Module containing first wall, blanket and shield routines author: P J Knight, CCFE, Culham Science Centre N/A This module contains routines for calculating the parameters of the first wall, blanket and shield components of a fusion power plant.
!
Superconducting TF coil nuclear heating estimate author: P J Knight, CCFE, Culham Science Centre coilhtmx : output real : peak magnet heating (MW/m3) dpacop : output real : copper stabiliser displacements/atom htheci : output real : peak TF coil case heating (MW/m3) nflutf : output real : maximum neutron fluence (n/m2) pheci : output real : inboard coil case heating (MW) pheco : output real : outboard coil case heating (MW) ptfiwp : output real : inboard TF coil winding pack heating (MW) ptfowp : output real : outboard TF coil winding pack heating (MW) raddose : output real : insulator dose (rad) ptfnuc : output real : TF coil nuclear heating (MW) This subroutine calculates the nuclear heating in the superconducting TF coils, assuming an exponential neutron attenuation through the blanket and shield materials. The estimates are based on 1990 ITER data.
The arrays coef(i,j) and decay(i,j)
are used for exponential decay approximations of the
(superconducting) TF coil nuclear parameters.
j = 1 : stainless steel shield (assumed)
j = 2 : tungsten shield (not used)| Type | Intent | Optional | Attributes | Name | ||
|---|---|---|---|---|---|---|
| real(kind=dp), | intent(out) | :: | coilhtmx | |||
| real(kind=dp), | intent(out) | :: | dpacop | |||
| real(kind=dp), | intent(out) | :: | htheci | |||
| real(kind=dp), | intent(out) | :: | nflutf | |||
| real(kind=dp), | intent(out) | :: | pheci | |||
| real(kind=dp), | intent(out) | :: | pheco | |||
| real(kind=dp), | intent(out) | :: | ptfiwp | |||
| real(kind=dp), | intent(out) | :: | ptfowp | |||
| real(kind=dp), | intent(out) | :: | raddose | |||
| real(kind=dp), | intent(out) | :: | ptfnuc |