Skip to content
Merged
87 changes: 50 additions & 37 deletions documentation/eng-models/tf-coil.md
Original file line number Diff line number Diff line change
Expand Up @@ -786,6 +786,8 @@ $$
Von-Mises yeild stress is also shown in the output for information.
</p>

-------------

## TF coil ripple


Expand All @@ -806,20 +808,40 @@ ripple impacts TF coil design in two ways:
conductor is larger than the value obtained using the axisymmetric
assumption. This is only true in `PROCESS` for the superconducting coil case. More info can be found [here](../eng-models/tf-coil-superconducting.md#on-coil-ripple-peak_tf_with_ripple).

### Plasma ripple
-------------

### Plasma ripple | `plasma_outboard_edge_toroidal_ripple()`

The maximum plasma ripple is defined in *PROCESS* with the user input `ripple_b_tf_plasma_edge_max`
The maximum toroidal plasma ripple at the outboard is defined in `PROCESS` with the user input `ripple_b_tf_plasma_edge_max`
as:

$$
\delta = \frac{B_\mathrm{max}-B_\mathrm{min}}{B_\mathrm{max}+B_\mathrm{min}}
$$

with \( B_\mathrm{min}\) and \( B_\mathrm{max}\) minimum field (between coils)
with $B_\mathrm{min}$ and $B_\mathrm{max}$ minimum field (between coils)
and the maximum field (on coil toroidal direction) respectively, measured at
the mid-plane plasma outer limit (separatrix). <em>PROCESS</em> plasma ripple
is estimated using a parametric Bio-Savart calculation fitted using the
<em>UKAEA</em> free boundary MHD code <em>FIESTA</em>. The shape (Princeton-D)
the mid-plane plasma outer limit (separatrix).

To prevent intolerable fast particles losses and plasma instabilities,
$\delta$ must be limited to a few percent, approximatively \( \delta \in
[0.5-1]\) . If intolerable, the plasma ripple can be reduced with many
different techniques, for example the TF coil shape, stabilisation coils can
be added, more coils can be used or the coil outboard radius can be increased.
All these design modifications affects the coil system design, for example
ripple shape optimisation should be done without generating too much bending
stress due to the un-adapted curvature radius, and adding coils must not prevent
remote maintenance. To keep the design procedure as simple as possible in
`PROCESS`, unacceptable ripple is reduced by simply moving the
TF coil leg to a larger radius. The outboard ripple is directly obtained reverting the ripple fit to provide
$R_\mathrm{outboard\ WP}^\mathrm{mid}$ as a function of the ripple.
The minimal $R_\mathrm{outboard\ WP}^\mathrm{mid}$ is technically obtained
by increasing the gap between the vacuum vessel and the coil (`dr_shld_vv_gap_outboard`).

#### D-shaped coils

`PROCESS` plasma ripple is estimated using a parametric Bio-Savart calculation fitted using the
UKAEA free boundary MHD code FIESTA. The shape (Princeton-D)
used for these MHD model is shown in the left section of Figure 11.


Expand All @@ -834,10 +856,10 @@ used for these MHD model is shown in the left section of Figure 11.
<br>
<figcaption><i>
<p style='text-align: justify;'>
Figure 11 : The left graph shows the filament shape used in the
<em>FIESTA</em> ripple calculations. The current loops are made straight
Figure 11 : The top graph shows the filament shape used in the
FIESTA ripple calculations. The current loops are made straight
section (red lines) connecting vertices (blue dots) following the coil
shape. The right plot shows the ripple calculated by <em>FIESTA</em> (lines with
shape. The bottom plot shows the ripple calculated by FIESTA (lines with
open circles) compared to the fit values (lines without circles) for
different number of coils (16, 18 and 20) and lateral winding pack to
TF size ratio (\(x = 0.737\) and \(x = 2.947\)) as a function of the
Expand All @@ -863,13 +885,12 @@ dimensions defined as:


$$
x = \frac{\Delta R_\mathrm{tWP}^\mathrm{out}}{R_\mathrm{maj}} N_\mathrm{TF}
x = \frac{\Delta x_\mathrm{WP,max}}{R_\mathrm{maj}} N_\mathrm{TF}
$$


with \(\Delta R_\mathrm{tWP}^\mathrm{out}\) the plasma side WP thickness
defined in the Figures 1 and 3, \(N_\mathrm{TF}\) the number of coils and
\(R_\mathrm{maj}\) the plasma centre radius. \(y\) is the plasma outer
with $\Delta x_\mathrm{WP,max}$ the maximum toroidal width of the WP on the plasma side, $N_\mathrm{TF}$ the number of coils and
$R_\mathrm{maj}$ the plasma centre radius. $y$ is the plasma outer
mid-plane separatrix to outboard TF leg mid-plane radius ratio:


Expand All @@ -878,41 +899,33 @@ $$
$$


with \(a_\mathrm{min}\) the plasma minor radius and \(R_\mathrm{outboard\ TF}
^\mathrm{mid}\) the TF winding pack outboard leg midplane radius at its
with $a_\mathrm{min}$ the plasma minor radius and $R_\mathrm{outboard\ TF}
^\mathrm{mid}$ the TF winding pack outboard leg midplane radius at its
centre. The scaling fitting range is provided by:


- **Number of coils:** \( N_\mathrm{TF} \in \{16, 18, 20\} \).
- **Number of coils:** $N_\mathrm{TF} \in \{16, 18, 20\}$

- **Winding pack size ratio:** $x \in [0.737-2.95]$

- **separatrix to TF ratio:** $y \in [0.7-0.8]$

#### Picture frame coils

For the picture frame coils the presence of a straight outboard leg means the ripple is just given by:

$$
\delta = \left(\frac{R_{\text{maj}}+a_{\text{min}}}{R_\mathrm{outboard\ TF}^\mathrm{mid}}\right)^{\frac{1}{N_{\text{TF}}}}
$$

- **Winding pack size ratio:** \( x \in [0.737-2.95] \)

- **separatrix to TF ratio:** \( y \in [0.7-0.8] \)




To prevent intolerable fast particles losses and plasma instabilities,
\(\delta\) must be limited to a few percent, approximatively \( \delta \in
[0.5-1]\) . If intolerable, the plasma ripple can be reduced with many
different techniques, for example the TF coil shape, stabilisation coils can
be added, more coils can be used or the coil outboard radius can be increased.
All these design modifications affects the coil system design, for example
ripple shape optimisation should be done without generating too much bending
stress due to the un-adapted curvature radius, and adding coils must not prevent
remote maintenance. To keep the design procedure as simple as possible in
<em>PROCESS</em>, unacceptable ripple is reduced by simply moving the
TF coil leg to a larger radius. The outboard ripple is directly obtained reverting the ripple fit to provide
\(R_\mathrm{outboard\ WP}^\mathrm{mid}\) as a function of the ripple.
The minimal \(R_\mathrm{outboard\ WP}^\mathrm{mid}\) is technically obtained
by increasing the gap between the vacuum vessel and the coil (dr_shld_vv_gap_outboard).


The currently implemented plasma ripple evaluation assumes a Princeton-D shape
and is therefore not valid anymore if very different shapes are considered,
with picture frame coils, for example, different models should be
considered/implemented in <em>PROCESS</em>.

------------

## TF coil parameter summary table

Expand Down
Loading
Loading