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

Disruption Avoidance in Tokamaks

Not scheduled
20m
EICC, Edinburgh

EICC, Edinburgh

150 Morrison St, Edinburgh EH3 8EE
Poster Presentation Plasma Control (MCF)

Description

The poloidal magnetic flux produced by the net plasma current changes by approximately 10% over the range of credible current profiles. The time derivative of the poloidal flux outside a surface of fixed toroidal flux $\psi_t$, is given by the loop voltage $V_\ell$, which implies the actual current profile is given by the spatial constancy of $V_\ell$. Using Boozer coordinates, the internal inductance $\ell_i$, and $q_{edge}/q_{axis}$ can be given using $I(\psi_t)/I_{plasma}$ and a surface-shape function $\sigma(\psi_t)$,which can be expanded in $\psi_t$. The ratio of the second derivative relative to the first of $\sigma$ is $\delta_t.$ A large $\ell_i$ is associated with tearing and disruptions. A large edge current density, given by $(dI/d\psi_t)_{edge}$, and a large triangularity $\delta_t$ are shown to reduce $\ell_i$ for a given $I(\psi_t)/I_{plasma}$. It is important to determine if there are any safe regions against disruptions in the space of $\ell_i$, $q_{edge}/q_{axis}$, edge current, and $\delta_t.$ The scatter diagram using $\ell_i$, $q_{edge}/q_{axis}$ for disruptions in JET-ILW of Figure 13 in Nucl. Fusion \textbf{60}, 066028 (2020) implies more quantities are needed to describe a disruption safe region.

Author

Allen Boozer (Columbia.edu)

Presentation materials

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