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Magnetohydrodynamics (MHD)

Magnetohydrodynamics (MHD) is the study of the dynamics of electrically conducting fluids in the presence of magnetic fields. In fusion research, MHD provides the framework for understanding plasma equilibrium, stability, and large-scale dynamics.

MHD treats the plasma as a single conducting fluid rather than tracking individual particles. This approximation is valid when:

  1. Length scales are much larger than the ion Larmor radius
  2. Time scales are much longer than the ion cyclotron period
  3. Collisions are frequent enough to maintain local thermal equilibrium

Under these conditions, the plasma can be described by fluid equations coupled with Maxwell’s equations.

Mass conservation:

ρt+(ρv)=0\frac{\partial \rho}{\partial t} + \nabla \cdot (\rho \mathbf{v}) = 0

where ρ\rho is mass density and v\mathbf{v} is fluid velocity.

The equation of motion including the magnetic force:

ρdvdt=p+j×B\rho \frac{d\mathbf{v}}{dt} = -\nabla p + \mathbf{j} \times \mathbf{B}

where pp is pressure, j\mathbf{j} is current density, and B\mathbf{B} is magnetic field. The term j×B\mathbf{j} \times \mathbf{B} is the Lorentz force per unit volume.

In ideal MHD (infinite conductivity):

E+v×B=0\mathbf{E} + \mathbf{v} \times \mathbf{B} = 0

In resistive MHD:

E+v×B=ηj\mathbf{E} + \mathbf{v} \times \mathbf{B} = \eta \mathbf{j}

where η\eta is the plasma resistivity.

For an adiabatic process:

ddt(pργ)=0\frac{d}{dt}\left(\frac{p}{\rho^\gamma}\right) = 0

where γ=5/3\gamma = 5/3 is the adiabatic index for a monatomic ideal gas.

The relevant Maxwell’s equations (in the MHD approximation where displacement current is neglected):

×B=μ0j\nabla \times \mathbf{B} = \mu_0 \mathbf{j} B=0\nabla \cdot \mathbf{B} = 0 Bt=×E\frac{\partial \mathbf{B}}{\partial t} = -\nabla \times \mathbf{E}

The j×B\mathbf{j} \times \mathbf{B} force can be decomposed into:

j×B=(B22μ0)+(B)Bμ0\mathbf{j} \times \mathbf{B} = -\nabla\left(\frac{B^2}{2\mu_0}\right) + \frac{(\mathbf{B} \cdot \nabla)\mathbf{B}}{\mu_0}

This reveals two physical effects:

The term B2/(2μ0)B^2/(2\mu_0) acts as a magnetic pressure. The plasma pushes back against increasing magnetic field strength.

The term (B)B/μ0(\mathbf{B} \cdot \nabla)\mathbf{B}/\mu_0 represents tension along the field lines, like a stretched rubber band. This restores bent field lines toward straightness.

The plasma beta β\beta is the ratio of plasma pressure to magnetic pressure:

β=pB2/(2μ0)=2μ0pB2\beta = \frac{p}{B^2/(2\mu_0)} = \frac{2\mu_0 p}{B^2}

This is a crucial parameter in fusion:

  • Low β\beta (1\ll 1): Magnetic pressure dominates; easier to confine but less efficient use of magnetic field
  • High β\beta (1\sim 1): More plasma per unit magnetic field; economically desirable but harder to stabilize

Typical values in tokamaks are β0.010.10\beta \sim 0.01-0.10 (1-10%).

In equilibrium, the plasma is stationary (v=0\mathbf{v} = 0), so:

p=j×B\nabla p = \mathbf{j} \times \mathbf{B}

This fundamental equation states that pressure gradients are balanced by magnetic forces.

For axisymmetric equilibria (like in tokamaks), the equilibrium condition reduces to the Grad-Shafranov equation:

R2(ψR2)=μ0R2dpdψFdFdψR^2 \nabla \cdot \left(\frac{\nabla \psi}{R^2}\right) = -\mu_0 R^2 \frac{dp}{d\psi} - F\frac{dF}{d\psi}

where ψ\psi is the poloidal flux function, RR is the major radius, p(ψ)p(\psi) is the pressure profile, and F(ψ)=RBϕF(\psi) = RB_\phi relates to the toroidal field.

Solving this equation determines the shape and properties of plasma equilibrium in a tokamak.

A plasma equilibrium is stable if small perturbations decay or oscillate with bounded amplitude. It is unstable if perturbations grow exponentially.

Stability can be analyzed using the energy principle. The change in potential energy δW\delta W for a displacement ξ\boldsymbol{\xi} determines stability:

δW=12ξF(ξ)d3r\delta W = -\frac{1}{2}\int \boldsymbol{\xi}^* \cdot \mathbf{F}(\boldsymbol{\xi}) \, d^3r

where F\mathbf{F} is the force operator. If δW>0\delta W > 0 for all ξ\boldsymbol{\xi}, the equilibrium is stable.

Several instabilities are important in fusion plasmas:

A helical distortion of the plasma column. The safety factor qq must satisfy:

q=rBϕRBθ>1q = \frac{r B_\phi}{R B_\theta} > 1

(Kruskal-Shafranov limit) to avoid the most dangerous external kink mode.

Axisymmetric pinching of the plasma column, stabilized by sufficient magnetic shear.

Pressure-driven instability that bulges on the outboard (low-field) side of the torus.

Resistive instability that can break and reconnect magnetic field lines, forming magnetic islands.

In ideal MHD (η=0\eta = 0), magnetic field lines are “frozen” into the plasma:

Bt=×(v×B)\frac{\partial \mathbf{B}}{\partial t} = \nabla \times (\mathbf{v} \times \mathbf{B})

The magnetic topology is preserved; field lines move with the plasma.

Finite resistivity allows magnetic field diffusion:

Bt=×(v×B)+ημ02B\frac{\partial \mathbf{B}}{\partial t} = \nabla \times (\mathbf{v} \times \mathbf{B}) + \frac{\eta}{\mu_0}\nabla^2\mathbf{B}

This enables magnetic reconnection, which can change field topology and release stored magnetic energy.

MHD equilibrium calculations guide the design of magnetic coils to achieve optimal plasma shapes for confinement and stability.

MHD stability considerations set operational limits on:

  • Maximum plasma pressure (beta limit)
  • Minimum safety factor (q-limit)
  • Maximum plasma current (disruption avoidance)

Violent MHD instabilities can terminate the plasma discharge in tokamaks, potentially damaging the device. Understanding and avoiding disruptions is critical for fusion reactor design.

Real-time MHD control systems use external coils to stabilize certain modes and extend operational boundaries.