In addition to the experimentally known external coil currents and
limiter position, the foregoing predictive FP analysis assumes
knowledge of
, the equilibrium pressure profile as a function of
normalized toroidal flux, which is known only when the equilibrium
problem itself has already been solved. Any scheme to find
from experimental measurements of electron and ion temperatures and
densities inevitably involves guessing the spatial to flux
transformation, clearly leading to some degree of approximation. We
prefer to avoid making any assumptions, however, and instead adopt an
interpretive approach to implicitly determine
. Here, the PCs
of
are iteratively varied in reconstructions to find the best
matching FP-derived equilibrium for the considered experimental data,
in this case Thomson scattering data of electron temperature and
density.
The Thomson scattering diagnostic on W7-AS [49]
currently measures electron temperature
and density
(and
thus the electron pressure
) on up to 20 channels at a single
time-point during a discharge. The measurement is performed along a
horizontal line-of-sight through the magnetic axis in a symmetry plane
(
=0) and is especially useful in that it yields a complete
profile covering the entire mid-plane diameter of the plasma. A
least-squares spline in
is fitted to
, which both smoothes
the data and allows continuous evaluation between channels. The
goodness of fit test is used to select the optimum degree of
smoothing and extract the maximum possible information from the data,
whereby the relative importance of points in the fit scales inversely
with their associated errors.
Our iterative procedure attempts to identify the spatial to flux
transformation implicit in
, assuming that
is constant
on flux surfaces. Starting from an initial guess, a number of PCs of
the equilibrium pressure profile
is varied to minimize a cost
function. This consists of the sum of squared differences between the
electron pressure evaluated on the high and low field radii on the
same flux surface (
and
respectively), normalized
to the global maximum of
, i.e. the quantity:
Extensive testing of interpretations based solely on the condition of
equation 4.1 often resulted in badly behaved interpreted
profiles (e.g. containing multiple turning points or even
negative values), despite the fact that the asymmetry was minimized.
This indicated the need for further regularization of the shape of
, the equilibrium pressure profile as a function of major
radius, which was mildly constrained to reflect that of
.
This is quite reasonable, since in most experimental scenarios we
expect the ion pressure profile not to introduce new features into the
pressure profile; thus the shape of
is largely given by
. The extra regularization produced profiles similar to those
of standard calculations without undue raising of the asymmetry and
also proved helpful in cases with poor input data.
A standard nonlinear least-squares minimization routine E04FCF from
the NAG library is used to perform the parameter variation. Note that
due to the above normalization, the interpreted fit depends only on
the topology of the
profile and not on its magnitude.
In fact, we are not exclusively limited to minimizing the asymmetry in
the
profile, but could also do this separately for the
or
profile. We discuss these possibilities later in
section 4.3.3 and proceed using
for now.
The figure of merit for the quality of the equilibrium simulation is
taken to be the residual asymmetry in
, i.e. the difference
between the
fit evaluated on inboard and outboard points of
equal flux along the Thomson line-of-sight. This quantity vanishes
for an equilibrium that is perfectly consistent with the Thomson data.
An additional consistency check on the interpreted equilibrium is that
the ion pressure,
, be everywhere positive
inside the plasma boundary.
The computed kinetic energy content can be optionally forced to match that derived from the diamagnetic flux measurement: this can stabilize the procedure when the input data is of poor quality, since it fixes the volume integral of the equilibrium pressure profile. The procedure generally lends itself well to adaptation, since matching additional profile or global data merely requires adding appropriate residuals to the cost function.
However, mismatches between the theoretical and physical magnetic configurations could falsify both the present scheme and the standard NEMEC calculations. This might arise due to differences between the actual geometry of the magnetic field coils and that used in the code. Taking this into account, however, would be most difficult and is outside the scope of this paper. Consistency checks with additional spatially resolved or global diagnostic data would reveal such discrepancies, if present. The impact of systematic errors such as these are investigated later.
Error bounds on the interpreted pressure profile can be calculated
from the
variance-covariance matrix V of the
fitted parameters
as follows: if
is any
parameter of the interpreted equilibrium and
is the gradient of
with respect to the
, then the
standard error in
,
, is given by:
| (4.2) |