29 June 2026 to 3 July 2026
EICC, Edinburgh
Europe/London timezone

Demonstration of shattered pellet injection schemes at ASDEX Upgrade for disruption mitigation in ITER

Not scheduled
20m
EICC, Edinburgh

EICC, Edinburgh

150 Morrison St, Edinburgh EH3 8EE
Oral Presentation Disruptions and Runaway Electrons (MCF)

Description

ITER will rely on shattered pellet injection (SPI) to mitigate the damaging consequences of plasma disruptions. Its disruption mitigation system (DMS) is designed to support various injection schemes and geometries to maximise material assimilation across the evolving plasma conditions during a disruption. The SPI system at ASDEX Upgrade has been adapted for the recent campaign to test a variety of injection schemes and to assess post thermal quench (TQ) injections which mimic the limited fragment plume-plasma intersection as expected for upper port injection in ITER. Experiments show that post-TQ injections suffer from weak fragment ablation due to the low plasma temperature, reducing densification and acceleration of the current quench (CQ) for minimising electromagnetic loads. In ohmic density limit disruptions, neon assimilation decreases by ~50% when fragments arrive 2 ms into the CQ compared with pre-TQ injection, leading to only partially mitigated CQs due to the comparatively low plasma resistivity.
Early deuterium injection aimed at avoiding the triggering of MHD activity and subsequent global reconnection event can dilute the plasma and reduce hot-tail runaway seeds. However, initial assimilation remains low (≈20%) and is further reduced by transport losses before TQ onset. Adding neon improves assimilation without shortening the pre-TQ phase to below the injection duration. Although smaller and faster fragments in general lead to a steeper density rise, their preferential edge deposition increases material losses by the time of the TQ. Intrinsic impurities, particularly tungsten in degraded H-mode plasmas, strongly influence mitigation performance. Longer pre-TQ phases and lower temperatures enhance fragment penetration and assimilation, and the presence of intrinsic impurities relaxes CQ mitigation requirements. Multiple Ne/D SPI has revealed that the assimilation deteriorates if the fragment plumes arrive more than 1 ms apart, which can be attributed to the already initiated plasma cooling. This imposes a strict requirement on the allowable fragment arrival jitter when material must be injected from several locations.
This contribution summarises results from recent ASDEX Upgrade SPI experiments and their implications for ITER’s disruption mitigation strategy.

Author

Stefan Jachmich (ITER Organization)

Co-authors

Ondrej Ficker (Institute of Plasma Physics of the CAS, Za Slovankou 1782/3, 182 00 Praha 8, Czech Republic) Paul Heinrich (Max-Plank-Institut für Plasmaphysik, D-85748, Garching, Germany) Ferenc Lengyel (HUN-REN Centre for Energy Research, Institiute for Atomic Energy Research, Budapest, Hungary) Pascal de Marne (Max-Plank-Institut für Plasmaphysik, D-85748, Garching, Germany) Andrew Moreau (Max-Plank-Institut für Plasmaphysik, D-85748, Garching, Germany) Gegerly Papp (Max-Planck-Institut für Plasmaphysik, Boltzmannstr. 2, 85748 Garching, Germany) Ansh Patel (Max-Plank-Institut für Plasmaphysik, D-85748, Garching, Germany) Umar Sheikh (Ecole Polytechnique Federale de Lausanne (EPFL), Swiss Plasma Center (SPC), CH-1015 Lausanne, Switzerland) Matthias Bernert (Max-Plank-Institut für Plasmaphysik, D-85748, Garching, Germany) Alexander Bock (Max-Plank-Institut für Plasmaphysik, D-85748, Garching, Germany) Joerg Hobirk (Max-Planck-Institut für Plasmaphysik, 85748 Garching, Germany) Bernd Kurzan (Max-Plank-Institut für Plasmaphysik, D-85748, Garching, Germany) Bernhard Sieglin (Max-Plank-Institut für Plasmaphysik, D-85748, Garching, Germany) ASDEX Upgrade Team EUROfusion Tokamak Exploitation team

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