Evolution of SPI-induced disruptions in ASDEX Upgrade

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Authors: P. Heinrich, G. Papp, S. Jachmich, F J Artola, M. Bernert, P. de Marné, M. Dibon, R. Dux, T. Eberl, O. Ficker, Peter Halldestam, Joerg Hobirk
+14 more M. Hoelzl, Felix Klossek, Michael Lehnen, T. Lunt, Marc Maraschek, Ansh Patel, Tobias Peherstorfer, N. Schwarz, U. Sheikh, B. Sieglin, Jakub Svoboda, Weikang Tang, the ASDEX Upgrade Team, EUROfusion Tokamak Exploitation Team
Cited by: 1
References: 66

Abstract

Abstract 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 (FL), main fragment arrival (MFA), plasma movement event (PME), MARFE, thermal quench (TQ)/plasma current spike (IP-spike), current quench (CQ), and vertical displacement event (VDE) 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) → concave (well mitigated/radiation dominated). Depending on the injection, pre-TQ durations between 15 and 0.5 ms and early CQ durations ( Δ t CQ 100 → 80 ) between 13.3 and 8.2 ms had been achieved at AUG.

Fields of Study & Subjects

Magnetic confinement fusion research Fusion materials and technologies Nuclear reactor physics and engineering

Publication details

Journal / source
Nuclear Fusion
Publisher
IOP Publishing
Volume
66
Issue
10
Pages
106014–106014
Publication date
30 July 2026
Language
EN