Shattered pellet injection (SPI), with research started in recent years, is the current concept for the ITER disruption mitigation system (DMS) to prevent disruption-related damage. Compared with impurity SPI, pure deuterium (D2) SPI could contribute to runaway electron (RE) avoidance in ITER via a strong dilution cooling before the thermal quench, as has been highlighted by predictive MHD modelling [1-3]. However, the drift of the ablation plasmoid towards the tokamak low field side (LFS) [4] and the existence of background impurities [2] could put this strategy (especially LFS D2 SPI injection) into question. These need to be clarified for the ITER DMS design, for which the validation of D2 SPI simulations against present experiments is crucial. In this work, we will present latest results on the modelling of D2 SPI into a JET H-mode plasma with JOREK [5], focusing on the (pre-)thermal quench dynamics and a detailed comparison with the experimental data. Our earlier simulations were in qualitative agreement with the radiation pattern of the JET bolometry system, whereas the total radiated power tended to be underestimated when assuming pure tungsten as the background impurity [6]. We will explore a more realistic mixture of background impurities (such as tungsten and neon) and investigate their role in the radiative cooling and thermal quench onset of the D2 SPI discharge. We will also discuss the evident drifts of the ablation plasmoids towards the LFS observed by the fast camera and study their role in the relatively small density rise measured by the central chord of the JET polarimeter [7]. These interpretative modelling could provide key information on the effectiveness of D2 SPI on RE avoidance for the ITER DMS design.

Interpretative 3D MHD modelling of deuterium shattered pellet injection into a JET H-mode plasma

Bonfiglio D;
2022

Abstract

Shattered pellet injection (SPI), with research started in recent years, is the current concept for the ITER disruption mitigation system (DMS) to prevent disruption-related damage. Compared with impurity SPI, pure deuterium (D2) SPI could contribute to runaway electron (RE) avoidance in ITER via a strong dilution cooling before the thermal quench, as has been highlighted by predictive MHD modelling [1-3]. However, the drift of the ablation plasmoid towards the tokamak low field side (LFS) [4] and the existence of background impurities [2] could put this strategy (especially LFS D2 SPI injection) into question. These need to be clarified for the ITER DMS design, for which the validation of D2 SPI simulations against present experiments is crucial. In this work, we will present latest results on the modelling of D2 SPI into a JET H-mode plasma with JOREK [5], focusing on the (pre-)thermal quench dynamics and a detailed comparison with the experimental data. Our earlier simulations were in qualitative agreement with the radiation pattern of the JET bolometry system, whereas the total radiated power tended to be underestimated when assuming pure tungsten as the background impurity [6]. We will explore a more realistic mixture of background impurities (such as tungsten and neon) and investigate their role in the radiative cooling and thermal quench onset of the D2 SPI discharge. We will also discuss the evident drifts of the ablation plasmoids towards the LFS observed by the fast camera and study their role in the relatively small density rise measured by the central chord of the JET polarimeter [7]. These interpretative modelling could provide key information on the effectiveness of D2 SPI on RE avoidance for the ITER DMS design.
2022
Istituto per la Scienza e Tecnologia dei Plasmi - ISTP
3D MHD
deuterium shattered pellet
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/412820
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