Max Planck Institute Optimizes Fusion Disruption Mitigation with SPI

In the quest to make fusion energy a viable and reliable power source, scientists are continually refining techniques to manage and mitigate disruptions that can damage tokamaks, the doughnut-shaped devices that house fusion reactions. A recent study published in the journal *Nuclear Fusion*, titled “Modelling of shattered pellet injection experiments on the ASDEX Upgrade tokamak,” sheds light on how shattered pellet injection (SPI) systems can be optimized to enhance disruption mitigation. The research, led by Ansh Patel of the Max Planck Institute for Plasma Physics in Germany, offers insights that could significantly impact the future of fusion energy.

Disruptions in tokamaks are sudden, uncontrolled events that can release immense energy, potentially damaging the reactor. SPI is a technique used to mitigate these disruptions by injecting small, shattered fragments of material into the plasma. The effectiveness of SPI depends on various factors, including the size and speed of the fragments and the composition of the pellets. Patel’s research focuses on understanding how these parameters influence the assimilation of the injected material, which is crucial for developing more efficient disruption mitigation strategies.

Using the 1.5D INDEX code, Patel and his team conducted simulations to study the impact of different fragment sizes, speeds, and pellet compositions on SPI assimilation in the ASDEX Upgrade (AUG) tokamak. The findings reveal that smaller, faster fragments start to assimilate quicker, but larger, faster fragments ultimately assimilate more material by the time a global reconnection event (GRE) is expected to occur. This duality highlights the complex interplay between fragment size, speed, and assimilation efficiency.

“Understanding these trends is crucial for optimizing SPI systems,” Patel explains. “By tailoring the fragment size and speed, we can enhance the assimilation of the injected material, which is key to effective disruption mitigation.”

The study also examined the effect of varying the neon content in mixed deuterium-neon pellets. For neon content below a certain threshold, the assimilated neon varied significantly. However, for larger injected neon content, a self-regulating mechanism limited the variation in the amount of assimilated neon. This finding suggests that there is an optimal range for neon content that maximizes assimilation efficiency.

In addition to studying mixed pellets, the researchers used a back-averaging model to simulate the plasmoid drift during pure deuterium injections. The model, calibrated using experimental data, showed that larger and faster fragments led to higher assimilation, although the material assimilation was generally limited to the plasma edge due to the plasmoid drift.

The trends identified in the study align with previously reported experimental observations, providing a solid foundation for further research and development. “These insights are not just academic; they have real-world implications for the energy sector,” Patel notes. “By improving disruption mitigation techniques, we can make fusion energy more reliable and cost-effective, bringing us closer to a future powered by clean, sustainable fusion energy.”

The research published in *Nuclear Fusion*, which translates to *Nuclear Fusion* in English, offers a comprehensive analysis of SPI systems and their potential to enhance disruption mitigation in tokamaks. As the fusion energy sector continues to evolve, the findings from this study could shape the development of more advanced and efficient SPI technologies, ultimately contributing to the commercial viability of fusion power.

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