PIXIE3D simulations of nonlinear saturation of MHD modes
POSTER
Abstract
The rapid loss of magnetic surfaces and the ensuing onset of
global field line stochasticity provide the primary path towards
enhanced transport losses that result in the fast thermal quench
during a tokamak disruption. The principal route to the loss of flux surfaces and field line stochasticity
is the excitation and nonlinear saturation of MHD modes. Moreover, the transport level is
dominated by parallel transport along open field lines which start at the core
but, due to the loss of magnetic surfaces, terminate at the first wall or the divertor plates.
Therefore, topological properties of those field lines are crucial in determining
the global transport.
Here, we use the nonlinear 3D MHD code, PIXIE3D, to perform
initial value simulations from tokamak equilibria of ITER and existing
machines that are unstable to a variety of large scale MHD modes, such
as (1,1) kink, double tearing, tearing, and external kink. We use a
simulation boundary that closely tracks the first wall in order to include the
plasma response from both inside and outside the magnetic
separatrix. By following the evolution of the dominant (n,m) modes, we track the
development of the MHD instabilities in the various discharges.
With the NEMATO field-line tracing code, we produce Poincare plots of
the disrupted magnetic topology and calculate quantities such as connection lengths
of open field lines and Lyapunov exponents of neighbouring field lines. By correlating
those measures of field-line stochasticity with kinetic simulations of thermal
collapse in wall bounded, slab plasmas we can gain insights into how 3D MHD sets off the thermal quench.
global field line stochasticity provide the primary path towards
enhanced transport losses that result in the fast thermal quench
during a tokamak disruption. The principal route to the loss of flux surfaces and field line stochasticity
is the excitation and nonlinear saturation of MHD modes. Moreover, the transport level is
dominated by parallel transport along open field lines which start at the core
but, due to the loss of magnetic surfaces, terminate at the first wall or the divertor plates.
Therefore, topological properties of those field lines are crucial in determining
the global transport.
Here, we use the nonlinear 3D MHD code, PIXIE3D, to perform
initial value simulations from tokamak equilibria of ITER and existing
machines that are unstable to a variety of large scale MHD modes, such
as (1,1) kink, double tearing, tearing, and external kink. We use a
simulation boundary that closely tracks the first wall in order to include the
plasma response from both inside and outside the magnetic
separatrix. By following the evolution of the dominant (n,m) modes, we track the
development of the MHD instabilities in the various discharges.
With the NEMATO field-line tracing code, we produce Poincare plots of
the disrupted magnetic topology and calculate quantities such as connection lengths
of open field lines and Lyapunov exponents of neighbouring field lines. By correlating
those measures of field-line stochasticity with kinetic simulations of thermal
collapse in wall bounded, slab plasmas we can gain insights into how 3D MHD sets off the thermal quench.
Presenters
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Ioannis Keramidas
Los Alamos National Laboratory
Authors
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Ioannis Keramidas
Los Alamos National Laboratory
-
Luis Chacon
Los Alamos Natl Lab
-
Xianzhu Tang
Los Alamos Natl Lab, Los Alamos National Laboratory