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2D Equilibria

Let's connect the ends of our 1D equilibria. Doing so is what gives us inherently toroidal configurations. From the 1-dimensional picture:

Figure 12.27

j×B=jθBzjzBθ=p=dpdr \vec j \cross \vec B = j_\theta B_z - j_z B_\theta \\ = \grad p = \dv{p}{r}

we move to an axisymmetric 2-dimensional torus, replacing our cylindrical coordinate system with a toroidal one

Figure 12.28

j×B=jθ×Bϕ+jϕ×Bθ=p \vec j \cross \vec B = \vec j_\theta \cross \vec B_\phi + \vec j_\phi \cross \vec B_\theta = \grad p

Eventually, the toroidal force balance will lead to the Grad-Shafranov Equation, which tells us how we can solve for a general equilibrium that solves j×B=p \vec j \cross \vec B = \grad p .

Let's consider how we might achieve such a configuration. A toroidal magnetic field can be achieved by driving current through a poloidal coil. A more complicated problem is how to drive toroidal current. In general this is done by means of a transformer, where the plasma itself is the secondary circuit. Driving a time-varying current through the primary induces a toroidal current through the plasma. This is called a transformer drive for current.

Grad-Shafranov equation

Computing jθ j_\theta and Bϕ B_\phi can be computationally difficult in a toroidal geometry, so let's do some work towards simplifying our force balance expression. The toroidal magnetic vector potential is defined as

Bθ=×Aϕ \vec B_\theta = \curl \vec A_\phi

If we integrate Bθ B_\theta over a poloidal surface, Stokes' theorem gives

Sp×AϕdS=Aϕdl=SpBθdS=Ψp \int _{S_p} \curl \vec A_\phi \cdot \dd \vec S = \oint \vec A_\phi \cdot \dd \vec l \\ = \int _{S_p} B_\theta \cdot \dd \vec S = \Psi _p

If the equilibrium is axisymmetric, Aϕ A_\phi must be uniform along dl \dd l , so

Aϕϕ^dl=Aϕ2πR=ΨpAϕ=ΨpRϕ^ A_\phi \vu \phi \cdot \oint \dd \vec l = A_\phi 2 \pi R = \Psi _p \\ \rightarrow A_\phi = \frac{ \Psi_p}{R} \vu \phi

where we absorb the factor of 2π 2 \pi into the poloidal flux Ψp \Psi _p . After some manipulation, we can relate Bθ B_\theta to the poloidal flux

Bθ=×Aϕ=R^RΨz+z^RΨR \vec B_\theta = \curl \vec A_\phi = - \frac{ \vu R}{R} \pdv{\Psi}{z} + \frac{\vu z}{R} \pdv{\Psi}{R}

μ0jϕ×Bθ=(×Bθ)×Bθ=×Bθ×(Ψ×ϕ^R)=[R(1RΨR)+1RΨ2z2][ΨR(ϕ^ϕ^)ϕR(Ψϕ^)] \mu_0 j_\phi \cross B_\theta = (\curl \vec B_\theta) \cross \vec B_\theta \\ = \curl \vec B_\theta \cross \left( \grad \Psi \cross \frac{\vu \phi}{R} \right) \\ = - \left[ \pdv{}{R} \left( \frac{1}{R} \pdv{\Psi}{R} \right) + \frac{1}{R} \pdv{\Psi ^2}{z^2} \right] \cdot \left[\frac{ \grad \Psi}{R} ( \vu \phi \cdot \vu \phi) - \frac{ \phi}{R} \cancel{(\grad \Psi \cdot \vu \phi)} \right]

That gives the first component of p \grad p , now let's do the other one

μ0jθ×Bϕ=(×Bϕ)×Bϕ=[R^Bϕz+z^1RR(RBϕ)]×Bϕ=BϕR[R^R(RBϕ)+z^z(RBϕ)]=BϕR(RBϕ) \mu_0 \vec j_\theta \cross \vec B_\phi = ( \curl \vec B_\phi) \cross \vec B_\phi \\ = \left[ - \vu R \pdv{B_\phi}{z} + \vu z \frac{1}{R} \pdv{}{R} ( R B_\phi) \right] \cross \vec B_\phi \\ = - \frac{B_\phi}{R} \left[ \vu R \pdv{}{R} (R B_\phi) + \vu z \pdv{}{z} (R B_\phi) \right] \\ = - \frac{B_\phi}{R} \grad (R B_\phi)

Finally, since pressure is a flux surface quantity we can write

p=dpdΨΨ=pΨ \grad p = \dv{p}{\Psi} \grad \Psi = p' \grad \Psi

The toroidal force balance now looks like

μ0pΨ=1R(R1RΨR+1R2Ψz2)ΨBϕR(RBϕ) \mu_0 p' \grad \Psi = - \frac{1}{R} \left( \pdv{}{R} \frac{1}{R} \pdv{\Psi}{R} + \frac{1}{R} \pdv{^2 \Psi}{z^2} \right) \grad \Psi - \frac{B_\phi}{R} \grad(R B_\phi)

We notice that the only vector quantities here are Ψ \grad \Psi and (RBϕ) \grad (R B_\phi) , so (RBϕ) \grad (R B_\phi) must be parallel to Ψ \grad \Psi and is a flux surface quantity. We can define our new flux surface quantity as

F(Φ)RBϕ=μ0Iθ2π=μ02πSpjθdS F(\Phi) \equiv R B_\phi = \frac{\mu_0 I_\theta}{2 \pi} = \frac{\mu_0}{2 \pi} \int_{S_p} \vec j_\theta \cdot \dd \vec S

F=dFdΨΨ=FΨ \grad F = \dv{F}{\Psi} \grad \Psi = F' \grad \Psi

Now each term in the toroidal force balance has a factor of Ψ \grad \Psi attached. Let's multiply through by R2 R^2 and factor out the gradient to arrive at the Grad-Shafranov equation:

R2μ0p=ΔΨFF R^2 \mu_0 p' = - \Delta ^\star \Psi - F F'

where

ΔRR1RR+2z2 \Delta ^\star \equiv R \pdv{}{R} \frac{1}{R} \pdv{}{R} + \pdv{^2}{z^2}

To solve the Grad-Shafranov equation, you solve for Ψ(R,z) \Psi(R, z) , which determines p(Ψ) p(\Psi) and F(Ψ) F(\Psi) , which directly gives you p(R,z) p(R, z) and F(R,z) F(R, z) and completely defines the equilibrium.

You can solve for the other terms as well. Since Bθ=ΨR×ϕ^ \vec B_\theta = \frac{\grad \Psi}{R} \cross \vu \phi

jϕ=1μ0RΔΨϕ^ \vec j_\phi = - \frac{1}{\mu_0 R} \Delta ^\star \Psi \vu \phi

and since Bϕ=FRϕ^ \vec B_\phi = \frac{F}{R} \vu \phi

jθ=1μ0R(RBϕ)×ϕ^ \vec j_\theta = - \frac{1}{\mu_0 R} \grad (R B_\phi) \cross \vu \phi

For the G-S equation to be solvable, you need to specify the equilibrium by specifying p(Φ) p(\Phi) and F(Φ) F(\Phi) . In practice, this is usually done by making experimental measurements to determine p p and F F . A common code that does this is called EFIT, which takes the boundary conditions of the magnetic field and measurements of temperature, density to perform a least-squares fit to solve the G-S equation.

In general, the Grad-Shafranov equation leads to a matrix equation

AΨ+f(Ψ)=g \overline \vec A \vec \Psi + \vec f(\Psi) = \vec g

Depending on the conditions we place on Ψ \Psi , f(Ψ) \vec f(\Psi) can be a nonlinear function.

Solutions to the Grad-Shafranov equation

In the limit that jB \vec j \parallel \vec B , then j×B=0=pp=0 \vec j \cross \vec B = 0 = \grad p \rightarrow p' = 0 . These are called force-free states. In the G-S equation, the pressure term vanishes and we're left with

ΔΨ+FF=0 \Delta ^\star \Psi + F F' = 0

Spheromaks and RFPs are examples of nearly force-free states in which the current is nearly parallel to the magnetic field. Notice that in completely force-free states, β=0 \langle \beta \rangle = 0 .

Another interesting limit is the case where FFΔΨ F F' \gg \Delta ^\star \Psi . Now we have

pjθ×Bϕ \grad p \approx \vec j_\theta \cross \vec B_\phi

which looks like a θ \theta -pinch which has been connected at the ends. Remember from the previous section that we can not maintain radial force balance with purely toroidal fields, so the toroidal current is not zero (hence the \approx ) but is just high enough to maintain radial force balance. This sort of configuration is called a high-β \beta tokamak.

The other limit is FFΔΨ F F' \ll \Delta ^\star \Psi

pjϕ×Bθ \grad p \approx \vec j_\phi \cross \vec B_\theta

which looks like an end-connected z-pinch. This configuration is usually called an Ohmically heated Tokamak, and the majority of currently operating tokamaks operate this way. As we know, a purely poloidal field has very bad stability properties, so Bϕ \vec B_\phi needs to be added to provide stability. The toroidal β \beta is very small

βt1βp1 \beta _t \ll 1 \qquad \beta _p \approx 1

Stability Considerations

The same stability factors exist in 2D equilibria that we found for 1D equilibria:

Magnetic shear - the safety factor q(Ψ)=ΔϕΔθ q(\Psi) = \frac{\Delta \phi}{\Delta \theta} for Δθ=2π \Delta \theta = 2 \pi . We can calculate q q more easily by integrating along a flux surface in the poloidal plane:

q(Ψ)=12π0Δϕdϕ=12π02πdϕdθdθ=12π02πdθrBϕRBθalong flux surf.=F(Ψ)2πdlpR2Bθdlp=rdθ q(\Psi) = \frac{1}{2 \pi} \int_0 ^{\Delta \phi} \dd \phi \\ = \frac{1}{2 \pi} \int _0 ^{2 \pi} \dv{\phi}{\theta} \dd \theta \\ = \frac{1}{2 \pi} \int_0 ^{2 \pi} \dd \theta \left. \frac{r B_\phi}{R B_\theta} \right|_{\text{along flux surf.}} \\ = \frac{F(\Psi)}{2 \pi} \oint \frac{ \dd l_p}{R^2 B_\theta} \qquad \dd l_p = r \dd \theta

Magnetic well: similarly we can get the magnetic well factor by integrating around a flux surface in the poloidal plane

Q=QdlpBθdlpBθ \langle Q \rangle = \frac{\oint \frac{Q \dd l_p}{B_\theta}}{\oint \frac{ \dd l_p}{B_\theta}}

Shafranov Shift

Remember that when we had an equilibrium which had a toroidal current and a corresponding poloidal magnetic field, and a poloidal magnetic field, then radial force balance will tend to shift the configuration outwards away from the major axis and a conducting wall or external coil will be required to maintain the equilibrium. The radial force balance is really achieved by jϕ×Bp \vec j_\phi \cross B_p

As we move towards the magnetic axis, Bp0 B_p \rightarrow 0 by definition. With less poloidal field to balance the radial force imbalance, there is more radial expansion. This means that inner portion of the plasma (inner flux surfaces) must shift radially further to achieve radial force balance.

Figure 12.29

The shift increases with plasma pressure. This effect is further enhanced if we have low poloidal fields, for example in the high-β \beta tokamak configurations.

Low aspect ratios also enhance the effect. Recall that the radial force imbalance increases with smaller aspect ratio, leading to a larger shift.