papp, G. Jachmich, S. Artola, J. Bernert, M. de Marné, P. Dibon, M. Dux, R. Eberl, T. Ficker, O. Halldestam, P. Hobirk, J. Hoelzl, M. Klossek, F. Lehnen, M. Lunt, T. Maraschek, M. Patel, A. Peherstorfer, T. Schwarz, N. Sheikh, U. Sieglin, B. Svoboda, J. Tang, W. Team, the ASDEX Upgrade Team, the EUROfusion Tokamak Exploitation
contents	Disruptions are a major concern for future fusion reactors based on the tokamak principle. To ensure machine protection, the thermal loads and vessel forces that arise during disruptions have to be mitigated reliably. For the ITER disruption mitigation system (DMS), the shattered pellet injection (SPI) technology has been selected. It can provide a prompt delivery of the injection material into the plasma core, with the mitigation efficiency depending on fragment size and velocity. A highly flexible SPI system was built and installed at the tokamak ASDEX Upgrade (AUG) to aid the finalization process of the ITER DMS and provide crucial input for modeling. The SPI-induced disruptions in the 2022 AUG experiments follow a typical chain of events, which are discussed in this paper: The first light, main fragment arrival, plasma movement event, MARFE, thermal quench/plasma current spike, current quench, and vertical displacement event phase. Depending on the injection parameters, these phases may vary significantly or some might not be present at all. In this paper, we will focus on the characterization of these disruption phases and figures of merit for the mitigation efficiency, depending on the SPI configuration. With increasing amount of assimilated neon in the plasma - primarily influenced by the neon content in the pellet but also the shattering parameters - the disruptions exhibit different behaviors. This disruption evolution seems to be a continuous process, with the most prominent feature being the changing disruption time scales and plasma current time trace shape during the CQ from convex (poorly or unmitigated) $\rightarrow$ concave (well mitigated/radiation dominated). Depending on the injection, pre-TQ durations between 15 - 0.5 ms and early CQ durations ($Δ\textrm{t}_\textrm{CQ}^{100 \rightarrow 80}$) between 13.3 - 8.2 ms had been achieved at AUG.
format	Preprint
id	arxiv_https___arxiv_org_abs_2604_05488
institution	arXiv
publishDate	2026
record_format	arxiv
spellingShingle	Evolution of SPI-induced disruptions in ASDEX Upgrade Heinrich, P. Papp, G. Jachmich, S. Artola, J. Bernert, M. de Marné, P. Dibon, M. Dux, R. Eberl, T. Ficker, O. Halldestam, P. Hobirk, J. Hoelzl, M. Klossek, F. Lehnen, M. Lunt, T. Maraschek, M. Patel, A. Peherstorfer, T. Schwarz, N. Sheikh, U. Sieglin, B. Svoboda, J. Tang, W. Team, the ASDEX Upgrade Team, the EUROfusion Tokamak Exploitation Plasma Physics Disruptions are a major concern for future fusion reactors based on the tokamak principle. To ensure machine protection, the thermal loads and vessel forces that arise during disruptions have to be mitigated reliably. For the ITER disruption mitigation system (DMS), the shattered pellet injection (SPI) technology has been selected. It can provide a prompt delivery of the injection material into the plasma core, with the mitigation efficiency depending on fragment size and velocity. A highly flexible SPI system was built and installed at the tokamak ASDEX Upgrade (AUG) to aid the finalization process of the ITER DMS and provide crucial input for modeling. The SPI-induced disruptions in the 2022 AUG experiments follow a typical chain of events, which are discussed in this paper: The first light, main fragment arrival, plasma movement event, MARFE, thermal quench/plasma current spike, current quench, and vertical displacement event phase. Depending on the injection parameters, these phases may vary significantly or some might not be present at all. In this paper, we will focus on the characterization of these disruption phases and figures of merit for the mitigation efficiency, depending on the SPI configuration. With increasing amount of assimilated neon in the plasma - primarily influenced by the neon content in the pellet but also the shattering parameters - the disruptions exhibit different behaviors. This disruption evolution seems to be a continuous process, with the most prominent feature being the changing disruption time scales and plasma current time trace shape during the CQ from convex (poorly or unmitigated) $\rightarrow$ concave (well mitigated/radiation dominated). Depending on the injection, pre-TQ durations between 15 - 0.5 ms and early CQ durations ($Δ\textrm{t}_\textrm{CQ}^{100 \rightarrow 80}$) between 13.3 - 8.2 ms had been achieved at AUG.
title	Evolution of SPI-induced disruptions in ASDEX Upgrade
topic	Plasma Physics
url	https://arxiv.org/abs/2604.05488