fwbs_variables Module

Full power blanket lifetime (years)

Calendar year blanket lifetime (years)

mass of water coolant (in shield, blanket, first wall, divertor) [kg]

vacuum vessel mass [kg]

density of steel [kg m^-3]

density of tungsten [kg m^-3]

density of tungsten carbide [kg m^-3]

total mass of vacuum vessel + cryostat [kg] (calculated if blktmodel>0)

energy multiplication in blanket and shield

power due to energy multiplication in blanket and shield [MW]

KIT blanket model: steel fraction of breeding zone

Solid angle fraction taken by one divertor

area fraction covered by heating/current drive apparatus plus diagnostics

area fraction taken up by other holes (IFE)

switch for first wall, blanket, shield and vacuum vessel shape:

• =1 D-shaped (cylinder inboard + ellipse outboard)
• =2 defined by two ellipses

first wall full-power year lifetime (y)

first wall mass [kg]

first wall armour mass [kg]

first wall armour thickness [m]

first wall armour volume [m^3]

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
• =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 primary_pumping = 0 or 1.

switch for inboard blanket:

• =0 No inboard blanket (blnkith=0.0)
• =1 Inboard blanket present

switch for nuclear heating in the coils:

• =0 Frances Fox model (default)
• =1 Fixed by user (qnuc)

nuclear heating in the coils (W) (inuclear=1)

lithium-6 enrichment of breeding material (%)

nuclear heating in the blanket [MW]

Total nuclear heating in the ST centrepost [MW]

Neutronic shield nuclear heating in the ST centrepost [MW]

TF neutronic nuclear heating in the ST centrepost [MW]

nuclear heating in the divertor [MW]

nuclear heating in the first wall [MW]

nuclear heating in the HCD apparatus and diagnostics [MW]

nuclear heating lost via holes [MW]

nuclear heating to vacuum vessel and beyond [MW]

nuclear heating in the shield [MW]

mass of blanket [kg]

mass of blanket - steel part [kg]

Total mass of armour, first wall and blanket [kg]

Volume ratio: Li4SiO4/(Be12Ti+Li4SiO4) (iteration variable 108)

combined breeder/multipler fraction of blanket by volume

He coolant fraction of blanket by volume (iblanket= 1,3 (CCFE HCPB))

He purge gas fraction of blanket by volume (iblanket= 1,3 (CCFE HCPB))

mass of lithium orthosilicate in blanket [kg] (iblanket=1,3 (CCFE HCPB))

mass of titanium beryllide in blanket [kg] (iblanket=1,3 (CCFE HCPB))

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)

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 )

Inboard/outboard FW coolant void fraction

Inboard/outboard FW coolant void fraction

Surface heat flux on first wall [MW] (sum = pradfw)

Surface heat flux on first wall [MW] (sum = pradfw)

First wall volume [m3]

Fractions of blanket by volume: steel, lithium orthosilicate, titanium beryllide

Fractions of blanket by volume: steel, lithium orthosilicate, titanium beryllide

Fractions of blanket by volume: steel, lithium orthosilicate, titanium beryllide

breeder material switch (iblanket=2 (KIT HCPB)):

• =1 Lithium orthosilicate
• =2 Lithium methatitanate
• =3 Lithium zirconate

density of breeder material [kg m^-3] (iblanket=2 (KIT HCPB))

beryllium fraction of blanket by volume (if iblanket=2, is Be fraction of breeding zone)

breeder fraction of blanket breeding zone by volume (iblanket=2 (KIT HCPB))

helium fraction of inboard blanket box manifold by volume (iblanket=2 (KIT HCPB))

helium fraction of outboard blanket box manifold by volume (iblanket=2 (KIT HCPB))

helium fraction of inboard blanket back plate by volume (iblanket=2 (KIT HCPB))

helium fraction of outboard blanket back plate by volume (iblanket=2 (KIT HCPB))

switch for size of heating/current drive ports (iblanket=2 (KIT HCPB)):

• =1 'small'
• =2 'large'

peak fast neutron fluence on TF coil superconductor [n m^-2] (iblanket=2 (KIT HCPB))

number of divertor ports (iblanket=2 (KIT HCPB))

number of inboard ports for heating/current drive (iblanket=2 (KIT HCPB))

number of outboard ports for heating/current drive (iblanket=2 (KIT HCPB))

tritium breeding ratio (iblanket=2,3 (KIT HCPB/HCLL))

tritium production rate [g day^-1] (iblanket=2 (KIT HCPB))

neutron wall load peaking factor (iblanket=2 (KIT HCPB))

mass of blanket - breeder part [kg] (iblanket=2 (KIT HCPB))

mass of blanket - beryllium part [kg]

Blanket thickness switch (Do not set blnkith, blnkoth, fwith or fwoth when iblanket=3):

• =1 thin 0.53 m inboard, 0.91 m outboard
• =2 medium 0.64 m inboard, 1.11 m outboard
• =3 thick 0.75 m inboard, 1.30 m outboard

Switch for pumping power for primary coolant (mechanical power only and peak first wall temperature is only calculated if primary_pumping=2):

• =0 User sets pump power directly (htpmw_blkt, htpmw_fw, htpmw_div, htpmw_shld)
• =1 User sets pump power as a fraction of thermal power (fpumpblkt, fpumpfw, fpumpdiv, fpumpshld)
• =2 Mechanical pumping power is calculated
• =3 Mechanical pumping power is calculated using specified pressure drop

Switch for shield material - currently only applied in costing routines cost_model = 2

• =0 Tungsten (default)
• =1 Tungsten carbide

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 (etath)
• =3 steam Rankine cycle
• =4 supercritical CO2 cycle

Switch for power conversion cycle for the liquid breeder component of the blanket:

• =2 user input thermal-electric efficiency (etath)
• =4 supercritical CO2 cycle

Switch for blanket coolant (set via blkttype):

• =1 helium
• =2 pressurized water

inner radius of inboard first wall/blanket coolant channels (stellarator only) [m]

inner radius of outboard first wall/blanket coolant channels (stellarator only) [m]

switch for first wall coolant (can be different from blanket coolant):

• 'helium'
• 'water'

wall thickness of first wall coolant channels [m]

radius of first wall cooling channels [m]

pitch of first wall cooling channels [m]

inlet temperature of first wall coolant [K]

outlet temperature of first wall coolant [K]

first wall coolant pressure [Pa] (secondary_cycle>1)

peak first wall temperature [K]

first wall channel roughness epsilon [m]

Length of a single first wall channel (all in parallel) [m] (iteration variable 114, useful for constraint equation 39)

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.)

blanket coolant pressure [Pa] (secondary_cycle>1)

inlet temperature of blanket coolant [K] (secondary_cycle>1)

Outlet temperature of blanket coolant [K] (secondary_cycle>1)

• input if coolwh=1 (helium)
• calculated if coolwh=2 (water)

blanket coolant pressure [Pa] (stellarator only)

number of outboard blanket modules in poloidal direction (secondary_cycle>1)

number of inboard blanket modules in poloidal direction (secondary_cycle>1)

number of outboard blanket modules in toroidal direction (secondary_cycle>1)

number of inboard blanket modules in toroidal direction (secondary_cycle>1)

maximum temperature of first wall material [K] (secondary_cycle>1)

thermal conductivity of first wall material at 293 K (W/m/K) (Temperature dependence is as for unirradiated Eurofer)

area coverage factor for vacuum vessel volume

area coverage factor for inboard shield volume

area coverage factor for outboard shield volume

first wall coolant fraction (calculated if lpulse=1 or ipowerflow=1)

Radiation power incident on the divertor (MW)

Radiation power incident on the first wall (MW)

Radiation power incident on the heating and current drive system (MW)

Radiation power lost through holes (eventually hits shield) (MW) Only used for stellarator

nuclear heating in the TF coil (MW)

nuclear heating in the TF coil (MW/m3) (blktmodel>0)

cryostat radius [m]

cryostat height [m]

radial distance between outer edge of largest (ipfloc=3) PF coil (or stellarator modular coil) and cryostat [m]

cryostat volume [m^3]

vacuum vessel volume [m^3]

coolant void fraction in shield

volume of blanket [m^3]

volume of inboard blanket [m^3]

volume of outboard blanket [m^3]

volume of shield [m^3]

mass of shield [kg]

mass of the penetration shield [kg]

mass of inboard shield [kg]

mass of outboard shield [kg]

Switch to use REFPROP routines (stellarator only)

lithium fraction of blanket by volume (stellarator only)

lithium oxide fraction of blanket by volume (stellarator only)

lithium lead fraction of blanket by volume (stellarator only)

vanadium fraction of blanket by volume (stellarator only)

mass of blanket - Li_2O part [kg]

mass of blanket - Li-Pb part [kg]

mass of blanket - vanadium part [kg]

mass of blanket - lithium part [kg]

coolant void fraction in blanket.

switch for blanket/tritium breeding model (see iblanket):

• =0 original simple model
• =1 KIT model based on a helium-cooled pebble-bed blanket (HCPB) reference design

neutron power deposition decay length of blanket structural material [m] (stellarators only)

neutron power deposition decay length of first wall structural material [m] (stellarators only)

neutron power deposition decay length of shield structural material [m] (stellarators only)

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

isentropic efficiency of FW and blanket coolant pumps

electrical efficiency of primary coolant pumps

BLANKET REFACTOR For DCLL, but to be used by all mods that share blanket library after testing. Thermodynamic Model for primary_pumping == 2

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

Switch for Liquid Metal Breeder Material - =0 PbLi - =1 Li

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.

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

Switch for Multi Module Segment (MMS) or Single Modle Segment (SMS) - =0 MMS - =1 SMS

Number of liquid metal breeder recirculations per day, for use with icooldual=1

Radial fraction of BZ liquid channels

Radial fraction of BZ liquid channels

Toroidal fraction of BZ liquid channels

Toroidal fraction of BZ liquid channels

FCI material density

Liquid metal coolant/breeder wall thickness thin conductor or FCI [m]

Liquid metal coolant/breeder thin conductor or FCI wall conductance [A V^-1 m^-1]

Toroidal width of the rectangular cooling channel [m] for long poloidal sections of blanket breeding zone

Radial width of the rectangular cooling channel [m] for long poloidal sections of blanket breeding zone

Number of poloidal sections in a liquid metal breeder/coolant channel for module/segment

Number of Liquid metal breeder/coolant channels per module/segment

Liquid metal breeder/coolant density [kg m^-3]

Liquid metal

Liquid metal

Liquid metal

Liquid metal breeder/coolant specific heat [J kg^-1 K^-1]

Liquid metal breeder/coolant thermal conductivity [W m^-1 K^-1]

Liquid metal breeder/coolant dynamic viscosity [Pa s]

Liquid metal breeder/coolant electrical conductivity [Ohm m]

Hartmann number

Toroidal Magnetic feild strength for IB/OB blanket [T]

Isentropic efficiency of blanket liquid breeder/coolant pumps

blanket liquid metal breeder/coolant pressure [Pa]

Inlet (scan var 68) and Outlet (scan var 69) temperature of the liquid breeder/coolant [K]

Inlet (scan var 68) and Outlet (scan var 69) temperature of the liquid breeder/coolant [K]

Density of the FW primary coolant

Viscosity of the FW primary coolant

Density of the blanket primary coolant

Viscosity of the blanket primary coolant

Spesific heat for FW and blanket primary coolant(s)

Spesific heat for FW and blanket primary coolant(s)

Spesific heat for FW and blanket primary coolant(s)

Spesific heat for FW and blanket primary coolant(s)

For a dual-coolant blanket, fraction of BZ power cooled by primary coolant

For a dual-coolant blanket, fraction of BZ self-cooled power (secondary coolant)

For a dual-coolant blanket, ratio of FW/Blanket nuclear power as fraction of total

For a dual-coolant blanket, ratio of FW/Blanket nuclear power as fraction of total

Number of radial and poloidal sections that make up the total primary coolant flow length in a blanket module (IB and OB)

Number of radial and poloidal sections that make up the total primary coolant flow length in a blanket module (IB and OB)

Number of radial and poloidal sections that make up the total primary coolant flow length in a blanket module (IB and OB)

Number of radial and poloidal sections that make up the total primary coolant flow length in a blanket module (IB and OB)

Number of radial and poloidal sections that make up the total secondary coolant/breeder flow length in a blanket module (IB and OB)

Number of radial and poloidal sections that make up the total secondary coolant/breeder flow length in a blanket module (IB and OB)

Number of radial and poloidal sections that make up the total secondary coolant/breeder flow length in a blanket module (IB and OB)

Number of radial and poloidal sections that make up the total secondary coolant/breeder flow length in a blanket module (IB and OB)