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fwbs_variables.py
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1315 lines (923 loc) · 32.4 KB
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"""
Module containing global variables relating to the first wall, blanket and
shield components
### References
-
"""
life_blkt_fpy: float = None
"""Full power blanket lifetime (years)"""
life_blkt: float = None
"""Calendar year blanket lifetime (years)"""
m_fw_blkt_div_coolant_total: float = None
"""mass of water coolant (in shield, blanket, first wall, divertor) [kg]"""
m_vv: float = None
"""vacuum vessel mass [kg]"""
den_steel: float = None
"""density of steel [kg m^-3]"""
denwc: float = None
"""density of tungsten carbide [kg m^-3]"""
dewmkg: float = None
"""total mass of vacuum vessel + cryostat [kg] (calculated if blktmodel>0)"""
f_p_blkt_multiplication: float = None
"""energy multiplication in blanket and shield"""
p_blkt_multiplication_mw: float = None
"""power due to energy multiplication in blanket and shield [MW]"""
fblss: float = None
"""KIT blanket model: steel fraction of breeding zone"""
f_ster_div_single: float = None
"""Solid angle fraction taken by one divertor"""
f_a_fw_outboard_hcd: float = None
"""area fraction of first wall covered by heating/current drive apparatus plus diagnostics"""
fhole: float = None
"""area fraction taken up by other holes (IFE)"""
i_fw_blkt_vv_shape: int = None
"""switch for first wall, blanket, shield and vacuum vessel shape:
- =1 D-shaped (cylinder inboard + ellipse outboard)
- =2 defined by two ellipses
"""
life_fw_fpy: float = None
"""first wall full-power year lifetime (y)"""
m_fw_total: float = None
"""first wall mass [kg]"""
fw_armour_mass: float = None
"""first wall armour mass [kg]"""
fw_armour_thickness: float = None
"""first wall armour thickness [m]"""
fw_armour_vol: float = None
"""first wall armour volume [m^3]"""
i_blanket_type: int = None
"""switch for blanket model:
- =1 CCFE HCPB model
- =2 KIT HCPB model # REMOVED, no longer usable
- =3 CCFE HCPB model with Tritium Breeding Ratio calculation # REMOVED, no longer usable
- =4 KIT HCLL model # REMOVED, no longer usable
- =5 DCLL model - no nutronics model included (in development) please check/choose values for
'dual-coolant blanket' fractions (provided in this file).
- please use i_p_coolant_pumping = 0 or 1.
"""
i_blkt_inboard: int = None
"""switch for inboard blanket:
- =0 No inboard blanket (dr_blkt_inboard=0.0)
- =1 Inboard blanket present
"""
inuclear: int = None
"""switch for nuclear heating in the coils:
- =0 Frances Fox model (default)
- =1 Fixed by user (qnuc)
"""
qnuc: float = None
"""nuclear heating in the coils (W) (`inuclear=1`)"""
f_blkt_li6_enrichment: float = None
"""lithium-6 enrichment of breeding material (%)"""
p_blkt_nuclear_heat_total_mw: float = None
"""nuclear heating in the blanket [MW]"""
pnuc_cp: float = None
"""Total nuclear heating in the ST centrepost [MW]"""
p_cp_shield_nuclear_heat_mw: float = None
"""Neutronic shield nuclear heating in the ST centrepost [MW]"""
pnuc_cp_tf: float = None
"""TF neutronic nuclear heating in the ST centrepost [MW]"""
p_div_nuclear_heat_total_mw: float = None
"""nuclear heating in the divertor [MW]"""
p_fw_nuclear_heat_total_mw: float = None
"""nuclear heating in the first wall [MW]"""
p_fw_hcd_nuclear_heat_mw: float = None
"""Nuclear heating in the HCD apparatus and diagnostics on the first wall [MW]"""
pnucloss: float = None
"""nuclear heating lost via holes [MW]"""
pnucvvplus: float = None
"""nuclear heating to vacuum vessel and beyond [MW]"""
p_shld_nuclear_heat_mw: float = None
"""nuclear heating in the shield [MW]"""
m_blkt_total: float = None
"""mass of blanket [kg]"""
m_blkt_steel_total: float = None
"""mass of blanket - steel part [kg]"""
armour_fw_bl_mass: float = None
"""Total mass of armour, first wall and blanket [kg]"""
# CCFE HCPB Blanket Model i_blanket_type=1
breeder_f: float = None
"""Volume ratio: Li4SiO4/(Be12Ti+Li4SiO4) (`iteration variable 108`)"""
breeder_multiplier: float = None
"""combined breeder/multipler fraction of blanket by volume"""
vfcblkt: float = None
"""He coolant fraction of blanket by volume (`i_blanket_type= 1` (CCFE HCPB))"""
vfpblkt: float = None
"""He purge gas fraction of blanket by volume (`i_blanket_type= 1` (CCFE HCPB))"""
m_blkt_li4sio4: float = None
"""mass of lithium orthosilicate in blanket [kg] (`i_blanket_type=1` (CCFE HCPB))"""
m_blkt_tibe12: float = None
"""mass of titanium beryllide in blanket [kg] (`i_blanket_type=1` (CCFE HCPB))"""
neut_flux_cp: float = None
"""Centrepost TF fast neutron flux (E > 0.1 MeV) [m^(-2).^(-1)]
This variable is only calculated for superconducting (i_tf_sup = 1 )
spherical tokamal magnet designs (itart = 0)
"""
f_neut_shield: float = None
"""Fraction of nuclear power shielded before the CP magnet (ST)
( neut_absorb = -1 --> a fit on simplified MCNP neutronic
calculation is used assuming water cooled (13%) tungesten carbyde )
"""
f_a_fw_coolant_inboard: float = None
"""Inboard FW coolant cross-sectional area void fraction"""
f_a_fw_coolant_outboard: float = None
"""Outboard FW coolant cross-sectional area void fraction"""
psurffwi: float = None
"""Surface heat flux on first wall [MW] (sum = p_fw_rad_total_mw)"""
psurffwo: float = None
"""Surface heat flux on first wall [MW] (sum = p_fw_rad_total_mw)"""
vol_fw_total: float = None
"""First wall volume [m3]"""
f_vol_blkt_steel: float = None
"""Fractions of blanket by volume: steel"""
f_vol_blkt_li4sio4: float = None
"""Fractions of blanket by volume: lithium orthosilicate"""
f_vol_blkt_tibe12: float = None
"""Fractions of blanket by volume: titanium beryllide"""
breedmat: int = None
"""breeder material switch:
- =1 Lithium orthosilicate
- =2 Lithium methatitanate
- =3 Lithium zirconate
"""
densbreed: float = None
"""density of breeder material [kg m^-3]"""
fblbe: float = None
"""beryllium fraction of blanket by volume"""
fblbreed: float = None
"""breeder fraction of blanket breeding zone by volume"""
fblhebmi: float = None
"""helium fraction of inboard blanket box manifold by volume"""
fblhebmo: float = None
"""helium fraction of outboard blanket box manifold by volume """
fblhebpi: float = None
"""helium fraction of inboard blanket back plate by volume """
fblhebpo: float = None
"""helium fraction of outboard blanket back plate by volume """
hcdportsize: int = None
"""switch for size of heating/current drive ports :
- =1 'small'
- =2 'large'
"""
nflutf: float = None
"""peak fast neutron fluence on TF coil superconductor [n m^-2] """
npdiv: int = None
"""number of divertor ports """
nphcdin: int = None
"""number of inboard ports for heating/current drive """
nphcdout: int = None
"""number of outboard ports for heating/current drive """
tbr: float = None
"""tritium breeding ratio"""
tritprate: float = None
"""tritium production rate [g day^-1] """
wallpf: float = None
"""neutron wall load peaking factor """
whtblbreed: float = None
"""mass of blanket - breeder part [kg] """
m_blkt_beryllium: float = None
"""mass of blanket - beryllium part [kg]"""
i_p_coolant_pumping: int = None
"""Switch for pumping power for primary coolant (mechanical power only and peak first wall
temperature is only calculated if `i_p_coolant_pumping=2`):
- =0 User sets pump power directly (p_blkt_coolant_pump_mw, p_fw_coolant_pump_mw, p_div_coolant_pump_mw, p_shld_coolant_pump_mw)
- =1 User sets pump power as a fraction of thermal power (f_p_blkt_coolant_pump_total_heat, f_p_fw_coolant_pump_total_heat, f_p_div_coolant_pump_total_heat, f_p_shld_coolant_pump_total_heat)
- =2 Mechanical pumping power is calculated
- =3 Mechanical pumping power is calculated using specified pressure drop
"""
i_shield_mat: int = None
"""Switch for shield material - *currently only applied in costing routines* `cost_model = 2`
- =0 Tungsten (default)
- =1 Tungsten carbide
"""
i_thermal_electric_conversion: int = None
"""Switch for power conversion cycle:
- =0 Set efficiency for chosen blanket, from detailed models (divertor heat not used)
- =1 Set efficiency for chosen blanket, from detailed models (divertor heat used)
- =2 user input thermal-electric efficiency (eta_turbine)
- =3 steam Rankine cycle
- =4 supercritical CO2 cycle
"""
secondary_cycle_liq: int = None
"""Switch for power conversion cycle for the liquid breeder component of the blanket:
- =2 user input thermal-electric efficiency (eta_turbine)
- =4 supercritical CO2 cycle
"""
i_blkt_coolant_type: int = None
"""Switch for blanket coolant (set via blkttype):
- =1 helium
- =2 pressurized water
"""
i_fw_coolant_type: str = None
"""switch for first wall coolant (can be different from blanket coolant):
- 'helium'
- 'water'
"""
dr_fw_wall: float = None
"""wall thickness of first wall coolant channels [m]"""
radius_fw_channel: float = None
"""radius of first wall cooling channels [m]"""
dx_fw_module: float = None
"""Width of a FW module containing a cooling channel [m]"""
temp_fw_coolant_in: float = None
"""inlet temperature of first wall coolant [K]"""
temp_fw_coolant_out: float = None
"""outlet temperature of first wall coolant [K]"""
pres_fw_coolant: float = None
"""first wall coolant pressure [Pa] (`i_thermal_electric_conversion>1`)"""
temp_fw_peak: float = None
"""peak first wall temperature [K]"""
roughness_fw_channel: float = None
"""first wall channel roughness epsilon [m]"""
len_fw_channel: float = None
"""Length of a single first wall channel (all in parallel) [m]
(`iteration variable 114`, useful for `constraint equation 39`)
"""
f_fw_peak: float = None
"""peaking factor for first wall heat loads. (Applied separately to inboard and outboard loads.
Applies to both neutron and surface loads. Only used to calculate peak temperature - not
the coolant flow rate.)
"""
pres_blkt_coolant: float = None
"""blanket coolant pressure [Pa] (`i_thermal_electric_conversion>1`)"""
temp_blkt_coolant_in: float = None
"""inlet temperature of blanket coolant [K] (`i_thermal_electric_conversion>1`)"""
temp_blkt_coolant_out: float = None
"""Outlet temperature of blanket coolant [K] (`i_thermal_electric_conversion>1`)
- input if `i_blkt_coolant_type=1` (helium)
- calculated if `i_blkt_coolant_type=2` (water)
"""
coolp: float = None
"""blanket coolant pressure [Pa] (stellarator only)"""
n_blkt_outboard_modules_poloidal: int = None
"""number of outboard blanket modules in poloidal direction (`i_thermal_electric_conversion>1`)"""
n_blkt_inboard_modules_poloidal: int = None
"""number of inboard blanket modules in poloidal direction (`i_thermal_electric_conversion>1`)"""
n_blkt_outboard_modules_toroidal: int = None
"""number of outboard blanket modules in toroidal direction (`i_thermal_electric_conversion>1`)"""
n_blkt_inboard_modules_toroidal: int = None
"""number of inboard blanket modules in toroidal direction (`i_thermal_electric_conversion>1`)"""
temp_fw_max: float = None
"""maximum temperature of first wall material [K] (`i_thermal_electric_conversion>1`)"""
fw_th_conductivity: float = None
"""thermal conductivity of first wall material at 293 K (W/m/K) (Temperature dependence
is as for unirradiated Eurofer)
"""
fvoldw: float = None
"""area coverage factor for vacuum vessel volume"""
fvolsi: float = None
"""area coverage factor for inboard shield volume"""
fvolso: float = None
"""area coverage factor for outboard shield volume"""
fwclfr: float = None
"""first wall coolant fraction (calculated if `i_pulsed_plant=1` or `ipowerflow=1`)"""
p_div_rad_total_mw: float = None
"""Total radiation power incident on the divertor(s) (MW)"""
p_fw_rad_total_mw: float = None
"""Radiation power incident on the first wall (MW)"""
p_fw_hcd_rad_total_mw: float = None
"""Radiation power incident on the heating and current drive systems on the first wall (MW)"""
pradloss: float = None
"""Radiation power lost through holes (eventually hits shield) (MW)
Only used for stellarator
"""
p_tf_nuclear_heat_mw: float = None
"""nuclear heating in the TF coil (MW)"""
ptfnucpm3: float = None
"""nuclear heating in the TF coil (MW/m3) (`blktmodel>0`)"""
r_cryostat_inboard: float = None
"""cryostat radius [m]"""
z_cryostat_half_inside: float = None
"""cryostat height [m]"""
dr_pf_cryostat: float = None
"""Radial distance between outer edge of furthest away PF coil (or stellarator
modular coil) and cryostat [m]
"""
vol_cryostat: float = None
"""Cryostat structure volume [m^3]"""
vol_cryostat_internal: float = None
"""Internal volume of the cryostat [m^3]"""
vol_vv: float = None
"""vacuum vessel volume [m^3]"""
vfshld: float = None
"""coolant void fraction in shield"""
vol_blkt_total: float = None
"""volume of blanket [m^3]"""
vol_blkt_total_full_coverage: float = None
"""Volume of blanket with no holes or ports (toroidally continuous) [m³]"""
vol_blkt_inboard: float = None
"""volume of inboard blanket [m^3]"""
vol_blkt_inboard_full_coverage: float = None
"""Volume of inboard blanket with no holes or ports (toroidally continuous) [m³]"""
vol_blkt_outboard: float = None
"""volume of outboard blanket [m^3]"""
vol_blkt_outboard_full_coverage: float = None
"""Volume of outboard blanket with no holes or ports (toroidally continuous) [m³]"""
vol_shld_total: float = None
"""volume of shield [m^3]"""
whtshld: float = None
"""mass of shield [kg]"""
wpenshld: float = None
"""mass of the penetration shield [kg]"""
wtshldi: float = None
"""mass of inboard shield [kg]"""
wtshldo: float = None
"""mass of outboard shield [kg]"""
irefprop: int = None
"""Switch to use REFPROP routines (stellarator only)"""
fblli: float = None
"""lithium fraction of blanket by volume (stellarator only)"""
fblli2o: float = None
"""lithium oxide fraction of blanket by volume (stellarator only)"""
fbllipb: float = None
"""lithium lead fraction of blanket by volume (stellarator only)"""
fblvd: float = None
"""vanadium fraction of blanket by volume (stellarator only)"""
m_blkt_li2o: float = None
"""mass of blanket - Li_2O part [kg]"""
wtbllipb: float = None
"""mass of blanket - Li-Pb part [kg]"""
m_blkt_vanadium: float = None
"""mass of blanket - vanadium part [kg]"""
m_blkt_lithium: float = None
"""mass of blanket - lithium part [kg]"""
f_a_blkt_cooling_channels: float = None
"""coolant void fraction in blanket."""
blktmodel: int = None
"""switch for blanket/tritium breeding model (see i_blanket_type):
- =0 original simple model
- =1 KIT model based on a helium-cooled pebble-bed blanket (HCPB) reference design
"""
declblkt: float = None
"""neutron power deposition decay length of blanket structural material [m] (stellarators only)"""
declfw: float = None
"""neutron power deposition decay length of first wall structural material [m] (stellarators only)"""
declshld: float = None
"""neutron power deposition decay length of shield structural material [m] (stellarators only)"""
blkttype: int = None
"""Switch for blanket type:
- =1 WCLL;
- =2 HCLL; efficiency taken from M. Kovari 2016
"PROCESS": A systems code for fusion power plants - Part 2: Engineering
https://www.sciencedirect.com/science/article/pii/S0920379616300072
Feedheat & reheat cycle assumed
- =3 HCPB; efficiency taken from M. Kovari 2016
"PROCESS": A systems code for fusion power plants - Part 2: Engineering
https://www.sciencedirect.com/science/article/pii/S0920379616300072
Feedheat & reheat cycle assumed
"""
etaiso: float = None
"""isentropic efficiency of FW and blanket coolant pumps"""
eta_coolant_pump_electric: float = None
"""electrical efficiency of primary coolant pumps"""
i_fw_blkt_shared_coolant: int = None
"""Switch for whether the FW and BB are on the same pump system
i.e. do they have the same primary coolant or not
- =0 FW and BB have the same primary coolant, flow = FWin->FWout->BBin->BBout
- =1 FW and BB have the different primary coolant and are on different pump systems
"""
i_blkt_liquid_breeder_type: int = None
"""Switch for Liquid Metal Breeder Material
- =0 PbLi
- =1 Li
"""
i_blkt_dual_coolant: int = None
"""Switch to specify whether breeding blanket is single-cooled or dual-coolant.
- =0 Single coolant used for FW and Blanket (H2O or He). Solid Breeder.
- =1 Single coolant used for FW and Blanket (H2O or He). Liquid metal breeder
circulted for tritium extraction.
- =2 Dual coolant: primary coolant (H2O or He) for FW and blanket structure;
secondary coolant is self-cooled liquid metal breeder.
"""
i_blkt_liquid_breeder_channel_type: int = None
"""Switch for Flow Channel Insert (FCI) type if liquid metal breeder blanket.
- =0 Thin conducting walls, default electrical conductivity (bz_channel_conduct_liq) is Eurofer
- =1 Insulating Material, assumed perfect electrical insulator, default density (den_ceramic) is for SiC
- =2 Insulating Material, electrical conductivity (bz_channel_conduct_liq) is input (default Eurofer), default density (den_ceramic) is for SiC
"""
i_blkt_module_segmentation: int = None
"""Switch for Multi Module Segment (MMS) or Single Modle Segment (SMS)
- =0 MMS
- =1 SMS
"""
n_liq_recirc: int = None
"""Number of liquid metal breeder recirculations per day, for use with i_blkt_dual_coolant=1"""
r_f_liq_ib: float = None
"""Radial fraction of BZ liquid channels"""
r_f_liq_ob: float = None
"""Radial fraction of BZ liquid channels"""
w_f_liq_ib: float = None
"""Toroidal fraction of BZ liquid channels"""
w_f_liq_ob: float = None
"""Toroidal fraction of BZ liquid channels"""
den_ceramic: float = None
"""FCI material density"""
th_wall_secondary: float = None
"""Liquid metal coolant/breeder wall thickness thin conductor or FCI [m]"""
bz_channel_conduct_liq: float = None
"""Liquid metal coolant/breeder thin conductor or FCI wall conductance [A V^-1 m^-1]"""
a_bz_liq: float = None
"""Toroidal width of the rectangular cooling channel [m] for long poloidal sections of blanket breeding zone"""
b_bz_liq: float = None
"""Radial width of the rectangular cooling channel [m] for long poloidal sections of blanket breeding zone"""
nopol: int = None
"""Number of poloidal sections in a liquid metal breeder/coolant channel for module/segment"""
nopipes: int = None
"""Number of Liquid metal breeder/coolant channels per module/segment"""
den_liq: float = None
"""Liquid metal breeder/coolant density [kg m^-3]"""
wht_liq: float = None
"""Liquid metal"""
wht_liq_ib: float = None
"""Liquid metal"""
wht_liq_ob: float = None
"""Liquid metal"""
specific_heat_liq: float = None
"""Liquid metal breeder/coolant specific heat [J kg^-1 K^-1]"""
thermal_conductivity_liq: float = None
"""Liquid metal breeder/coolant thermal conductivity [W m^-1 K^-1]"""
dynamic_viscosity_liq: float = None
"""Liquid metal breeder/coolant dynamic viscosity [Pa s]"""
electrical_conductivity_liq: float = None
"""Liquid metal breeder/coolant electrical conductivity [Ohm m]"""
hartmann_liq: list[float] = None
"""Hartmann number"""
b_mag_blkt: list[float] = None
"""Toroidal Magnetic feild strength for IB/OB blanket [T]"""
etaiso_liq: float = None
"""Isentropic efficiency of blanket liquid breeder/coolant pumps"""
blpressure_liq: float = None
"""blanket liquid metal breeder/coolant pressure [Pa]"""
inlet_temp_liq: float = None
"""Inlet (scan var 68) temperature of the liquid breeder/coolant [K]"""
outlet_temp_liq: float = None
"""Outlet (scan var 69) temperature of the liquid breeder/coolant [K]"""
den_fw_coolant: float = None
"""Density of the FW primary coolant"""
visc_fw_coolant: float = None
"""Viscosity of the FW primary coolant"""
den_blkt_coolant: float = None
"""Density of the blanket primary coolant"""
visc_blkt_coolant: float = None
"""Viscosity of the blanket primary coolant"""
cp_fw: float = None
"""Spesific heat for FW and blanket primary coolant(s)"""
cv_fw: float = None
"""Spesific heat for FW and blanket primary coolant(s)"""
cp_bl: float = None
"""Spesific heat for FW and blanket primary coolant(s)"""
cv_bl: float = None
"""Spesific heat for FW and blanket primary coolant(s)"""
f_nuc_pow_bz_struct: float = None
"""For a dual-coolant blanket, fraction of BZ power cooled by primary coolant"""
f_nuc_pow_bz_liq: float = None
"""For a dual-coolant blanket, fraction of BZ self-cooled power (secondary coolant)"""
pnuc_fw_ratio_dcll: float = None
"""For a dual-coolant blanket, ratio of FW nuclear power as fraction of total"""
pnuc_blkt_ratio_dcll: float = None
"""For a dual-coolant blanket, ratio of Blanket nuclear power as fraction of total"""
n_blkt_inboard_module_coolant_sections_radial: int = None
"""Number of radial and poloidal sections that make up the total primary coolant flow
length in a blanket module (IB and OB)
"""
n_blkt_inboard_module_coolant_sections_poloidal: int = None
"""Number of radial and poloidal sections that make up the total primary coolant flow
length in a blanket module (IB and OB)
"""
n_blkt_outboard_module_coolant_sections_radial: int = None
"""Number of radial and poloidal sections that make up the total primary coolant flow
length in a blanket module (IB and OB)
"""
n_blkt_outboard_module_coolant_sections_poloidal: int = None
"""Number of radial and poloidal sections that make up the total primary coolant flow
length in a blanket module (IB and OB)
"""
bzfllengi_n_rad_liq: int = None
"""Number of radial and poloidal sections that make up the total secondary coolant/breeder
flow length in a blanket module (IB and OB)
"""
bzfllengi_n_pol_liq: int = None
"""Number of radial and poloidal sections that make up the total secondary coolant/breeder
flow length in a blanket module (IB and OB)
"""
bzfllengo_n_rad_liq: int = None
"""Number of radial and poloidal sections that make up the total secondary coolant/breeder
flow length in a blanket module (IB and OB)
"""
bzfllengo_n_pol_liq: int = None
"""Number of radial and poloidal sections that make up the total secondary coolant/breeder
flow length in a blanket module (IB and OB)
"""
radius_blkt_channel: float = None
"""Radius of blanket cooling channels [m]"""
radius_blkt_channel_90_bend: float = None
"""Radius of blanket cooling channel 90° bend [m]"""
radius_fw_channel_90_bend: float = None
"""Radius of first wall cooling channel 90° bend [m]"""
radius_fw_channel_180_bend: float = None
"""Radius of first wall cooling channel 180° bend [m]"""
radius_blkt_channel_180_bend: float = None
"""Radius of blanket cooling channel 180° bend [m]"""
dz_fw_half: float = None
"""Half-height of first wall structure [m]"""
def init_fwbs_variables():
"""Initialise FWBS variables"""
global \
life_blkt_fpy, \
life_blkt, \
m_fw_blkt_div_coolant_total, \
m_vv, \
den_steel, \
denwc, \
dewmkg, \
f_p_blkt_multiplication, \
p_blkt_multiplication_mw, \
fblss, \
f_ster_div_single, \
f_a_fw_outboard_hcd, \
fhole, \
i_fw_blkt_vv_shape, \
life_fw_fpy, \
m_fw_total, \
fw_armour_mass, \
fw_armour_thickness, \
fw_armour_vol, \
i_blanket_type, \
i_blkt_inboard, \
inuclear, \
qnuc, \
f_blkt_li6_enrichment, \
p_blkt_nuclear_heat_total_mw, \
pnuc_cp, \
p_cp_shield_nuclear_heat_mw, \
pnuc_cp_tf, \
p_div_nuclear_heat_total_mw, \
p_fw_nuclear_heat_total_mw, \
p_fw_hcd_nuclear_heat_mw, \
pnucloss, \
pnucvvplus, \
p_shld_nuclear_heat_mw, \
m_blkt_total, \
m_blkt_steel_total, \
armour_fw_bl_mass, \
breeder_f, \
breeder_multiplier, \
vfcblkt, \
vfpblkt, \
m_blkt_li4sio4, \
m_blkt_tibe12, \
neut_flux_cp, \
f_neut_shield, \
f_a_fw_coolant_inboard, \
f_a_fw_coolant_outboard, \
psurffwi, \
psurffwo, \
vol_fw_total, \
f_vol_blkt_steel, \
f_vol_blkt_li4sio4, \
f_vol_blkt_tibe12, \
breedmat, \
densbreed, \
fblbe, \
fblbreed, \
fblhebmi, \
fblhebmo, \
fblhebpi, \
fblhebpo, \
hcdportsize, \
nflutf, \
npdiv, \
nphcdin, \
nphcdout, \
tbr, \
tritprate, \
wallpf, \
whtblbreed, \
m_blkt_beryllium, \
i_p_coolant_pumping, \
i_shield_mat, \
i_thermal_electric_conversion, \
secondary_cycle_liq, \
i_blkt_coolant_type, \
i_fw_coolant_type, \
dr_fw_wall, \
radius_fw_channel, \
dx_fw_module, \
temp_fw_coolant_in, \
temp_fw_coolant_out, \
pres_fw_coolant, \
temp_fw_peak, \