Let's connect the ends of our 1D equilibria. Doing so is what gives us inherently toroidal configurations. From the 1-dimensional picture:
j×B=jθBz−jzBθ=∇p=drdp
we move to an axisymmetric 2-dimensional torus, replacing our cylindrical coordinate system with a toroidal one
j×B=jθ×Bϕ+jϕ×Bθ=∇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.
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 and Bϕ 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
If we integrate Bθ over a poloidal surface, Stokes' theorem gives
∫Sp∇×Aϕ⋅dS=∮Aϕ⋅dl=∫SpBθ⋅dS=Ψp
If the equilibrium is axisymmetric, Aϕ must be uniform along dl, so
Aϕϕ^⋅∮dl=Aϕ2πR=Ψp→Aϕ=RΨpϕ^
where we absorb the factor of 2π into the poloidal flux Ψp. After some manipulation, we can relate Bθ to the poloidal flux
We notice that the only vector quantities here are ∇Ψ and ∇(RBϕ), so ∇(RBϕ) must be parallel to ∇Ψ and is a flux surface quantity. We can define our new flux surface quantity as
F(Φ)≡RBϕ=2πμ0Iθ=2πμ0∫Spjθ⋅dS
∇F=dΨdF∇Ψ=F′∇Ψ
Now each term in the toroidal force balance has a factor of ∇Ψ attached. Let's multiply through by R2 and factor out the gradient to arrive at the Grad-Shafranov equation:
R2μ0p′=−Δ⋆Ψ−FF′
where
Δ⋆≡R∂R∂R1∂R∂+∂z2∂2
To solve the Grad-Shafranov equation, you solve for Ψ(R,z), which determines p(Ψ) and F(Ψ), which directly gives you p(R,z) and F(R,z) and completely defines the equilibrium.
You can solve for the other terms as well. Since Bθ=R∇Ψ×ϕ^
jϕ=−μ0R1Δ⋆Ψϕ^
and since Bϕ=RFϕ^
jθ=−μ0R1∇(RBϕ)×ϕ^
For the G-S equation to be solvable, you need to specify the equilibrium by specifying p(Φ) and F(Φ). In practice, this is usually done by making experimental measurements to determine p and 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
Depending on the conditions we place on Ψ, f(Ψ) can be a nonlinear function.
Solutions to the Grad-Shafranov equation
In the limit that j∥B, then j×B=0=∇p→p′=0. These are called force-free states. In the G-S equation, the pressure term vanishes and we're left with
Δ⋆Ψ+FF′=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.
Another interesting limit is the case where FF′≫Δ⋆Ψ. Now we have
∇p≈jθ×Bϕ
which looks like a θ-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 ≈) but is just high enough to maintain radial force balance. This sort of configuration is called a high-β tokamak.
The other limit is FF′≪Δ⋆Ψ
∇p≈jϕ×Bθ
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 needs to be added to provide stability. The toroidal β is very small
βt≪1βp≈1
Stability Considerations
The same stability factors exist in 2D equilibria that we found for 1D equilibria:
Magnetic shear - the safety factor q(Ψ)=ΔθΔϕ for Δθ=2π. We can calculate q more easily by integrating along a flux surface in the poloidal plane:
Magnetic well: similarly we can get the magnetic well factor by integrating around a flux surface in the poloidal plane
⟨Q⟩=∮Bθdlp∮BθQdlp
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
As we move towards the magnetic axis, Bp→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.
The shift increases with plasma pressure. This effect is further enhanced if we have low poloidal fields, for example in the high-β 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.