PROCESS is a systems code at UKAEA that calculates in a self-consistent manner the parameters of a fusion power plant with a specified performance, ensuring that its operating limits are not violated, and with the option to optimise to a given function of these parameters.
[ ] There are several different descriptions of casthi and the plasma-side steel layer: Inboard leg case plasma side wall thickness Plasma side case Inboard tf coil case inner \(plasma side) thickness Outer case Plasma side casing The outer cylinder Inboard TF coil plasma-facing case thickness inboard TF coil case plasma side thickness Coil case (plasma side) TF coil case inner thickness Plasma-facing wall thickness Plasma side TF coil support coil case thickness outboard distance (radial) Case thickness, plasma side Inboard leg case outboard thickness TF Coil inner leg plasma facing case thickness TF coil inner plasma facing case thickness
and possibly others!
@timothy-nunn @jonmaddock You can see just how useful it will be to have all the variable descriptions in a single place, and to have diagrams in one or more of the output files!
For what it's worth, I would go with something like "Inboard TF coil case: plasma-side thickness", except that this doesn't make clear whether it is measured on the midline.
[ ] Two different plasma side casing shapes can be selected using the i_tf_case_geom switch:
i_tf_case_geom = 0 : rounded plasma side case. As it is the ITER design choice, this configuration is taken as default. i_tf_case_geom = 1 : Straight plasma side case.
Figure 2 illustrates the two plasma side casing configurations.
I suggest removing this switch, and allowing only the rounded plasma-side case (option 0).
[ ] Radial build of TF coil centre-line :
Thickness (m) Outer radius (m)
Innermost edge of TF coil 3.419 3.419
Coil case ("nose") 0.494 3.913 (thkcas)
Insertion gap for winding pack 0.010 3.923 (tfinsgap)
Winding pack ground insulation 0.008 3.931 (tinstf)
Winding - first half 0.227 4.158 (dr_tf_wp/2-tinstf-t
Winding - second half 0.227 4.385 (dr_tf_wp/2-tinstf-t
Winding pack insulation 0.008 4.393 (tinstf)
Insertion gap for winding pack 0.010 4.403 (tfinsgap)
Plasma side case min radius 0.070 4.473 (casthi)
Plasma side case max radius 4.561 4.561 (r_tf_inboard_out)
TF coil dimensions are consistent
The line with `casthi` doesn't relate to the centre-line and should be removed. The right hand column represents the thickness dimensions on the midline, which doesn't have a name at present, so it should read something like this:
In GitLab by @mkovari on Dec 23, 2021, 09:25
casthi
and the plasma-side steel layer:Inboard leg case plasma side wall thickness
Plasma side case
Inboard tf coil case inner \(plasma side) thickness
Outer case
Plasma side casing
The outer cylinder
Inboard TF coil plasma-facing case thickness
inboard TF coil case plasma side thickness
Coil case (plasma side)
TF coil case inner thickness
Plasma-facing wall thickness
Plasma side TF coil support
coil case thickness outboard distance (radial)
Case thickness, plasma side
Inboard leg case outboard thickness
TF Coil inner leg plasma facing case thickness
TF coil inner plasma facing case thickness
and possibly others!
@timothy-nunn @jonmaddock You can see just how useful it will be to have all the variable descriptions in a single place, and to have diagrams in one or more of the output files!
For what it's worth, I would go with something like "Inboard TF coil case: plasma-side thickness", except that this doesn't make clear whether it is measured on the midline.
[ ] Two different plasma side casing shapes can be selected using the
i_tf_case_geom
switch:i_tf_case_geom = 0
: rounded plasma side case. As it is the ITER design choice, this configuration is taken as default.i_tf_case_geom = 1
: Straight plasma side case.Figure 2 illustrates the two plasma side casing configurations.
I suggest removing this switch, and allowing only the rounded plasma-side case (option 0).
Inboard TF coil case: plasma-side thickness 0.158 4.561