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Rename tfcth variable to dr_tf_coil_inboard and update all references…
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chris-ashe committed Nov 12, 2024
1 parent f7e9c51 commit 657ffa9
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6 changes: 3 additions & 3 deletions documentation/proc-pages/eng-models/machine-build.md
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Expand Up @@ -25,7 +25,7 @@ depending on the switches used.
Central solenoid 0.500 2.624 (ohcth) IP, ITV
CS precompression 0.065 2.689 (precomp)
Gap 0.050 2.739 (gapoh) IP, ITV
TF coil inboard leg 1.400 4.139 (tfcth) IP
TF coil inboard leg 1.400 4.139 (dr_tf_coil_inboard) IP
Gap 0.050 4.189 (tftsgap) IP
Thermal shield, inboard 0.050 4.239 (thshield_ib) IP
Gap 0.020 4.259 (gapds) IP
Expand Down Expand Up @@ -63,7 +63,7 @@ case the machine is not symmetric about the midplane.
Single null case
Thickness (m) Height (m)
TF coil 1.576 9.862 (tfcth)
TF coil 1.576 9.862 (dr_tf_coil_inboard)
Gap 0.050 8.286 (tftsgap)
Thermal shield 0.050 8.236 (thshield)
Gap 0.050 8.186 (vgap_vv_thermalshield)
Expand All @@ -81,7 +81,7 @@ case the machine is not symmetric about the midplane.
Gap 0.050 -9.702 (vgap_vv_thermalshield)
Thermal shield 0.050 -9.752 (thshield)
Gap 0.050 -9.802 (tftsgap)
TF coil 1.576 -11.379 (tfcth)
TF coil 1.576 -11.379 (dr_tf_coil_inboard)
```

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4 changes: 2 additions & 2 deletions documentation/proc-pages/eng-models/pf-coil.md
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Expand Up @@ -29,11 +29,11 @@ into account snull and other recent changes e.g. rclsnorm)

`ipfloc(j)` = 1: PF coils are placed above the central solenoid (one group only);
*R* = `rohc` + `rpf1`<br>
*Z* = $\pm$(`hmax` * `ohhghf` + 0.1 + 0.5 * (`hmax` * (1 - `ohhghf`) + `tfcth` + 0.1))
*Z* = $\pm$(`hmax` * `ohhghf` + 0.1 + 0.5 * (`hmax` * (1 - `ohhghf`) + `dr_tf_coil_inboard` + 0.1))

`ipfloc(j)` = 2: PF coils are placed above the TF coils (one group only);<br>
*R* = `rmajor` + `rpf2`<br>
*Z* = $\pm$(`hmax` * `tfcth` + 0.86)
*Z* = $\pm$(`hmax` * `dr_tf_coil_inboard` + 0.86)

`ipfloc(j)` = 3: PF coils are placed radially outside the TF coils (any number of groups);<br>
*R* = `rtot` + `dr_tf_coil_outboard`/2 + `routr`<br>
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16 changes: 8 additions & 8 deletions documentation/proc-pages/eng-models/tf-coil.md
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Expand Up @@ -58,7 +58,7 @@ The TF coils are assumed to be supporting each other against the net centering f
#### TF coil inboard radial size

<p style='text-align: justify;'>
Following the geometry and its parametrization presented in <em>Figure 1</em>, the TF total thickness <em>tfcth</em> \( \left( \Delta R_\mathrm{TF} \right) \) is related with the inner and outer case radial thicknesses (<em>thkcas</em>, \( \Delta R_\mathrm{case}^\mathrm{in} \) and <em>casthi</em>, \( \Delta R_\mathrm{case}^\mathrm{out} \) respectively) and the WP radial thickness <em>dr_tf_wp</em> \(\Delta R_\mathrm{WP}\) by the following equation :
Following the geometry and its parametrization presented in <em>Figure 1</em>, the TF total thickness <em>dr_tf_coil_inboard</em> \( \left( \Delta R_\mathrm{TF} \right) \) is related with the inner and outer case radial thicknesses (<em>thkcas</em>, \( \Delta R_\mathrm{case}^\mathrm{in} \) and <em>casthi</em>, \( \Delta R_\mathrm{case}^\mathrm{out} \) respectively) and the WP radial thickness <em>dr_tf_wp</em> \(\Delta R_\mathrm{WP}\) by the following equation :
</p>

$$
Expand All @@ -74,13 +74,13 @@ $$
$$

<p style='text-align: justify;'>
The TF coil radial thickness (<em>tfcth</em>) can parametrized in two ways in <em>PROCESS</em>:
The TF coil radial thickness (<em>dr_tf_coil_inboard</em>) can parametrized in two ways in <em>PROCESS</em>:
</p>
- <p style='text-align: justify;'>
**Direct parametrization**: the TF radial inboard thickness width is set as an input variable : `tfcth` (iteration variable 57). The WP radial thickness (`dr_tf_wp`) is calculated from `tfcth` and the two case radial thicknesses. This parametrization is used by default.
**Direct parametrization**: the TF radial inboard thickness width is set as an input variable : `dr_tf_coil_inboard` (iteration variable 57). The WP radial thickness (`dr_tf_wp`) is calculated from `dr_tf_coil_inboard` and the two case radial thicknesses. This parametrization is used by default.
</p>
- <p style='text-align: justify;'>
**WP thickness parametrization**: the TF inboard radial thickness is calculated from the the case and the WP radial thickness. This option is selected by using the WP thickness (`dr_tf_wp`, iteration variable 140) as an iteration variable. Doing so, any `tfcth` values will be overwritten and for this reason `dr_tf_wp` and `tfcth` cannot be used as iteration variables simultaneously. Although not set by default for backward compatibility, this parametrization provides a more stable optimization procedure (negative WP area layer cannot be obtained by construction) and is hence encouraged.
**WP thickness parametrization**: the TF inboard radial thickness is calculated from the the case and the WP radial thickness. This option is selected by using the WP thickness (`dr_tf_wp`, iteration variable 140) as an iteration variable. Doing so, any `dr_tf_coil_inboard` values will be overwritten and for this reason `dr_tf_wp` and `dr_tf_coil_inboard` cannot be used as iteration variables simultaneously. Although not set by default for backward compatibility, this parametrization provides a more stable optimization procedure (negative WP area layer cannot be obtained by construction) and is hence encouraged.
</p>

#### Case geometry
Expand All @@ -95,7 +95,7 @@ $$
**Sidewall casing:** this section corresponds to the lateral side of the case, separating the WP with the other vaulted coils. As in the WP geometry is generally squared, the sidewall case thickness may vary with the machine radius. For this reason, the user sets its dimensions though its minimal thickness `casths`. The user can either directly specify `casths` or define it as a fraction of the total coil thickness at the inner radius of the WP (`r_wp_inner`) with the `casths_fraction` input. If `casths_fraction` is set in the input file, the `casths` value will be overwritten.
</p>
- <p style='text-align: justify;'>
**Plasma side casing:** this section corresponds to the case section separating the WP with the plasma. As the geometry of this section is rounded, its thickness is set by its minimal value `casthi` (user input). This parameter can also be defined as a fraction of the total TF coil thickness `tfcth` using `casthi_fraction`. If the `casthi_fraction` parametrization is used, the `casthi` value will be overwritten.
**Plasma side casing:** this section corresponds to the case section separating the WP with the plasma. As the geometry of this section is rounded, its thickness is set by its minimal value `casthi` (user input). This parameter can also be defined as a fraction of the total TF coil thickness `dr_tf_coil_inboard` using `casthi_fraction`. If the `casthi_fraction` parametrization is used, the `casthi` value will be overwritten.
</p>

Two different plasma side casing shapes can be selected using the `i_tf_case_geom` integer switch:
Expand Down Expand Up @@ -1256,14 +1256,14 @@ Another subroutine, `tfspcall` is called outside `stfcoil` to estimate to check
| Parameter | description | Iteration variable | Default | Unit |
| - | - | - | - | - |
| `tf_in_cs` | TF coil inboard leg radial placement switch. <br> - 0 : Outside of central solenoid <br> - 1 : Inside of central solenoid | - | 0 | - |
| `tfcth` | TF coil maximum radial size <br> calculated if `dr_tf_wp` is used as iteration variable | ixc = 13 | No default | m |
| `dr_tf_coil_inboard` | TF coil maximum radial size <br> calculated if `dr_tf_wp` is used as iteration variable | ixc = 13 | No default | m |
| `tfootfi` | Outboard/inboard TF coil thickness ratio | - | 1 | - |
| `dr_tf_wp` | Winding pack radial thickness <br> calculated if `tfcth` is used as iteration variable. Include the ground insulation and the insertion gap. | ixc = 140 | No default | m |
| `dr_tf_wp` | Winding pack radial thickness <br> calculated if `dr_tf_coil_inboard` is used as iteration variable. Include the ground insulation and the insertion gap. | ixc = 140 | No default | m |
| `thkcas` | Nose/inner case radial thickness | ixc = 57 | 0.3 | m |
| `casths` | Minimal sidewall casing thickness | - | - | m |
| `casths_fraction` | Minimal sidewall casing thickness as a fraction of the TF coil toroidal thickness. Overwites the `casths` input value | - | 0.03 | - |
| `casthi` | Minimal plasma side casing thickness | - | - | m |
| `casthi_fraction` | Minimal plasma side casing thickness as a fraction of the TF thickness (`tfcth`). Overwites the `casthi` input value | - | 0.05 | - |
| `casthi_fraction` | Minimal plasma side casing thickness as a fraction of the TF thickness (`dr_tf_coil_inboard`). Overwites the `casthi` input value | - | 0.05 | - |
| `i_tf_case_geom` | Plasma side casing geometry option:<br> - 0 : rounder front casing (ITER) <br> - 1 : Straight casing | - | 0 | - |
| `i_tf_wp_geom` | Winding pack geometry option:<br> - 0 : rectangular <br> - 1 : double rectangle <br> - 2 : trapezoidal | - | Integer turn : 0 <br> otherwise : 1 | - |
| `tinstf` | WP ground insulation thickness | - | 0.018 | m |
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2 changes: 1 addition & 1 deletion documentation/proc-pages/fusion-devices/stellarator.md
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Expand Up @@ -209,7 +209,7 @@ The fully three-dimensional shape of the coils is assumed to be fixed, but the s

The stellarator coils are assumed to be superconducting - no resistive coil calculations are performed. The critical field at the superconductor is calculated using circular approximations for the coils in the inductance and field calculations, and the limit is enforced automatically. All superconductor materials that are available for tokamaks are also available for stellarators.

The winding pack cross-section is rectangular for the stellarator coils, rather than the two-step cross-section assumed for tokamaks. The coil thicknesses and most of the dimensions of the materials within the coil cross-section are outputs from the model, instead of being inputs as is the case for tokamaks; see the variable descriptor file for details. In addition, certain iteration variables (`tfcth`, no. 13; `thkcas`, no. 57; `cpttf`, no. 60 and `tftort`, no. 77) should not be turned on in the input file as they are calculated self-consistently (`thkcas` is required as input); the code will stop with an error message of this is attempted.
The winding pack cross-section is rectangular for the stellarator coils, rather than the two-step cross-section assumed for tokamaks. The coil thicknesses and most of the dimensions of the materials within the coil cross-section are outputs from the model, instead of being inputs as is the case for tokamaks; see the variable descriptor file for details. In addition, certain iteration variables (`dr_tf_coil_inboard`, no. 13; `thkcas`, no. 57; `cpttf`, no. 60 and `tftort`, no. 77) should not be turned on in the input file as they are calculated self-consistently (`thkcas` is required as input); the code will stop with an error message of this is attempted.
The conduit insulation thickness (`thicndut`), as well as the steel thickness around each conductor (`thwcndut`) should be given as input parameters together with the dimension of the conductor area (`t_turn_tf`).


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4 changes: 2 additions & 2 deletions examples/data/mfile_to_csv_vars.json
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Expand Up @@ -11,7 +11,7 @@
"fcohbop",
"alstroh",
"rmajor",
"tfcth",
"dr_tf_coil_inboard",
"ohcth",
"cpttf",
"dr_tf_wp",
Expand All @@ -20,4 +20,4 @@
"divfix",
"rmajor"
]
}
}
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