Runaway electron avalanche and macroscopic beam formation: Simulations of the DTT full power scenario

The transition of the Divertor Tokamak Test (DTT) facility from its initial commissioning phase (Day-0 scenario, plasma current Ip=2 MA) to the full power scenario, characterized by its highest nominal plasma current (Ip=5.5 MA), introduces a critical shift in the dynamics of runaway electrons (REs) generation. While previous predictive studies of the low-current scenario indicated a robust safety margin against RE beam formation, this work reveals that the exponential scaling of the RE avalanche gain with plasma current severely narrows the safe operational window in the full power scenario. Using the non-linear magnetohydrodynamic code JOREK, we perform comprehensive 2D simulations of the current quench (CQ) phase of several disruption scenarios, systematically scanning initial RE seed currents and injected impurity levels. The results demonstrate that in the full power scenario, the avalanche multiplication factor is sufficiently high (Gav≈1.3×105) to convert an initial 5.5 A seed current into macroscopic RE beams of ≈0.7 MA when large amounts of impurities are present. For even higher RE seeds, the RE current can peak at ≈3.2 MA, constituting up to ≈80% of the total plasma current during the CQ. These findings suggest that, unlike the Day-0 phase, the disruption mitigation strategy for the full power scenario involves a careful balance between thermal load mitigation and RE avoidance, necessitating a well-chosen quantity of injected impurities. This work provides the baseline needed for future estimations of RE loads on the plasma-facing components of DTT, which will be essential for designing and positioning mitigation components like sacrificial limiters.

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Publication Details

Journal
Physics of Plasmas
Published
2026-05-01
DOI
https://doi.org/10.1063/5.0320384
Primary Topic
Magnetic confinement fusion research
Type
article
Field-Weighted Citation Impact
0.00

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article

Runaway electron avalanche and macroscopic beam formation: Simulations of the DTT full power scenario

N. Schwarz, Enrico Emanuelli, F. Vannini, G. Ramogida et al.
Physics of Plasmas
Magnetic confinement fusion research
article

Runaway electron avalanche and macroscopic beam formation: Simulations of the DTT full power scenario

N. Schwarz, Enrico Emanuelli, F. Vannini, G. Ramogida, D. Bonfiglio, F. Subba, Team JOREK, Eric Nardon, Vinodh Bandaru, Matthias Hoelzl
article en

Abstract

The transition of the Divertor Tokamak Test (DTT) facility from its initial commissioning phase (Day-0 scenario, plasma current Ip=2 MA) to the full power scenario, characterized by its highest nominal plasma current (Ip=5.5 MA), introduces a critical shift in the dynamics of runaway electrons (REs) generation. While previous predictive studies of the low-current scenario indicated a robust safety margin against RE beam formation, this work reveals that the exponential scaling of the RE avalanche gain with plasma current severely narrows the safe operational window in the full power scenario. Using the non-linear magnetohydrodynamic code JOREK, we perform comprehensive 2D simulations of the current quench (CQ) phase of several disruption scenarios, systematically scanning initial RE seed currents and injected impurity levels. The results demonstrate that in the full power scenario, the avalanche multiplication factor is sufficiently high (Gav≈1.3×105) to convert an initial 5.5 A seed current into macroscopic RE beams of ≈0.7 MA when large amounts of impurities are present. For even higher RE seeds, the RE current can peak at ≈3.2 MA, constituting up to ≈80% of the total plasma current during the CQ. These findings suggest that, unlike the Day-0 phase, the disruption mitigation strategy for the full power scenario involves a careful balance between thermal load mitigation and RE avoidance, necessitating a well-chosen quantity of injected impurities. This work provides the baseline needed for future estimations of RE loads on the plasma-facing components of DTT, which will be essential for designing and positioning mitigation components like sacrificial limiters.

Physics of PlasmasVol. 33(5)
ITER (FR), National Agency for New Technologies, Energy and Sustainable Economic Development (IT), Indian Institute of Technology Guwahati (IN), Istituto Nazionale di Statistica (IT), Università degli Studi della Tuscia (IT), Politecnico di Torino (IT), Indian Institute of Information Technology Guwahati (IN), CEA Cadarache (FR), Max Planck Institute for Plasma Physics (DE), Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali di Frascati (IT), Consorzio per la Ricerca Sanitaria (IT)
EUROfusion
Openalex Percentile: Top 6%
Magnetic confinement fusion research
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