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1-Dimensional Equilibria

The θ \theta -pinch

In a θ \theta pinch, we have an applied axial field generated by a driven azimuthal current distribution. The way these usually work is that you begin with a plasma generated by some pre-ionization process and zero field. Then you crank up the current to drive an azimuthal current in the plasma (in the opposite direction as the external current).

j×B=pjθBz=dpdr \vec j \cross \vec B = \grad p \quad \rightarrow \quad j_\theta B_z = \dv{p}{r}

jθ=1μ0dBzdr j_\theta = - \frac{1}{\mu_0} \dv{B_z}{r}

dpdr=1μ0BzdBzdr=ddr(Bz22μ0) \dv{p}{r} = - \frac{1}{\mu_0} B_z \dv{B_z}{r} = - \dv{}{r} \left( \frac{B_z ^2}{2 \mu_0} \right)

p+Bz22μ0=constant=B022μ0 p + \frac{B_z ^2}{2 \mu_0} = \text{constant} = \frac{B_0 ^2}{2 \mu_0}

Figure 12.21

At equilibrium, the magnetic pressure balances the plasma pressure. If we say that the pressure is

p=p0er2/a2 p = p_0 e^{- r^2 / a^2}

with p0 p_0 the pressure on-axis, then we can solve for the axial field

Bz=B0(1B0er2/a2)1/2 B_z = B_0 (1 - B_0 e^{-r^2/a^2})^{1/2}

We can define the peak β \beta to be the ratio of the on-axis pressure to the maximum magnetic field

β0=p0B02/2μ0 \beta_0 = \frac{p_0}{B_0 ^2 / 2 \mu_0}

By definition, the peak β \beta will always be 1 \leq 1 . We can define β \langle \beta \rangle

β=pBa2/2μ0 \langle \beta \rangle = \frac{ \langle p \rangle }{B_a ^2 / 2 \mu_0}

where Ba B_a is a characteristic field value, typically taken to be at the plasma edge.

β=2μ0B02πa20a2πrpdr \langle \beta \rangle = \frac{2 \mu_0}{B_0 ^2 \pi a^2} \int _0 ^a 2 \pi r p \, \dd r

=2a20arpB02/2μ0dr=2a20a(1Bz2B02)rdr = \frac{2}{a^2} \int_0 ^a \frac{ rp}{B_0 ^2/2 \mu_0} \dd r = \frac{2}{a^2} \int_0 ^a \left( 1 - \frac{B_z ^2}{B_0 ^2} \right) r \dd r

In this form, we can see that because Bz B_z will everywhere be less than B0 B_0 , we can increase β \langle \beta \rangle by driving Bz B_z as low as possible. In this particular example, β/β0=63% \langle \beta \rangle / \beta_0 = 63\% .

Z-pinch

In the case of a Z-pinch, we only have an applied axial current.

j=jz(r)z^ \vec j = j_z (r) \vu z

For force balance

j×B=pjzBθ=dpdr \vec j \cross \vec B = \grad p \quad \rightarrow \quad - j_z B_\theta = \dv{p}{r}

jz=1μ01rddr(rBθ) j_z = \frac{1}{\mu_0} \frac{1}{r} \dv{}{r} ( r B_\theta)

dpdr=Bθμ0rddr(rBθ) - \dv{p}{r} = \frac{B_\theta}{\mu_0 r} \dv{}{r} ( r B_\theta)

If we find it convenient we can separate this into a magnetic pressure term

ddr(p+Bθ22μ0)=Bθ2μ0r - \dv{}{r} \left( p + \frac{B_\theta ^2}{2 \mu_0} \right) = \frac{B_\theta ^2}{\mu_0 r}

Bennett Profile

An example of an achievable distribution is the Bennett profile, which has a diffuse form

Bθ=μ0I2πrr2+a2 B_\theta = \frac{\mu_0 I}{2 \pi} \frac{r}{r^2 + a^2}

jz=Iπa2(r2+a2)2 j_z = \frac{I}{\pi} \frac{a^2}{(r^2 + a^2) ^2}

p=μ0I28π2a2(r2+a2)2 p = \frac{\mu_0 I^2}{8 \pi ^2} \frac{a^2}{(r^2 + a^2)^2}

Interestingly, jp j \propto p . For a uniform temperature, jn j \propto n . Since current density is the product of v \vec v and n n , this says that we have a uniform drift velocity and all particles are drifting with the same velocity at all points along the profile. If we consider what the equilibrium profile looks like for a Bennett profile:

Figure 12.22

So for r<a r < a we have magnetic tension and pressure which balance the plasma pressure. For ra r \geq a we have magnetic tension which balances both plasma pressure and magnetic pressure.

The Z-pinch β \langle \beta \rangle

βpBa2/2μ0=2μ0Ba2πa20a2πrpdr \langle \beta \rangle \equiv \frac{ \langle p \rangle}{B_a ^2 / 2 \mu_0} \\ = \frac{2 \mu_0}{B_a ^2 \pi a^2} \int_0 ^a 2 \pi r p \dd r

If we multiply the force balance by r2 r^2 and integrate

0ar2dpdrdr+1μ00arBθddr(rBθ)dr=00=[r2p]0a0apd(r2)+[(rBθ)22μ0]0a \int_0 ^a r^2 \dv{p}{r} \dd r + \frac{1}{\mu_0} \int_0 ^a r B_\theta \dv{}{r} (r B_\theta) \dd r = 0 \\ 0 = \left[ r^2 p \right] _0 ^a - \int_0 ^a p \dd (r^2) + \left[ \frac{(r B_\theta)^2}{2 \mu_0} \right] _0 ^a

If we have a discrete pinch such that p(a)=0 p(a) = 0 then the first term vanishes.

0a2rpdr=(aBa)22μ0 \int_0 ^a 2 r p \dd r = \frac{(a B_a)^2}{2 \mu_0}

If we substitute our definition of β \langle \beta \rangle , we find β=1 \langle \beta \rangle = 1 . For a diffuse pinch in which p(a)0 p(a) \neq 0 we end up with β1 \langle \beta \rangle \leq 1 and we have a wall-supported plasma. Ideal confinement (β=1 \langle \beta \rangle = 1 ) is a very nice property and is what makes the Z-pinch configuration so interesting.

Stability Considerations

Instability results if there exists a plasma displacement that leads to a lower energy state. There are several ways to provide stability in the context of MHD. The two most common are magnetic shear and magnetic well.

Magnetic Shear

In ideal MHD, magnetic field lines can not break or tear. Let's consider some flux surface containing field lines B3 \vec B_3 . Behind it, we have another flux surface containing field lines B2 B_2 which are not parallel to B3 \vec B_3 , and the same for B1 \vec B_1 .

Figure 12.23

Because the field lines are a different angles to each other, these flux surfaces can not interpenetrate. In other words, if the flux surface pressures are P1>P2>P3 P_1 > P_2 > P_3 , we can maintain the pressure gradient and prevent the flux surfaces from moving each other. What prevents the surfaces from achieving a lower energy state is the magnetic shear between flux surfaces.

Without shear, the surfaces can interpenetrate and exchange positions. In the case of a toroidal geometry, magnetic shear is defined by the rotational transform ι \iota , or by the safety factor

q=2πι q = \frac{2 \pi}{\iota}

Generally speaking, q q is generally referenced for tokamaks and ι \iota is referenced for stellarators. Another way of picturing the safety factor in a toroidal geometry is

qno. of windings long wayno. of windings short way=dψtdVdϕpdV=dϕtdϕp=nm=toroidal transitspoloidal transits q \equiv \frac{\text{no. of windings long way}}{\text{no. of windings short way}} \\ = \frac{ \dv{\psi_t}{V}}{\dv{\phi_p}{V}} = \dv{\phi_t}{\phi_p} \\ = \frac{n}{m} = \frac{\text{toroidal transits}}{\text{poloidal transits}}

In a cylindrical (1D) geometry it is just

q=longitudinal transitsazimuthal transits q = \frac{\text{longitudinal transits}}{\text{azimuthal transits}}

Let's calculate the safety factor for a toroidal geometry:

Figure 12.24

dϕpdV=Bθ2πRdr2πR02πrdr=Bθ2πrRR0 \dv{\phi_p}{V} = \frac{ B_\theta 2 \pi R \dd r}{2 \pi R_0 2 \pi r \dd r} \\ = \frac{ B_\theta}{2 \pi r} \frac{R}{R_0}

dϕtdV=Bϕ2πrdr2πR02πrdr=Bϕ2πR0 \dv{\phi_t}{V} = \frac{B_\phi 2 \pi r \dd r}{2 \pi R_0 2 \pi r \dd r} \\ = \frac{B_\phi}{2 \pi R_0}

q=rBϕRBθ q = \frac{r B_\phi}{R B_\theta}

In a cylindrical geometry the analysis is even simpler

q=2πrBzLBθ q = 2 \pi \frac{r B_z}{L B_\theta}

As a note, it would appear that q0 q \rightarrow 0 at the magnetic axis as r0 r \rightarrow 0 , but in general Bθ0 B_\theta \rightarrow 0 as well, and the safety factor is generally bounded at r0 r \rightarrow 0

q q is a flux surface quantity.

We care about magnetic shear. How does that relate to the safety factor? Magnetic shear is defined as

s2dq/qdV/V=2dln(q)dln(V) s \equiv 2 \frac{\dd q / q}{\dd V /V} = 2 \dv{\ln (q)}{\ln(V)}

Even a uniform Bz B_z or Bθ B_\theta produces a finite magnetic shear because of the way that r r and Bθ B_\theta change. The safety factor is often considered synonymous with magnetic shear, and often we don't even compute s s .

Shear is generally a stabilizing effect. Interchange between flux surfaces can be prevented/inhibited by shear, or by making it energetically unfavorable. Shear tends to stabilize current-driven instabilities.

Magnetic Well

As before, we can consider two adjacent flux surfaces B1,P1 B_1, P_1 and B2,P2 B_2, P_2 . If B2>B1 B_2 > B_1 and P2>P1 P_2 > P_1 , the interchange is energetically favorable. But if B2>B1 B_2 > B_1 and P2<P1 P_2 < P_1 then the interchange may be unfavorable without any magnetic shear.

Consider a plasma confined by an externally applied magnetic field generated by a coil I I

Figure 12.25

On the left side, the magnetic field gradient is in the same direction as the plasma pressure gradient, which is a destabilizing configuration. Flux surfaces are able to interchange easily, and the magnetic field is described as having bad curvature. On the right side, the gradients are in the same direction and the magnetic field has a good curvature.

We can define the "wellness" W W as

Wtotal pressure change relative to mag. pressurerelative volume change=dp+B2/2μ0/B2/2μ0dV/V W \equiv \frac{ \text{total pressure change relative to mag. pressure}}{\text{relative volume change}} \\ = \frac{\dd \langle p + B^2/2 \mu_0 \rangle / \langle B^2/2 \mu_0 \rangle}{\dd V / V}

where the angle brackets indicate a quantity integrated along a field line

Q0LQdlB0ldlB \langle Q \rangle \equiv \frac{\int_0 ^L \frac{ Q \dd l}{|B|}}{\int_0 ^l \frac{\dd l}{|B|}}

For a stabilizing effect, the wellness must be greater than 0. This means that the magnetic pressure must increase faster than the pressure decreases to prevent pressure-driven instabilities.

Since W W is evaluated along a field line, it is also a surface quantity.

Application to 1D Equilibria

θ \theta -pinch: Since Bθ=0 B_\theta = 0 , q q \rightarrow \infty , which really just means q q is not well defined for a θ \theta -pinch. If we consider some small δBθ \delta B_\theta , we get a very large q q . From a magnetic shear perspective, a θ \theta -pinch has very large values of shear and very good stability properties.

The wellness is

W=VB2ddV2μ0p+B2=πr2LBz212πrLddr(2μ0p+Bz2)=μ0rBz2ddr(p+Bz22μ0)=0 W = \frac{V}{\langle B^2 \rangle} \dv{}{V} \langle 2 \mu_0 p + B^2 \rangle \\ = \frac{\pi r^2 L}{B_z ^2} \frac{1}{2 \pi r L} \dv{}{r} (2 \mu_0 p + B_z ^2) \\ = \frac{\mu_0 r}{B_z ^2} \dv{}{r} \left( p + \frac{B_z ^2}{2 \mu_0} \right) = 0

so a θ \theta -pinch has neutral magnetic well.

Vacuum case:

W=μ0rBz2ddr(Bz22μ0)=0 W = \frac{\mu_0 r}{ B_z ^2} \dv{}{r} \left( \frac{ B_z ^2}{2 \mu_0} \right) = 0

So vacuum magnetic fields also have neutral wellness. This leads to a general result sometimes referred to as "a plasma cannot dig its own well." In other words, by introducing plasma to a magnetic configuration, it cannot make the configuration more stable than it was. Plasmas make stability more challenging, not less.

Z-pinch:

Since Bz=0 B_z = 0 , q=0 q = 0 and there is no magnetic shear. Even for a small value of δBz \delta B_z you still get a small q q . The magnetic well properties of a Z-pinch are

W=VB2ddV2μ0p+B2=μ0rBθ2ddr(p+Bθ22μ0)=μ0rBθ2(Bθ2μ0r)=1 W = \frac{V}{\langle B^2 \rangle} \dv{}{V} \langle 2 \mu_0 p + B^2 \rangle \\ = \frac{\mu_0 r}{B_\theta ^2} \dv{}{r} \left( p + \frac{B_\theta ^2}{2 \mu_0} \right) \\ = \frac{\mu_0 r}{B_\theta ^2} \left( - \frac{ B_\theta ^2}{ \mu_0 r} \right) = -1

Recall that W>0 W > 0 for stability, so the Z-pinch has negative magnetic well and provides no pressure stability.

In summary,

  • Both θ \theta - and Z-pinch have high β \beta
  • θ \theta -pinch is stable
  • Z-pinch is unstable
  • End losses in a θ \theta pinch enormous since kk k_\parallel \gg k_\perp

Screw Pinch

A natural extension is to combine a moderate toroidal field and a moderate poloidal field to produce a screw pinch configuration.

Figure 12.26

×B=μ0j \curl \vec B = \mu_0 \vec j

jθ=1μ0dBzdr \rightarrow j_\theta = - \frac{1}{\mu_0 } \dv{B_z}{r}

jz=1μ0rddr(rBθ) j_z = \frac{1}{\mu_0 r} \dv{}{r} (r B_\theta)

For static MHD equilibrium

j×B=p \vec j \cross \vec B = \grad p

ddr(p+Bθ2+Bz22μ0)=Bθ2μ0r \dv{}{r} \left( p + \frac{ B_\theta ^2 + B_z ^2}{2 \mu_0} \right) = - \frac{B_\theta ^2}{\mu_0 r}

We can define a toroidal β \beta where B0=Bz(a) B_0 = B_z (a)

βt=pB02/2μ0=2μ0B021πa20a2πrpdr \beta_t = \frac{\langle p \rangle }{B_0 ^2 / 2 \mu_0} \\ = \frac{2 \mu_0}{ B_0 ^2} \frac{1}{\pi a^2} \int _0 ^a 2 \pi r p \dd r

and in the poloidal direction with Bθ,a=Bθ(a)=μ0I2πa B_{\theta, a} = B_\theta (a) = \frac{\mu_0 I}{2 \pi a}

βp=pBθ,a2/2μ0=8π2a2μ0I02(1πa20a2πrpdr)=16π2μ0I020arpdr \beta_p = \frac{\langle p \rangle}{B_{\theta, a} ^2 / 2 \mu_0} \\ = \frac{8 \pi ^2 a^2}{ \mu_0 I_0 ^2} \left( \frac{1}{\pi a^2} \int _0 ^a 2 \pi r p \dd r \right) \\ = \frac{16 \pi ^2}{\mu_0 I_0 ^2} \int_0 ^a r p \dd r

To proceed we can multiply the force balance by r2 r^2 and integrate

0ar2prdr(1)+0ar(Bθ2+Bz22μ0)dr(2)+0ar2Bθ2μ0rdr(3)=0 \underbrace{\int_0 ^a r^2 \pdv{p}{r} \dd r}_{(1)} + \underbrace{\int _0 ^a \pdv{}{r} \left( \frac{ B_\theta ^2 + B_z ^2 }{2 \mu_0} \right) \dd r}_{(2)} + \underbrace{\int_0 ^a r^2 \frac{B_\theta ^2}{\mu_0 r} \dd r}_{(3)} = 0

(1)=0ar2dp=r2p0a0apd(r2)=0a2rpdr (1) = \int_0 ^a r^2 \dd p = \left. r^2 p \right|_0 ^a - \int_0 ^a p \dd (r^2) = - \int_0 ^a 2 r p \dd r

(2)=0ar2d(Bθ2+Bz22μ0)=r2(Bθ2+Bz22μ0)0a0ar(Bθ2+Bz2μ0)dr (2) = \int_0 ^a r^2 \dd \left( \frac{B_\theta ^2 + B_z ^2}{2 \mu_0 } \right) \\ = \left. r^2 \left( \frac{ B_\theta ^2 + B_z ^2}{2 \mu_0 } \right) \right|_0 ^a - \int_0 ^a r \left( \frac{ B_\theta ^2 + B_z ^2}{\mu_0} \right) \dd r

(3)=0arBθ2μ0dr (3) = \int_0 ^a r \frac{B_\theta ^2}{\mu_0} \dd r

Combining we have

0a2rpdr+a2Bθ,a22μ0+a2B022μ0B0=Bz(r=a)0arBz2μ0dr=00a2rpdr+μ0I028π2+0ar(Bθ2Bz2μ0)dr=0 - \int_0 ^a 2 r p \dd r + \frac{a^2 B_{\theta, a}^2}{2 \mu_0} + \overbrace{\frac{a^2 B_0 ^2}{2 \mu_0}}^{B_0 = B_z(r = a)} - \int_0 ^a r \frac{B_z ^2}{\mu_0} \dd r = 0 \\ - \int_0 ^a 2 r p \dd r + \frac{ \mu_0 I_0 ^2}{8 \pi ^2} + \int_0 ^a r \left( \frac{ B_\theta ^2 - B_z ^2}{\mu_0} \right) \dd r = 0

Dividing 0a2rpdr \int_0 ^a 2 r p \dd r gives

[16π2μ0I20arpdr]1+[4μ0B02a20arpdr]12a20a(1Bz2B02)rdr=1 \left[ \frac{16 \pi^2}{\mu_0 I^2} \int_0 ^a r p \dd r \right] ^{-1} + \left[\frac{4 \mu_0}{B_0 ^2 a^2} \int_0 ^a r p \dd r \right] ^{-1} \frac{2}{a^2} \int_0 ^a \left(1 - \frac{B_z ^2}{B_0 ^2} \right) r \dd r = 1

or

1βp+αtβt=1 \frac{1}{\beta_p} + \frac{\alpha_t}{\beta_t} = 1

where

αt=2a20a(1Bz2B02)rdr \alpha_t = \frac{2}{a^2} \int_0 ^a \left( 1 - \frac{B_z^2}{B_0 ^2} \right) r \dd r

is the diamagnetism.

βp=(1αtβt)1 \beta _p = \left( 1 - \frac{\alpha_t}{\beta_t} \right) ^{-1}

If we have a diamagnetic current, then α>0 \alpha > 0 . This maximizes confinement, since we have confinement in the azimuthal field, as well as the axial field. The limit where you have a skin current such that Bz=0 B_z = 0 inside the plasma results in the best confinement and αt=1 \alpha _t = 1 .

Looking at the safety factor,

q=2πrBzLBθ q = \frac{2 \pi r B_z}{L B_\theta}

If we look at the edge r=a r = a ,

qa=2πaB0LBθ,a q_a = \frac{2 \pi a B_0}{L B_{\theta, a}}

As it turns out, this value of the edge safety factor is critically important, and for stability we require that qa>1 q_a > 1 .

The magnetic shear of a screw pinch is

s=2VqdqdVV=πr2LdV=2πLrdr=2Vrdrs=rqdqdr s = 2 \frac{V}{q} \dv{q}{V} \\ V = \pi r^2 L \\ \dd V = 2 \pi L r \dd r = \frac{2 V}{r} \dd r \\ s = \frac{r}{q} \dv{q}{r}

The shear can be adjusted by changing the applied axial field.

The magnetic well is

W=VB2d(2μ0p+B2)dV=μ0rB2ddr(p+B22μ0)=μ0rB2(Bθ2μ0r)=Bθ2B2=Bθ2Bθ2+Bz2=(1+Bz2Bθ2)1 W = \frac{V}{B^2} \dv{(2 \mu_0 p + B^2)}{V} \\ = \frac{\mu_0 r}{B^2} \dv{}{r} \left( p + \frac{B^2}{2 \mu_0} \right) \\ = \frac{\mu_0 r}{B^2} \left( - \frac{B_\theta ^2}{\mu_0 r} \right) \\ = - \frac{B_\theta ^2}{B^2} \\ = - \frac{B_\theta ^2}{B_\theta ^2 + B_z ^2} \\ = - \left( 1 + \frac{B_z ^2}{B_\theta ^2} \right) ^{-1}

So the well is always less than zero, but adding Bz B_z improves the well.

By combining the properties of θ \theta -pinch and Z-pinch, we are able to sacrifice some β \beta to achieve better stability properties. Of course, we have not addressed the end losses in any way; to do that, we need to connect the ends.