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Modelling the nonlinear plasma response to externally applied three-dimensional fields with the Stepped Pressure Equilibrium Code

Published online by Cambridge University Press:  17 October 2022

A.M. Wright*
Affiliation:
Princeton Plasma Physics Laboratory, Princeton, NJ 08540, USA
P. Kim
Affiliation:
Institute for Research in Electronics and Applied Physics, University of Maryland, College Park, MD 20742, USA
N.M. Ferraro
Affiliation:
Princeton Plasma Physics Laboratory, Princeton, NJ 08540, USA
S.R. Hudson
Affiliation:
Princeton Plasma Physics Laboratory, Princeton, NJ 08540, USA
*
†Email address for correspondence: awright@pppl.gov
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Abstract

Small-amplitude, symmetry-breaking magnetic field perturbations, including resonant magnetic perturbations (RMPs) and error fields, can profoundly impact plasma properties in both tokamaks and stellarators. In this work, we perform the first comparison between the Stepped Pressure Equilibrium Code (SPEC) (a comparatively fast and efficient equilibrium code based on energy-minimisation principles) and M3D-C$^{1}$ (a high-fidelity albeit computationally expensive initial-value extended-magnetohydro- dynamic (MHD) code) to assess the conditions under which SPEC can be used to model the nonlinear, non-ideal plasma response to an externally applied $(m=2,n=1)$ RMP field in an experimentally relevant geometry. We find that SPEC is able to capture the plasma response in the weakly nonlinear regime – meaning perturbation amplitudes below the threshold for break up of the separatrix and onset of secondary magnetic island formation – when around half of the total toroidal flux is enclosed in the volume containing the $q=2$ resonant surface. The observed dependence of SPEC solutions on input parameters, including toroidal flux and the number of volumes into which the plasma is partitioned, indicates that additional exploration of the underlying Multi-Region Relaxed MHD physics model is needed to constrain the choice of parameters. Nonetheless, this work suggests promising applications of SPEC to optimisation and fusion plasma design.

Information

Type
Research Article
Copyright
Copyright © The Author(s), 2022. Published by Cambridge University Press
Figure 0

Figure 1. Equilibrium safety factor ($q$, solid) and pressure ($p$, dashed) profiles. Here, $q_0=1.3$, $q_a=4$ and $\beta =0.82\,\%$. Mode rational surfaces, located at $x_s=\{0.11,0.19,0.27,0.51\}$ and corresponding to $q(x_s)=\{4/3, 7/5,3/2,2\}$, respectively, are indicated by vertical dotted lines.

Figure 1

Figure 2. Non-ideal linear growth rates, $\gamma _{(m,n)}$, computed using M3D-C$^{1}$ for toroidal mode numbers $1\leq n\leq 5$. In each case, the poloidal mode number, $m$, corresponds to that of the fastest growing linear instability. The dependence of $\gamma _{(m,n)}$ on resistivity, $\eta$, indicates these are resistive modes. In particular, $\gamma _{(2,1)}\sim \eta ^{0.684}$, $\gamma _{(3,2)}\sim \eta ^{0.603}$, $\gamma _{(4,3)}\sim \eta ^{0.344}$, $\gamma _{(6,4)}\sim \eta ^{0.653}$ and $\gamma _{(7,5)}\sim \eta ^{0.538}$.

Figure 2

Figure 3. Non-ideal linear growth rates, $\gamma _{(m,n)}$, computed using M3D-C$^{1}$ for $\nu =10^{-7}$ (circles) and $\nu =10^{-6}$ (stars) and three different values of resistivity, $\eta$.

Figure 3

Figure 4. The original (green, dashed) and discretised (a) $q$-profiles and (b) pressure profiles for $\varPsi _{t,i=3}=0.3$ (blue), $0.4$ (purple) and $0.5$ (pink), where $\varPsi _{t,i=3}$ is the normalised toroidal flux in the volume containing the $q=2$ resonance (a, horizontal dashed line). The original profiles are given by (2.1) and (2.2), respectively. The discretised profiles are obtained from SPEC by running in ‘fixed iota’ mode and enforcing axisymmetry. See figure 5 for a summary of the procedure.

Figure 4

Figure 5. Summary of the workflow used to calculate a nonlinear, non-ideal response to externally applied, symmetry-breaking magnetic field perturbations using SPEC. The equilibrium profiles are used to calculate the toroidal and poloidal fluxes in each volume, $\varPsi _{t,i}$ and $\varPsi _{p,i}$. The parallel current density is discretised to obtain $\mu _i$. SPEC's ‘fixed iota’ mode is then used to obtain the volume-averaged helicity, $\mathcal {K}_i$, in each volume. In this first calculation, axisymmetry is enforced by setting the toroidal Fourier resolution parameter equal to zero. The SPEC boundary is then deformed to model the effect of an externally applied magnetic field perturbation. Finally, with $\mathcal {K}_i$, $\mu _i$, $\varPsi _{t,i}$ and $\varPsi _{p,i}$ as inputs in each volume, SPEC's fixed helicity mode is used to calculate a nonlinear, non-ideal response to the applied magnetic field perturbation.

Figure 5

Figure 6. Poincaré sections of the plasma response as computed by M3D-C$^{1}$ and evaluated at $t=5000\tau _A$ for $0.1\ \text {mT}\leq \delta B_{r}\leq 2\ \text {mT}$. Shown here as a function of normalised poloidal flux, $\psi _p$, and poloidal angle, $\theta$.

Figure 6

Figure 7. Poincaré sections of the plasma response as computed by M3D-C$^{1}$ and evaluated at $t=5000\tau _A$ for $\delta B_{r}=0.1,\ 0.7,\ 1,\ 1.5\ \text{mT}$. The pressure profiles shown in figure 8 correspond to cuts taken along $z=0$.

Figure 7

Figure 8. Pressure profiles at $t=5000\tau _A$ as computed by M3D-C$^{1}$ shown as a cut taken along $z=0$ for $\delta B_{r}= 0.1,\ 0.7,\ 1,\ 1.5\ \text{mT}$ (solid lines). Also shown is the equilibrium pressure profile (black line), given by (2.2). For comparison, the discretised pressure profiles used in the SPEC calculations are represented by filled curves for $\varPsi _{t,i=3}=0.3$ (red), $0.4$ (green) and $0.5$ (blue).

Figure 8

Figure 9. Saturated widths of $(m=2,n=1)$ magnetic islands due to externally applied $(2,1)$ RMP fields, as calculated by M3D-C$^{1}$ (pink), and SPEC for $\varPsi _{t,i=3}=0.3$ (blue), $\varPsi _{t,i=3}=0.4$ (orange) and $\varPsi _{t,i=3}=0.5$ (purple), where $\varPsi _{t,i=3}$ is the normalised toroidal flux enclosed in the volume containing the $q=2$ surface.

Figure 9

Figure 10. Poincaré sections of the plasma response as computed by SPEC (left, $\delta B_{r}=0.21 \text { mT}$ and $\varPsi _{t,i=3}=0.5$) and M3D-C$^{1}$ (right, $\delta B_{r}=0.2 \text { mT}$). The SPEC interfaces are represented by black curves with $N_{\rm vol}=5$ and the M3D-C$^{1}$ solution is evaluated at $t=5000\tau _A$.

Figure 10

Figure 11. Poincaré sections of the plasma response as computed by SPEC (left, $\delta B_{r}=0.683 \text { mT}$ and $\varPsi _{t,i=3}=0.5$) and (centre, $\delta B_{r}=0.736 \text { mT}$ and $\varPsi _{t,i=3}=0.5$) and M3D-C$^{1}$ (right, $\delta B_{r}=0.7 \text { mT}$). The SPEC interfaces are represented by black curves with $N_{\rm vol}=5$ and the M3D-C$^{1}$ solution is evaluated at $t=5000\tau _A$.