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Glossary

Magnetic Flux

The total magnetic field threading through a surface — the quantity that governs induction, confinement geometry, and every volt of transformer action in a tokamak

Reviewed Last reviewed: 9 Aug 2026 · Category: Glossary

Definition and Physical Meaning

Magnetic flux, denoted ΦB, quantifies the total amount of magnetic field passing through a given surface. Formally it is the surface integral of the magnetic field vector B over an area A: ΦB = ∫B·dA. The SI unit is the weber (Wb), equivalent to one volt-second. A uniform field of one tesla threading one square metre produces exactly one weber of flux.[1]

Flux is a scalar quantity, but its sign carries physical meaning: it indicates which side of the surface the net field emerges from. When the field is uniform and perpendicular to the surface the expression simplifies to ΦB = BA, but in most plasma devices the field varies spatially, making the full integral essential.

Role in Fusion Devices

In a tokamak the central solenoid stores magnetic flux and then swings it to drive the toroidal plasma current by transformer action. The total available flux swing — measured in volt-seconds — sets an upper bound on how long an inductively driven plasma discharge can last. Devices pursuing steady-state operation must supplement the solenoid with non-inductive current-drive methods precisely because the solenoid’s flux is finite.[2]

Poloidal flux surfaces, defined as contours of constant poloidal magnetic flux ψ, form the nested surfaces on which plasma pressure and current density are approximately constant. These flux surfaces are the backbone of magnetohydrodynamic (MHD) equilibrium theory and determine the shape, elongation, and triangularity of the plasma cross-section.[3]

One weber equals one volt sustained for one second. The flux swing of the central solenoid — typically tens of volt-seconds in large tokamaks — directly limits the duration of an inductively driven plasma pulse.

Measurement and Practical Considerations

Flux loops — simple wire loops placed at known locations around the vacuum vessel — measure the time derivative of magnetic flux via Faraday’s law. Integrating the induced voltage over time recovers the flux itself. Arrays of flux loops, combined with magnetic pickup coils, feed the real-time equilibrium reconstruction codes (such as EFIT) that operators rely on to control plasma shape and position during a discharge.[4]

Because magnetic flux is conserved in a perfectly conducting plasma, it also underpins the concept of “frozen-in” flux in ideal MHD: field lines move with the plasma as though they were embedded in it, a simplification that breaks down only where resistivity or reconnection becomes important.

Sources

  1. Griffiths, D.J. Introduction to Electrodynamics, 4th ed. Cambridge University Press, 2017.
  2. Wesson, J. Tokamaks, 4th ed. Oxford University Press, 2011.
  3. Freidberg, J.P. Ideal MHD. Cambridge University Press, 2014.
  4. Lao, L.L. et al. 'Reconstruction of current profile parameters and plasma shapes in tokamaks.' Nuclear Fusion 25.11 (1985): 1611.

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