,
,
be a set of right-handed cylindrical coordinates whose symmetry axis corresponds to that of the
plasma equilibrium.
On the other hand, let
,
,
be a set of right-handed flux coordinates such that
labels the equilibrium magnetic flux-surfaces, and
increases by
for every poloidal circuit of a given flux-surface. We can assume that
without loss of generality. (Note that
is a generalization of the poloidal angle introduced in Section 2.7 that does not assume that the flux-surfaces have circular cross-sections.) As before, we shall set
on the outboard midplane. Note that
. The Jacobean of our flux-coordinate
system is defined
Now, a general vector field,
, can be written
The axisymmetric equilibrium magnetic field of a tokamak can be expressed in the following manifestly divergence-free manner:
where
. It follows that
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(2.125) |
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(2.126) |
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(2.127) |
It is convenient to specialize to a coordinate system in which
It follows thatThe equilibrium electric field is written
Here,
, and
. Note that the previous equation automatically satisfies
.
Finally, we expect the plasma equilibrium to be characterized by number density, temperature, and pressure profiles that
are flux-surface functions [18]. In other words,
,
, and
. (See
Section 2.25.)