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Direct Prediction of Nonlinear Tearing Mode Saturation Using a Variational Principle

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Direct Prediction of Nonlinear Tearing Mode Saturation Using a Variational Principle Direct prediction of nonlinear tearing mode saturation using a variational principle J. Loizu1, Y.-M. Huang2, S. R. Hudson2, A. Baillod1, A. Kumar3, and Z. Qu3 1 Ecole´ Polytechnique F´ed´erale de Lausanne, Swiss Plasma Center, CH-1015 Lausanne, Switzerland 2 Princeton Plasma Physics Laboratory, PO Box 451, Princeton NJ 08543, USA 3 Mathematical Sciences Institute, the Australian National University, Canberra ACT 2601, Australia∗ (Dated: June 8, 2020) It is shown that the variational principle of multi-region relaxed magnetohydrodynamics (MRxMHD) can be used to predict the stability and nonlinear saturation of tearing modes in strong guide field configurations without resolving the dynamics and without explicit dependence on the plasma resistivity. While the magnetic helicity is not a good invariant for tearing modes, we show that the saturated tearing mode can be obtained as an MRxMHD state of a priori unknown helicity by appropriately constraining the current profile. The predicted saturated island width in a tearing-unstable force-free slab equilibrium is shown to reproduce the theoretical scaling at small values of ∆0 and the scaling obtained from resistive MHD simulations at large ∆0. Magnetic reconnection is a ubiquitous phenomenon in very fact that a saturated state can be reached proves the the Universe that exhibits fast conversion of tremendous existence of a nearby, generally three-dimensional MHD amounts of magnetic energy into kinetic energy. It is ob- equilibrium. These observations raise the question: is served in solar eruptive flares [1, 2] and in the interaction there a variational principle that would allow direct cal- between the solar wind and the Earth's magnetic field [3]. culation of the saturated tearing modes, without resolv- Magnetic reconnection has an immediate practical im- ing the complex, resistivity-dependent dynamics? In this portance. In magnetic fusion devices, reconnection drives letter, we provide compelling analytical and numerical fast relaxation processes, such as sawtooth-like temper- evidence that this is possible. This opens the possibility ature crashes in tokamaks [4], reversed field pinches [5], of performing much simpler numerical calculations, but and stellarators [6], as well as other typically slower re- most importantly provides deep insight into the funda- laxation processes, such as neoclassical tearing modes in mental physical mechanisms that underpin tearing mode tokamaks [7], which degrade plasma confinement, slow formation and saturation, leading to new general under- plasma rotation, and can trigger plasma disruptions. standing of magnetic reconnection phenomena. In the presence of a strong guide field (e.g., the toroidal The theory of Taylor relaxation [15, 16], which does field in tokamaks), reconnection often occurs via the tear- not explicitly involve resistivity as a parameter, seems to ing mode instability. Within resistive magnetohydrody- indicate that it is indeed possible to find certain glob- namics (MHD), tearing modes appear when a certain ally relaxed, saturated states by minimizing the classical parameter, ∆0, which depends on the equilibrium pro- MHD potential energy [17], files, exceeds a critical value, ∆c, which is zero except for toroidal effects [8, 9]. A magnetic island then grows with Z p B2 W = + dV ; (1) a time scale between the ideal (Alfv´en)time scale τ and A Vp γ − 1 2µ0 the resistive (diffusion) time scale τη [10]. In tokamaks, nonlinear saturation of the tearing mode is typically ob- where Vp is the plasma volume, p is the plasma pressure, served, and the corresponding saturated island width, and γ is the adiabatic index. Taylor relaxed states satisfy wsat, is a critical parameter for machine operation [7]. a Beltrami equation, r × B = µB, with µ being a con- Numerical simulations of the growth and saturation of stant. They are obtained by taking p = 0 in Eq. (1) and resistive tearing modes in realistic parameter regimes are extremizing W for arbitrary variations in the magnetic expensive, primarily because of the very large Lundquist field subject to the only constraints of conserved total number, S = τη/τA 1, which imposes resolving very magnetic fluxes and conserved global magnetic helicity, disparate time scales [11]. For example, the ITER toka- 9 Z mak [12] can easily reach S ∼ 10 in the core. K = A · B dV ; (2) There are three crucial observations to make: (1) while Vp the linear growth rate of the tearing mode always de- pends on resistivity, e.g. γ ∼ η3=5 in a cylinder [8], where A is the magnetic vector potential. In an infinitely the instability parameter ∆0 does not, and the instability conducting, ideal plasma, K is an exact invariant in time, threshold is ∆c = 0 except for toroidal corrections [9]; (2) thereby reflecting the topological implications of Alfv´en's while the nonlinear growth rate of the island depends on theorem [18]. In a plasma with finite resistivity, K is dis- resistivity [13], the value of wsat does not [14]; and (3) the sipated in time, but often much slower than W . In fact, it can be argued that K is a good invariant during re- laxation processes that involve small-scale magnetic fluc- tuations or fast reconnection time scales [16, 19]. Ex- ∗Electronic address: [email protected] periments have indeed confirmed the quasi-invariance of 2 K during sawtooth oscillations in tokamaks [20] and re- We start by considering a force-free, doubly periodic, versed field pinches [21]. Tearing modes, however, usu- plasma current slab described by the following equilib- ally go through a slow nonlinear phase [13] and hence rium magnetic field [27]: B = Bz ez + ez × r , where z invariants other than K shall be sought to describe their is the guide-field direction and the flux function (x) = 2 saturation in terms of a more general variational princi- 0= cosh (x) determines the \poloidal" magnetic field, 0 ple. Moreover, Taylor's theory cannot describe saturated By(x) = (x), as well as the \toroidal" current density 00 states with non-trivial current profiles in strong guide jz(x) = (x) (Figure 1). The toroidal field, Bz, has a field configurations. In fact, since the current density \radial" dependence such as to satisfy the force-balance 2 2 2 in a Taylor state satisfies j = µB, its spatial variation is condition Bz (x) + By (x) = B0 , where B0 is the magni- quite limited in systems with a magnetic field whose mag- tude of the magneticp field on the resonant surface (x = 0). nitude, B, is almost uniform. In addition, Taylor states By setting 0 = 3 3=4 we have that the maximum do not support pressure gradients, which are ubiquitous poloidal field is By;max = 1, and hence we can ensure to any relevant magnetic fusion experiment. that a strong guide field is present by choosing B0 1. Over a decade ago, the theory of multi-region relaxed This current sheet can be characterized by a radialp equi- p 00 MHD (MRxMHD) was proposed by Dewar et al [22, 23] librium scale length a ≡ jjz(0)=jz (0)j = 1= 8 ≈ 0:35, in an attempt to generalize Taylor's relaxation theory and we choose a box size Lx = 2π a. The poloidal and allow one to explore energetically favourable recon- extent is what controls the stability of the system and nection events while maintaining some ability to con- thus we choose Ly = Lz = L as control parameter. strain the pressure and current profiles. MRxMHD starts with the same energy W , Eq. (1), but considers a con- 1.5 1 strained minimization with additional topological con- 1 straints. The plasma is partitioned into N nested vol- 0 umes separated by N −1 ideal interfaces that are assumed 0.5 y to remain magnetic surfaces during the minimization of z 0 j -1 the energy. In each volume, the plasma undergoes Taylor B -0.5 relaxation and the magnetic helicity, Eq. (2), is conserved -2 within the volume, along with the toroidal and poloidal -1 magnetic fluxes. While varying the plasma potential en- -1.5 -3 ergy, W , the ideal interfaces are allowed to undergo geo- -2 0 2 -2 0 2 x x metrical deformations. The resulting MRxMHD equilib- rium states satisfy FIG. 1: Equilibrium radial profiles for the poloidal magnetic 0 field, By(x) = (x), and the toroidal current density, jz(x) = 00 r × Bl = µlBl (3) (x). Red circles and red stairs describe the equilibrium 2 profiles obtained from the SPEC solution with N = 41, B = B 0 p + l = 0 (4) 10, L = 2π,Ψw = 0:1. 2µ0 where l = 1; :::N labels the volumes, µl is a constant char- While this equilibrium is ideally stable [28], it is unsta- acterizing the Taylor states that is related to the parallel ble to a tearing mode [29], which grows at the resonant surface x = 0. The instability parameter for the tearing current, and · l is the jump across the interface sep- arating volumes l and l + 1. mode is independent of resistivity and can be calculated A numerical solution to the MRxMHD equations can analytically [29], be found by using the Stepped-Pressure Equilibrium 2(5 − k2)(3 + k2) Code (SPEC), which can run in slab [24], cylindrical [25], ∆0 = p ; (5) or toroidal geometry [26]. Provided that the boundary k2 4 + k2 geometry and the number N of relaxation volumes are given, the solution is determined by a set of N quadru- with an instability occurring for ∆0 > 0. Here k is the plets, fp; Ψt; Ψp;Kgl=1:::N . Namely, in each volume one poloidal wavenumber whose smallestp possible value is k = must provide: the pressure p, the enclosed toroidal flux 2π=L. Hence ∆0 > 0 for 2π=L < 5. The condition for Ψ , the enclosed poloidal flux Ψ , and the enclosed mag- instability thus becomes a condition for the current sheet t p p netic helicity K.
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