Divertor
The divertor provides a means of removing plasma reaching the scrape-off layer. The principal outputs from the code are the divertor heat load, used to determine its lifetime, and its peak temperature. The divertor is cooled either by gaseous helium or by pressurised water.
Switch i_single_null
controls the overall plasma configuration. Setting i_single_null= 0
corresponds to an up-down symmetric, double null configuration, while
i_single_null= 1
(the default) assumes a single null plasma with the divertor at the
bottom of the machine. The vertical build and PF coil current scaling
algorithms take the value of this switch into account, although not the plasma
geometry at present.
The Harrison-Kukushkin-Hotston divertor model1 developed for ITER is available, but is unlikely to be relevant for a reactor.
The divertor heat flux hldiv
can be calculated or it can be input by the user. Options are selected using the switch i_hldiv
:
i_hldiv |
Description |
---|---|
0 | the user inputs the value for hldiv |
1 | the Peng chamber model (divtart ) is called to calculate hldiv |
2 | the Wade heat flux model (divwade ) is called to calculate hldiv |
Peng Chamber model | divtart()
i_hldiv == 1
The tight aspect ratio tokamak divertor model (divtart()
) 5 calculates the divertor heat flux by
assuming that the power is evenly spread around the divertor chamber by the action of a gaseous
target. Each divertor is assumed to be approximately triangular in the R,Z plane.
The inner radius of the divertor region is given by:
This is treated as the same as the centrepost and first wall thickness at the divertor height.
The outer radius of the divertor region is simply
The height of the divertor box is taken to be the same as the gap between the plasma X-point and the divertor structure.
Therefore the vertical plate surface area in the divertor box is given by:
The top horizontal plate area is given by:
We define an angle \theta such that:
The diagonal plate area is then given by:
Therefore the total divertor surface area is given by:
If a double null machine is set up with i_single_null = 0
then the total divertor area is simply:
The divertor heat load is then found as:
Radiated power area
The main assumption of the Peng gaseous divertor model is that the power radiated to the divertor is equally radiated in the divertor box across all three surfaces. This may not truly be the case in reality.
The interactive graph below can be used to investigate how changing the key prameters changes the divertor configuration. The grey box represents the first wall, the far right red line represents the right hand edge of the divertor region (r_{\text{outer}}), the far left red line represents the left hand edge of the divertor region (r_{\text{inner}}) and the blue line represents the bottom of the divertor region (\Delta z_{\text{plasma,div}}).
Wade Heat Flux Model
i_hldiv == 2
A divertor heat flux model is provided in Appendix A.II. of 2. This uses the Eich scaling 3 and S-factor 4 to calculate the SOL width at the outboard divertor, mapped to the midplane:
where
This is then used to calculate the wetted area in the divertor
where N_{div} is the number of divertors (1 or 2), F_{exp} is the relevant flux expansion, and \theta_{div} is the tilt of the separatrix relative to the target in the poloidal plane, and has the form
where
where B_{p,mid} and B_{T,mid} are the poloidal and toroidal fields on the outer midplane. The parameter \beta_{div} is the angle of incidence between the field line and the target.
The divertor heat flux in \mathrm{MW}/\mathrm{m^{2}} is then
where f_{rad,div} is the SOL radiative fraction.
For the purposes of this model, the following are inputs:
- Flux expansion F_{exp} (
flux_exp
, default = 2) - Field line angle with respect to divertor target plate (degrees) \beta_{div} (
beta_div
), also available as an iteration variable (170) - SOL radiative fraction, f_{rad,div} (
rad_fraction_sol
).
-
N.A. Uckan and ITER Physics Group, 'ITER Physics Design Guidelines: 1989', ITER Documentation Series, No. 10, IAEA/ITER/DS/10 (1990) ↩
-
M.R. Wade & J.A. Leuer, 'Cost Drivers for a Tokamak-Based Compact Pilot Plant, Fusion Science and Technology, 77:2, 119-143 (2021) ↩
-
T. Eich et al, 'Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER', Nucl. Fusion 53 093031 (2013) ↩
-
A. Scarabosio et al, 'Scaling of the divertor power spreading (S-factor) in open and closed divertor operation in JET and ASDEX Upgrade, Journal of Nuclear Materials, Vol. 463, 49-54 (2015) ↩
-
Y.-K. M. Peng, J. B. Hicksand AEA Fusion, Culham (UK), "Engineering feasibility of tight aspect ratio Tokamak (spherical torus) reactors". 1990. https://inis.iaea.org/records/ey2rf-dah04 ↩