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Simulation of shattered pellet injections with plasmoid drifts in ASDEX Upgrade and ITER
Chalmers Univ Technol, Dept Phys, SE-41296 Gothenburg, Sweden.ORCID iD: 0000-0002-5444-5860
Chalmers Univ Technol, Dept Phys, SE-41296 Gothenburg, Sweden.ORCID iD: 0009-0007-2654-0354
Max Planck Inst Plasma Phys, Garching, Germany.ORCID iD: 0000-0001-6471-2304
Max Planck Inst Plasma Phys, Garching, Germany.ORCID iD: 0000-0003-0694-5446
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2025 (English)In: Plasma Physics and Controlled Fusion, ISSN 0741-3335, E-ISSN 1361-6587, Vol. 67, no 10, article id 105034Article in journal (Refereed) Published
Abstract [en]

Pellet injection is an important means to fuel and control discharges and mitigate disruptions in reactor-scale fusion devices. To accurately assess the efficiency of these applications, it is necessary to account for the drift of the ablated material towards the low-field side. In this study, we have implemented a semi-analytical model for ablation cloud drifts in the numerical disruption modelling tool DREAM. We show that this model is capable of reproducing the density evolution in shattered pellet injection (SPI) experiments in ASDEX Upgrade, for model parameters within the expected range. The model is then used to investigate the prospects for disruption mitigation by staggered SPIs in 15MA DT H-mode ITER scenarios. We find that the drifts may decrease the assimilation of pure deuterium SPIs by about an order of magnitude, which may be important to consider when designing the disruption mitigation scheme in ITER. The ITER scenarios studied here generally result in similar multi-MA runaway electron (RE) currents, regardless of the drift assumptions, but the effect of the drift is larger in situations with a fast and early thermal quench. The RE current may also be more strongly affected by the drift losses when accounting for RE losses caused by the vertical plasma motion.

Place, publisher, year, edition, pages
IOP Publishing , 2025. Vol. 67, no 10, article id 105034
Keywords [en]
disruption mitigation, shattered pellet injection, plasmoid drift, plasma simulation, ASDEX Upgrade, ITER
National Category
Fusion, Plasma and Space Physics
Identifiers
URN: urn:nbn:se:kth:diva-375526DOI: 10.1088/1361-6587/ae140fISI: 001607541200001Scopus ID: 2-s2.0-105034123515OAI: oai:DiVA.org:kth-375526DiVA, id: diva2:2032639
Note

QC 20260416

Available from: 2026-01-27 Created: 2026-01-27 Last updated: 2026-05-25Bibliographically approved
In thesis
1. Modelling runaway electron generation in tokamaks
Open this publication in new window or tab >>Modelling runaway electron generation in tokamaks
2026 (English)Licentiate thesis, comprehensive summary (Other academic)
Abstract [en]

Tokamak disruptions can convert a large fraction of the plasma current into a beam of relativistic runaway electrons. In a reactor-scale device such as ITER,a runaway electron beam could carry several megaamperes and, if left uncontrolled, could cause severe damage to plasma-facing components. Predicting whether a given disruption scenario leads to a dangerous runaway beam, and designing injection schemes that prevent it, requires models that capture the interplay between material injection, rapid plasma cooling, electric field evolution, and the various mechanisms by which runaway electrons are born,multiply, and are lost. This thesis addresses runaway electron physics from seed formation to disruption mitigation through numerical modelling.

A synthetic electron cyclotron emission (ECE) framework is developed and applied to vertical ECE measurements on the TCV tokamak, combining Fokker-Planck calculations of the electron distribution function with ray tracing and radiative transfer. The analysis demonstrates that vertical ECE can resolve the energy-dependent dynamics of suprathermal electrons in the 20–100 keV range, providing constraints on the nascent runaway seed that are difficult to obtain with conventional diagnostics.

The disruption simulation framework Dream is then extended with several physics models relevant to ITER: runaway electron losses from vertical plasma displacement, cross-field drift of pellet ablation material, stochasticity driven current-profile relaxation, and an updated Compton scattering source for the ITER first wall. These are applied to a systematic study of shattered pellet injection scenarios in ITER showing that avoiding a multi-megaampere runaway beam depends sensitively on the thermal quench timescale, the injected material composition, and the competition between runaway multiplication and scrape-off losses. Finally, a viable theoretical pathway that limits the runaway current to tolerable levels even in the presence of nuclear runaway sources is identified.

Place, publisher, year, edition, pages
Stockholm: KTH Royal Institute of Technology, 2026. p. ix, 71
Series
TRITA-EECS-AVL ; 2026:59
Keywords
Nuclear fusion, Tokamak, Runaway electrons, Disruptions
National Category
Fusion, Plasma and Space Physics
Research subject
Electrical Engineering
Identifiers
urn:nbn:se:kth:diva-382158 (URN)978-91-8106-637-1 (ISBN)
Presentation
2026-06-12, H1, Teknikringen 33, Stockholm, 10:00 (English)
Opponent
Supervisors
Note

QC 20260525

Available from: 2026-05-25 Created: 2026-05-22 Last updated: 2026-06-16Bibliographically approved

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Hoppe, MathiasVotta, Lorenzo

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