Module-level Variables

Volume of inboard and outboard shield (m3)

Volume of inboard and outboard shield (m3)

Volume of inboard and outboard Vacuum Vessel (m3)

Volume of inboard and outboard Vacuum Vessel (m3)

Clearance between uppermost PF coil and cryostat lid (m)

Inboard/outboard void fraction of blanket

Inboard/outboard void fraction of blanket

Inboard/outboard blanket coolant channel length (radial direction) (m)

Inboard/outboard blanket coolant channel length (radial direction) (m)

Inboard/outboard blanket mid-plan toroidal circumference for segment (m)

Inboard/outboard blanket mid-plan toroidal circumference for segment (m)

Inboard/outboard blanket segment poloidal length (m)

Inboard/outboard blanket segment poloidal length (m)

Inboard/outboard primary blanket flow lengths (m)

Inboard/outboard primary blanket flow lengths (m)

Inboard/outboard secondary blanket flow lengths (m)

Inboard/outboard secondary blanket flow lengths (m)

Inboard/outboard first wall nuclear heating (MW)

Inboard/outboard first wall nuclear heating (MW)

Inboard/outboard first wall peak temperature (K)

Inboard/outboard first wall peak temperature (K)

Inboard/outboard total mass flow rate to remove inboard FW power (kg/s)

Inboard/outboard total mass flow rate to remove inboard FW power (kg/s)

Inboard/outboard total mass flow rate to remove inboard FW power (kg/s)

Inboard/utboard total number of pipes

Inboard/utboard total number of pipes

Inboard/outboard mass flow rate per coolant pipe (kg/s)

Inboard/outboard mass flow rate per coolant pipe (kg/s)

Neutron power deposited inboard/outboard blanket blanket (MW)

Neutron power deposited inboard/outboard blanket blanket (MW)

Inboard/outboard blanket mass flow rate for coolant (kg/s)

Inboard/outboard blanket mass flow rate for coolant (kg/s)

Inboard/outboard blanket mass flow rate for coolant (kg/s)

Inboard/outboard blanket mass flow rate for liquid breeder (kg/s)

Inboard/outboard blanket mass flow rate for liquid breeder (kg/s)

Inboard/outboard blanket mass flow rate for liquid breeder (kg/s)

Total mass flow rate for coolant (kg/s)

Inboard/outboard total num of pipes

Inboard/outboard total num of pipes

Inboard/outboard mass flow rate per coolant pipe (kg/s)

Inboard/outboard mass flow rate per coolant pipe (kg/s)

Inboard/outboard coolant velocity in blanket (m/s)

Inboard/outboard coolant velocity in blanket (m/s)

Inboard/outboard first wall pumping power (MW)

Inboard/outboard first wall pumping power (MW)

Inboard/outboard blanket pumping power (MW)

Inboard/outboard blanket pumping power (MW)

Inboard/outboard fw and blanket pumping power (MW)

Inboard/outboard fw and blanket pumping power (MW)

Blanket internal half-height (m)

Shield internal half-height (m)

Vacuum vessel internal half-height (m)

Switch used to specify selected component: blanket=0, shield=1, vacuum vessel=2

maximum number of groups of PF coils

maximum number of PF coils in a given group

maximum number of points across the midplane of the plasma at which the field from the PF coils is fixed

maximum number of fixed current PF coils

maximum total number of coils across all groups

new variable to include 2 additional circuits: plasma and central solenoid

smoothing parameter used in PF coil current calculation at the beginning of pulse (BoP)

allowable hoop stress in Central Solenoid structural material (Pa)

Switch for CS stress calculation:

• =0 Hoop stress only
• =1 Hoop + Axial stress

Central solenoid vertical cross-sectional area (m2)

Central solenoid (OH) trun cross-sectional area (m2)

central solenoid conductor+void area with area of steel subtracted (m2)

maximum field in central solenoid at end of flat-top (EoF) (T)

maximum field in central solenoid at beginning of pulse (T)

peak field at coil i (T)

PF group current array, flux-swing cancellation current (MA) Input if i_pf_current=0, computed otherwise

PF group current array, equilibrium current (MA) Input if i_pf_current=0, computed otherwise

Central solenoid overall current density at beginning of pulse (A/m2)

Central solenoid overall current density at end of flat-top (A/m2) (iteration variable 37) (sweep variable 62)

current per turn in coil i at time j (A)

peak current per turn input for PF coil i (A)

PF coil current array, at beginning of pulse (MA) Indexed by coil number, not group number

PF coil current array, at flat top (MA) Indexed by coil number, not group number

PF coil current array, at end of pulse (MA) Indexed by coil number, not group number

Efficiency of transfer of PF stored energy into or out of storage.

ratio of central solenoid overall current density at beginning of flat-top / end of flat-top

ratio of central solenoid overall current density at beginning of pulse / end of flat-top (iteration variable 41)

copper fraction of strand in central solenoid

copper fraction of cable conductor (PF coils)

F-value for constraint equation 51

Switch for location of PF coil group i:

• =1 PF coil on top of central solenoid (flux ramp only)
• =2 PF coil on top of TF coil (flux ramp only)
• =3 PF coil outside of TF coil (equilibrium coil)
• =4 PF coil, general location (equilibrium coil)

switch for PF & CS coil conductor type:

• =0 superconducting PF coils
• =1 resistive PF coils

total sum of I x turns x radius for all PF coils and CS (Am)

switch for superconductor material in central solenoid:

• =1 ITER Nb3Sn critical surface model with standard ITER parameters
• =2 Bi-2212 high temperature superconductor (range of validity T < 20K, adjusted field b < 104 T, B > 6 T)
• =3 NbTi
• =4 ITER Nb3Sn model with user-specified parameters
• =5 WST Nb3Sn parameterisation
• =6 REBCO HTS tape in CroCo strand
• =7 Durham Ginzburg-Landau critical surface model for Nb-Ti
• =8 Durham Ginzburg-Landau critical surface model for REBCO
• =9 Hazelton experimental data + Zhai conceptual model for REBCO

switch for superconductor material in PF coils:

• =1 ITER Nb3Sn critical surface model with standard ITER parameters
• =2 Bi-2212 high temperature superconductor (range of validity T < 20K, adjusted field b < 104 T, B > 6 T)
• =3 NbTi
• =4 ITER Nb3Sn model with user-specified parameters
• =5 WST Nb3Sn parameterisation
• =6 REBCO HTS tape in CroCo strand
• =7 Durham Ginzburg-Landau critical surface model for Nb-Ti
• =8 Durham Ginzburg-Landau critical surface model for REBCO
• =9 Hazelton experimental data + Zhai conceptual model for REBCO

superconductor strand critical current density under operating conditions in central solenoid (A/m2). Necessary for the cost calculation in $/kA m

superconductor strand critical current density under operating conditions in PF coils (A/m2). Necessary for the cost calculation in $/kA m

Switch for controlling the current of the PF coils:

• =0 Input via the variables curpfb, curpff, curpfs
• =1 SVD targets zero field across midplane (flux swing coils) and the correct vertical field at the plasma center (equilibrium coils)

Switch for the placement of Location 3 (outboard) PF coils when the TF coils are superconducting (i_tf_sup = 1)

• =0 (Default) Outboard PF coils follow TF shape in an ellipsoidal winding surface
• =1 Outboard PF coils all have same radius, cylindrical winding surface

central solenoid superconductor critical current density (A/m2) at beginning-of-pulse

central solenoid superconductor critical current density (A/m2) at end-of-flattop

central solenoid cable critical current density (A/m2) at beginning-of-pulse

central solenoid cable critical current density (A/m2) at end-of-flattop

number of PF circuits (including central solenoid and plasma)

number of PF coils in group j

number of filaments the top and bottom of the central solenoid should be broken into during scaling (5 - 10 is good)

number of groups of PF coils. Symmetric coil pairs should all be in the same group

number of PF coils (excluding the central solenoid) + 1

Central solenoid height / TF coil internal height

central solenoid steel fraction (iteration variable 122)

Ratio of permissible PF coil conductor current density to critical conductor current density based on short-sample DC measurements

steel case thickness for PF coil i (m)

PF coil resistivity (if ipfres=1) (Ohm-m)

Resistivity of CS and PF coil bus bars (irrespective of whether the coils themselves are superconducting or resistive) (Ohm-m)

mass of heaviest PF coil (tonnes)

radius of largest PF coil (m)

Total mean wall plug power dissipated in PFC and CS power supplies (MW) (issue #713)

central solenoid resistive power during flattop (W)

total PF coil resistive losses during flattop (W)

inner radius of coil i (m)

outer radius of coil i (m)

peak current in coil i (MA-turns)

average winding pack current density of PF coil i (A/m2) at time of peak current in that coil (calculated for ipfloc=1 coils)

allowable central solenoid current density at end of flat-top (A/m2)

allowable central solenoid current density at beginning of pulse (A/m2)

allowable winding pack current density of PF coil i (A/m2)

radius to the centre of the central solenoid (m)

radial distance (m) from outboard TF coil leg to centre of ipfloc=3 PF coils

radius of PF coil i (m)

offset (m) of radial position of ipfloc=1 PF coils from being directly above the central solenoid

offset (m) of radial position of ipfloc=2 PF coils from being at rmajor (offset = rpf2triangrminor)

PF coil radial positioning adjuster:

• for groups j with ipfloc(j) = 1; rref(j) is ignored
• for groups j with ipfloc(j) = 2; rref(j) is ignored
• for groups j with ipfloc(j) = 3; rref(j) is ignored
• for groups j with ipfloc(j) = 4; rref(j) is radius of the coil in units of minor radii from the major radius (r = rmajor + rref*rminor)

Maximum shear stress (Tresca criterion) coils/central solenoid [MPa]

maximum permissible tensile stress (MPa) in steel coil cases for superconducting PF coils (ipfres=0)

fraction of JxB hoop force supported by steel case for superconducting PF coils (ipfres=0)

mutual inductance matrix (H)

Central solenoid temperature margin (K)

number of turns in PF coil i

winding pack void fraction of PF coil i for coolant

void fraction of central solenoid conductor for coolant

total flux swing available for burn (Wb)

flux swing from PF coils for burn (Wb)

flux swing from PF coils for startup (Wb)

total flux swing from PF coils (Wb)

total flux swing from the central solenoid (Wb)

central solenoid flux swing for burn (Wb)

central solenoid flux swing for startup (Wb)

total flux swing for startup (constraint eqn 51 to enforce vssu=vsres+vsind) (Wb)

total flux swing for pulse (Wb)

used in current waveform of PF coils/central solenoid

total mass of the PF coil conductor (kg)

total mass of the PF coil structure (kg)

conductor mass for PF coil i (kg)

structure mass for PF coil i (kg)

upper point of PF coil i (m)

lower point of PF coil i (m)

z (height) location of PF coil i (m)

PF coil vertical positioning adjuster:

• for groups j with ipfloc(j) = 1; zref(j) is ignored
• for groups j with ipfloc(j) = 2 AND itart=1 (only); zref(j) is distance of centre of PF coil from inside edge of TF coil (remember that PF coils for STs lie within the TF coil)
• for groups j with ipfloc(j) = 3; zref(j) = ratio of height of coil group j to plasma minor radius

Central solenoid max field limit [T]

F-value for CS mmax field (cons. 79, itvar 149)

Ratio of CS coil turn conduit length to depth

Length of CS of CS coil turn conduit

Depth/width of CS of CS coil turn conduit

Length of CS of CS coil turn conduit length

Length of CS of CS coil turn conduit length

power plant type

short descriptive title for the run

switch for turning on/off diagnostic messages

• =0 turn off diagnostics
• =1 turn on diagnostics

turns on built-in tests if set to 1

maximum number of VMCON iterations

input file prefix

output file prefix

scan parameter description label

scan value name label

scan parameter description label (2nd dimension)

scan value name label (2nd dimension)

Makes iscan available globally.

VMCON convergence parameter "sum"

minimum minor radius (m)

Minimal radial space between plasma and coils (m)

blanket total surface area (m2)

inboard blanket surface area (m2)

outboard blanket surface area (m2)

inboard blanket box manifold thickness (m) (blktmodel>0)

outboard blanket box manifold thickness (m) (blktmodel>0)

inboard blanket base plate thickness (m) (blktmodel>0)

outboard blanket base plate thickness (m) (blktmodel>0)

inboard blanket breeding zone thickness (m) (blktmodel>0) (iteration variable 90)

outboard blanket breeding zone thickness (m) (blktmodel>0) (iteration variable 91)

inboard blanket thickness (m); (calculated if blktmodel>0) (=0.0 if iblnkith=0)

outboard blanket thickness (m); calculated if blktmodel>0

top blanket thickness (m), = mean of inboard and outboard blanket thicknesses

central solenoid inboard radius (m) (iteration variable 29)

cryostat lid height scaling factor (tokamaks)

cryostat thickness (m)

vacuum vessel inboard thickness (TF coil / shield) (m)

vacuum vessel outboard thickness (TF coil / shield) (m)

vacuum vessel topside thickness (TF coil / shield) (m) (= d_vv_bot if double-null)

vacuum vessel underside thickness (TF coil / shield) (m)

F-value for stellarator radial space check (constraint equation 83)

Fraction of space occupied by CS pre-compression structure

Separation force in CS coil pre-compression structure

first wall total surface area (m2)

inboard first wall surface area (m2)

outboard first wall surface area (m2)

inboard first wall thickness, initial estimate as calculated (m)

outboard first wall thickness, initial estimate as calculated (m)

gap between inboard vacuum vessel and thermal shield (m) (iteration variable 61)

gap between central solenoid and TF coil (m) (iteration variable 42)

minimum gap between outboard vacuum vessel and TF coil (m) (iteration variable 31)

gap between outboard vacuum vessel and TF coil (m)

maximum (half-)height of TF coil (inside edge) (m)

difference in distance from midplane of upper and lower portions of TF legs (non-zero for single-null devices) (m)

height to top of (upper) TF coil leg (m)

half-height of TF coil inboard leg straight section (m)

Switch for existence of central solenoid:

• =0 central solenoid not present
• =1 central solenoid exists

Switch for existence of central solenoid pre-compression structure:

• =0 no pre-compression structure
• =1 calculated pre-compression structure

Switch for placing the TF coil inside the CS

• = 0 TF coil is outside the CS (default)
• = 1 TF coil is inside the CS

Central solenoid thickness (m) (iteration variable 16)

CS coil precompression structure thickness (m)

sum of thicknesses to the major radius (m)

Required space between coil and plasma for blanket shield wall etc (m)

plasma inboard radius (m) (consistency equation 29)

radius to inboard shield (inside point) (m)

radius to outboard shield (outside point) (m)

Radial plasma facing side position of inboard vacuum vessel [m]

Radial inner side position of inboard neutronic shield [m]

Radial plasma facing side position of inboard neutronic shield [m]

Mid-plane inboard TF coil leg radius at the centre-machine side [m]

Mid-plane inboard TF coil leg radius at middle of the coil [m]

Mid-plane inboard TF coil leg radius at the plasma side [m]

Mid-plane outboard TF coil leg radius at the middle of the coil [m]

Switch selecting the he parametrization of the outer radius of the top of the CP part of the TF coil 0 : r_cp_top is set by the plasma shape 1 : r_cp_top is a user input 2 : r_cp_top is set using the CP top and midplane CP radius ratio

Top outer radius of the centropost (ST only) (m)

Ratio between the top and the midplane TF CP outer radius [-] Not used by default (-1) must be larger than 1 otherwise

TF coil horizontal inner bore (m)

TF coil vertical inner bore (m)

Gap between plasma and first wall, inboard side (m) (if iscrp=1) Iteration variable: ixc = 73 Scan variable: nsweep = 58

Gap between plasma and first wall, outboard side (m) (if iscrp=1) Iteration variable: ixc = 74 Scan variable: nsweep = 59

shield total surface area (m2)

inboard shield surface area (m2)

outboard shield surface area (m2)

inboard shield thickness (m) (iteration variable 93)

lower (under divertor) shield thickness (m)

outboard shield thickness (m) (iteration variable 94)

upper/lower shield thickness (m); calculated if blktmodel > 0 (= shldlth if double-null)

allowable stress in CSpre-compression structure (Pa)

inboard TF coil thickness, (centrepost for ST) (m) (input, calculated or iteration variable 13)

vertical distance between centre of TF coils and centre of plasma (m)

TF coil outboard leg / inboard leg radial thickness ratio (i_tf_sup=0 only) (iteration variable 75)

Outboard TF coil thickness (m)

Minimum metal-to-metal gap between TF coil and thermal shield (m)

TF-VV thermal shield thickness, inboard (m)

TF-VV thermal shield thickness, outboard (m)

TF-VV thermal shield thickness, vertical build (m)

vertical gap between vacuum vessel and thermal shields (m)

vertical gap between x-point and divertor (m) (if = 0, it is calculated)

vertical gap between top of plasma and first wall (m) (= vgap_xpoint_divertor if double-null)

gap between vacuum vessel and blanket (m)

length of inboard divertor plate (m)

length of outboard divertor plate (m)

poloidal length, x-point to inboard strike point (m)

poloidal length, x-point to outboard strike point (m)

outboard strike point radius (m)

base plant electric load (W)

cryogenic plant power (MW)

Maximum cryogenic plant power (MW) Constraint equation icc = 87 Scan variable nwseep = 56

f-value for maximum cryogenic plant power Iteration variable ixc = 164 Constraint equation icc = 87

AC to resistive power conversion for TF coils

thermal to electric conversion efficiency if secondary_cycle=2; otherwise calculated.

facility heat removal (MW)

total baseline power required at all times (MW)

scaled fraction of gross power to balance-of-plant

power to mgf (motor-generator flywheel) units (MW) (ignored if iscenr=2)

fraction of total blanket thermal power required to drive the blanket coolant pumps (default assumes water coolant) (secondary_cycle=0)

fraction of total divertor thermal power required to drive the divertor coolant pumps (default assumes water coolant)

fraction of total first wall thermal power required to drive the FW coolant pumps (default assumes water coolant) (secondary_cycle=0)

fraction of total shield thermal power required to drive the shield coolant pumps (default assumes water coolant)

Minimum total electrical power for primary coolant pumps (MW) (NOT RECOMMENDED)

Heat removal at cryogenic temperature tmpcry (W)

Heat removal at cryogenic temperature tcoolin (W)

heat transport system electrical pump power (MW)

blanket primary coolant mechanical pumping power (MW)

blanket secondary coolant mechanical pumping power (MW)

blanket primary + secondary coolant mechanical pumping power (MW)

divertor coolant mechanical pumping power (MW)

first wall coolant mechanical pumping power (MW)

shield and vacuum vessel coolant mechanical pumping power (MW)

Waste power lost from primary coolant pumps (MW)

switch for power flow model:

• =0 pre-2014 version
• =1 comprehensive 2014 model

Switch for shield thermal power destiny:

• =0 does not contribute to energy generation cycle
• =1 contributes to energy generation cycle

number of primary heat exchangers

total pulsed power system load (MW)

peak MVA requirement

heat removal from first wall/divertor (MW)

gross electric power (MW)

power dissipated in heating and current drive system (MW)

maximum injector power during pulse (heating and ramp-up/down phase) (MW)

injector wall plug power (MW)

secondary injector wall plug power (MW)

net electric power (MW)

recirculating electric power (MW)

total thermal power removed from fusion core (MW)

Low-grade heat lost in divertor (MW)

Low-grade heat lost into HCD apparatus (MW)

Low-grade heat (MW)

Low-grade heat (VV + lost)(MW)

Low-grade heat deposited in shield (MW)

High-grade heat useful for electric production (MW)

base AC power requirement per unit floor area (W/m2)

total steady state TF coil AC power demand (MW)

estimate of total low voltage power (MW)

power required for tritium processing (MW)

coolant temperature at turbine inlet (K) (secondary_cycle = 3,4)

vacuum pump power (MW)

switch for vacuum pumping model:

• ='old' for old detailed ETR model
• ='simple' for simple steady-state model with comparison to ITER cryopumps

number of high vacuum pumps (real number), each with the throughput of one ITER cryopump (50 Pa m3 s-1), all operating at the same time (vacuum_model='simple')

switch for vacuum pump type:

• =0 - for turbomolecular pump (magnetic bearing) with speed of 2.0 m3/s (1.95 for N2, 1.8 for He, 1.8 for DT)
• =1 - for compound cryopump with nominal speed of 10.0 m3/s (9.0 for N2, 5.0 for He and 25.0 for DT)

number of ducts (torus to pumps)

vacuum system duct length scaling

base pressure during dwell before gas pre-fill(Pa)

divertor chamber pressure during burn (Pa)

Pump throughput (molecules/s) (default is ITER value)

plasma chamber wall outgassing rate (Pa-m/s)

neutral gas temperature in chamber (K)

mass of vacuum duct shield (kg)

diameter of duct passage (m)

number of high vacuum pumps

switch for dwell pumping options:

• =0 pumping only during tdwell
• =1 pumping only during tramp
• =2 pumping during tdwell + tramp

area of one pumping port as a fraction of plasma surface area

maximum pumping speed per unit area for deuterium & tritium, molecular flow

effective pumping speed reduction factor due to duct impedance

initial neutral pressure at the beginning of the dwell phase (Pa)

outgassing decay index

outgassing prefactor kw: outgassing rate at 1 s per unit area (Pa m s-1)

Radial BZ thickness [m]

Radial BZ thickness [m]

Structure/coolant compositional fractions

Structure/coolant compositional fractions

MF/BSS compositional fractions

MF/BSS compositional fractions

MF/BSS compositional fractions

MF/BSS compositional fractions

Volume of FCIs, other BZ structure, liquid channels, backwall and MF/BSS [m^3]

Volume of FCIs, other BZ structure, liquid channels, backwall and MF/BSS [m^3]

Volume of FCIs, other BZ structure, liquid channels, backwall and MF/BSS [m^3]

BZ masses by composition [kg]

BZ masses by composition [kg]

BZ masses by composition [kg]

BZ masses by composition [kg]

BZ masses by composition [kg]

BZ masses by composition [kg]

BZ masses by composition [kg]

Backwall masses by composition [kg]

Backwall masses by composition [kg]

Backwall masses by composition [kg]

MF/BSS masses by composition [kg]

MF/BSS masses by composition [kg]

FW masses by composition [kg]

FW masses by composition [kg]

FW masses by composition [kg]

Total masses of material in blanket [kg]

Total masses of material in blanket [kg]

Total mass for an inboard/outboard reactor segment [kg]

Total mass for an inboard/outboard reactor segment [kg]

Total mass for an inboard/outboard reactor segment [kg]

Dimensionless winding pack width

Dimensionless winding pack radial thickness

Ratio of peak field with ripple to nominal axisymmetric peak field

Current in each TF coil

Total cross-sectional area of winding pack including GW insulation and insertion gap [m2]

Total cross-sectional area of winding pack without ground insulation and insertion gap [m2]

Inboard coil steel coil cross-sectional area [m2]

Inboard coil insulation cross-section per coil [m2]

Inboard coil steel fraction [-]

Inboard coil insulation fraction [-]

Vertical distance from the midplane to the top of the tapered section [m]

Radial position of plasma-facing edge of TF coil outboard leg [m]

Radial position of outer edge of TF coil inboard leg [m]

Radial position of inner edge and centre of winding pack [m]

Radial position of outer edge and centre of winding pack [m]

Radial position of centre and centre of winding pack [m]

Conductor layer radial thickness at centercollumn top [m] Ground insulation layer included, only defined for itart = 1

CP turn insulation volume [m3]

CP ground insulation volume [m3]

Volume of the CP outer casing cylinder

Minimal toroidal thickness of of winding pack [m]

Averaged toroidal thickness of of winding pack [m]

Average lateral casing thickness [m]

Front casing area [m2]

Nose casing area [m2]

Inboard mid-plane cross-section area of the WP ground insulation [m2]

TF ouboard leg turn insulation area per coil [m2]

TF outboard leg ground insulation area per coil [m2]

Exact TF ouboard leg conductor area [m2]

Half toroidal angular extent of a single TF coil inboard leg

Tan half toroidal angular extent of a single TF coil inboard leg

Conductor area radial and toroidal dimension (integer turn only) [m]

Conductor area radial and toroidal dimension (integer turn only) [m]

Cable area radial and toroidal dimension (integer turn only) [m]

Cable area radial and toroidal dimension (integer turn only) [m]

Turn radial and toroidal dimension (integer turn only) [m]

Turn radial and toroidal dimension (integer turn only) [m]

Cable area averaged dimension (square shape) [m]

Total inboard vertical tension (all coils) [N]

The Tresca stress experienced by the Vacuum Vessel when the SCTF coil quenches [Pa]

Area of cable space inside jacket

administration building volume (m3)

volume of administration buildings (m3)

aux building supporting tokamak processes length, width, height (m)

aux building supporting tokamak processes length, width, height (m)

aux building supporting tokamak processes length, width, height (m)

Site-Wide Auxiliary Cooling Water facility length, width, height (m)

Site-Wide Auxiliary Cooling Water facility length, width, height (m)

Site-Wide Auxiliary Cooling Water facility length, width, height (m)

Radial thickness of bio-shield around reactor (m)

Chemistry labs and treatment buldings length, width, height (m)

Chemistry labs and treatment buldings length, width, height (m)

Chemistry labs and treatment buldings length, width, height (m)

vertical clearance from TF coil to cryostat (m) (calculated for tokamaks)

clearance beneath TF coil to foundation (including basement) (m)

control building length, width, height (m)

control building length, width, height (m)

control building length, width, height (m)

control building volume (m3)

volume of control, protection and i&c building (m3)

vertical dimension of crane arm, operating over reactor (m)

horizontal clearance to building wall for crane operation (m)

vertical clearance for crane operation (m)

Cryogenic Buildings for Magnet and Fuel Cycle length, width, height (m)

Cryogenic Buildings for Magnet and Fuel Cycle length, width, height (m)

Cryogenic Buildings for Magnet and Fuel Cycle length, width, height (m)

Magnet Cryo Storage Tanks length, width, height (m)

Magnet Cryo Storage Tanks length, width, height (m)

Magnet Cryo Storage Tanks length, width, height (m)

vertical clearance from TF coil to cryostat (m)

volume of cryoplant building (m3)

effective total floor space (m2)

Transformers and electrical distribution facilities length, width, height (m)

Transformers and electrical distribution facilities length, width, height (m)

Transformers and electrical distribution facilities length, width, height (m)

Electric (eesential and non-essential) load centres length, width, height (m)

Electric (eesential and non-essential) load centres length, width, height (m)

Electric (eesential and non-essential) load centres length, width, height (m)

Energy Storage facilities length, width, height (m)

Energy Storage facilities length, width, height (m)

Energy Storage facilities length, width, height (m)

volume of electrical equipment building (m3)

volume of energy storage equipment building (m3) (not used if lpulse=0)

Fuel Cycle facilities length, width (m)

Fuel Cycle facilities length, width (m)

foundation thickness (m)

air & gas supply (amalgamated) buildings length, width, height (m)

air & gas supply (amalgamated) buildings length, width, height (m)

air & gas supply (amalgamated) buildings length, width, height (m)

clearance beneath TF coil (m)

HCD building length, width, height (m)

HCD building length, width, height (m)

HCD building length, width, height (m)

clearance around components in hot cell (m)

hot cell wall thickness (m)

heat sinks length, width, height (m)

heat sinks length, width, height (m)

heat sinks length, width, height (m)

hot cell storage component separation distance (m)

hot cell storage and maintenance facility height (m)

hazardous waste storage building length, width, height (m)

hazardous waste storage building length, width, height (m)

hazardous waste storage building length, width, height (m)

switch between routines estimating building sizes (0 = default; 1 = updated)

switch to select verbose output for buildings (1 = verbose)

radioactive waste smelting facility length, width, height (m)

radioactive waste smelting facility length, width, height (m)

radioactive waste smelting facility length, width, height (m)

ILW waste storage building length, width, height (m)

ILW waste storage building length, width, height (m)

ILW waste storage building length, width, height (m)

LLW waste storage building length, width, height (m)

LLW waste storage building length, width, height (m)

LLW waste storage building length, width, height (m)

pulsed magnet power building length, width, height (m)

pulsed magnet power building length, width, height (m)

pulsed magnet power building length, width, height (m)

steady state magnet power trains building length, width, height (m)

steady state magnet power trains building length, width, height (m)

steady state magnet power trains building length, width, height (m)

maintenance control building length, width, height (m)

maintenance control building length, width, height (m)

maintenance control building length, width, height (m)

maintenance building volume multiplication factor

NBI system length, width (m)

NBI system length, width (m)

volume of PF coil power supply building (m3)

power injection building volume (m3)

quantity safety factor for component use during plant lifetime

reactor building volume multiplication factor

reactor building roof thickness (m)

reactor building volume (m3)

reactor building wall thickness (m)

clearance around reactor (m)

reactor building foundation thickness (m)

reactor building length, width, height (m)

reactor building length, width, height (m)

reactor building length, width, height (m)

reactor building roof thickness (m)

reactor building wall thickness (m)

volume of maintenance and assembly building (m3)

robotics buildings length, width, height (m)

robotics buildings length, width, height (m)

robotics buildings length, width, height (m)

clearance to building wall for crane operation (m)

clearance around reactor (m)

security & safety buildings length, width, height (m)

security & safety buildings length, width, height (m)

security & safety buildings length, width, height (m)

fraction of shield mass per TF coil to be moved in the maximum shield lift

shops and warehouse volume (m3)

volume of shops and buildings for plant auxiliaries (m3)

footprint of staff buildings (m2)

staff buildings height (m)

clearance above crane to roof (m)

volume of TF coil power supply building (m3) (calculated if TF coils are superconducting)

transportation clearance between components (m)

transportation clearance between components (m)

volume of tritium, fuel handling and health physics buildings (m3)

turbine hall length, width, height (m)

turbine hall length, width, height (m)

turbine hall length, width, height (m)

tritiated waste storage building length, width, height (m)

tritiated waste storage building length, width, height (m)

tritiated waste storage building length, width, height (m)

internal volume of reactor building (m3)

sum of nuclear buildings volumes (m3)

warm shop length, width, height (m)

warm shop length, width, height (m)

warm shop length, width, height (m)

water, laundry & drainage buildings length, width, height (m)

water, laundry & drainage buildings length, width, height (m)

water, laundry & drainage buildings length, width, height (m)

reactor building crane capacity (kg) (calculated if 0 is input)

hot cell crane capacity (kg) (calculated if 0 is input)

[cold] workshop buildings length, width, height (m)

[cold] workshop buildings length, width, height (m)

[cold] workshop buildings length, width, height (m)

distance from centre of machine to building wall (m)

volume of warm shop building (m3)

warm shop building volume multiplication factor

Floor area of reactor building in m^2

Floor area of electrical equipment and power supply building in m^2

Floor area of auxiliary services building in m^2

Floor area of hot cell building in m^2

Floor area of reactor service building in m^2

Floor area of service water building in m^2

Floor area of fuel handling and storage building in m^2

Floor area of controlroom building in m^2

Floor area of AC power supply building in m^2

Floor area of admin building in m^2

Floor area of site service building in m^2

Floor area of cryogenics and inert gas storage building in m^2

Floor area of security building in m^2

Switch for pulse timings (if lpulse=1):

• =0, tohs = Ip(MA)/0.1 tramp, tqnch = input
• =1, tohs = iteration var or input. tramp/tqnch max of input or tohs

burn time (s) (calculated if lpulse=1)

burn time (s) - used for internal consistency

full cycle time (s)

down time (s)

time between pulses in a pulsed reactor (s) (iteration variable 17)

heating time, after current ramp up (s)

array of time points during plasma pulse (s)

array of time labels during plasma pulse (s)

time intervals - as strings (s)

plasma current ramp-up time for current initiation (s) (calculated if lpulse=0) (iteration variable 65)

Switch for plasma current ramp-up time (if lpulse=0):

• = 0, tohs = tramp = tqnch = Ip(MA)/0.5
• <>0, tohs = tohsin; tramp, tqnch are input

pulse length = tohs + t_fusion_ramp + tburn + tqnch

shut down time for PF coils (s); if pulsed, = tohs

initial PF coil charge time (s); if pulsed, = tohs

number of energy confinement time scaling laws

beam ion mass (amu)

average mass of fuel portion of ions (amu)

average mass of all ions (amu)

current profile index (calculated from q_0 and q if iprofile=1)

density profile index

pressure profile index

Alpha particle production rate per unit volume, from plasma and beams [particles/m3/sec]

Alpha particle production rate per unit volume, just from plasma [particles/m3/sec]

temperature profile index

aspect ratio (iteration variable 1)

multiplier for beam-background fusion calculation

total plasma beta (iteration variable 5) (calculated if stellarator)

fast alpha beta component

allowable beta

allowable lower beta

neutral beam beta component

poloidal beta

normaised total beta

leading coefficient for NB beta fraction

poloidal field (T)

toroidal field on axis (T) (iteration variable 2)

total toroidal + poloidal field (T)

fractional plasma burnup

fractional plasma burnup user input

vertical field at plasma (T)

Destabalisation parameter for iprofile=6 beta limit

coeff. for sawteeth effects on burn V-s requirement

multiplying factor times plasma volume (normally=1)

maximum ratio of conducting wall distance to plasma minor radius for vertical stability (constraint equation 23)

electron density (/m3) (iteration variable 6)

fuel ion density (/m3)

electron-electron coulomb logarithm

ion-electron coulomb logarithm

density limit (/m3) as calculated using various models

thermal alpha density (/m3)

hot beam ion density, variable (/m3)

hot beam ion density from calculation (/m3)

Troyon-like coefficient for beta scaling

density limit (/m3)

total ion density (/m3)

line averaged electron density (/m3)

proton ash density (/m3)

plasma average "n-tau" (seconds/m3)

high Z ion density (/m3)

Max. normalized gradient length in el. density (ipedestal==0 only)

Max. normalized gradient length in el. temperature (ipedestal==0 only)

maximum (eps*beta_poloidal) (constraint equation 6). Note: revised issue #346 "Operation at the tokamak equilibrium poloidal beta-limit in TFTR", 1992 Nucl. Fusion 32 1468

inverse aspect ratio

fraction of plasma current produced by auxiliary current drive

fraction of plasma current produced inductively

fraction of alpha energy to electrons

Fraction of alpha power deposited in plasma. Default of 0.95 taken from https://doi.org/10.1088/0029-5515/39/12/305.

fraction of alpha power to ions

deuterium fuel fraction

fraction of power to the lower divertor in double null configuration (i_single_null = 0 only) (default assumes SN)

factor to convert plasma surface area to first wall area in neutron wall load calculation (iwalld=1)

fraction of Greenwald density to set as pedestal-top density. If <0, pedestal-top density set manually using neped (ipedestal==1). (iteration variable 145)

fraction of Greenwald density to set as separatrix density. If <0, separatrix density set manually using nesep (ipedestal==1). (iteration variable 152)

helium-3 fuel fraction

physics figure of merit (= plasma_currentaspect*sbar, where sbar=1)

Zohm elongation scaling adjustment factor (ishape=2, 3)

F-value for Psep >= Plh + Paux (constraint equation 73)

F-value for minimum pdivt (constraint equation 80)

f-value for the constraint ne(0) > ne(ped) (constraint equation 81) (Iteration variable 154)

tritium fuel fraction

fusion reaction rate, from beams and plasma (reactions/m3/sec)

fusion reaction rate, just from plasma (reactions/m3/sec)

fraction of the plasma current produced by non-inductive means (iteration variable 44)

Ejima coefficient for resistive startup V-s formula

ratio of (fast alpha + neutral beam beta) to thermal beta

H factors for an ignited plasma for each energy confinement time scaling law

H factor on energy confinement times, radiation corrected (iteration variable 10).

Maximum allowed energy confinement time (s)

switch for bootstrap current scaling

• =1 ITER 1989 bootstrap scaling (high R/a only)
• =2 for Nevins et al general scaling
• =3 for Wilson et al numerical scaling
• =4 for Sauter et al scaling
• =5 for Sakai et al scaling
• =6 for ARIES scaling
• =7 for Andrade et al scaling
• =8 for Hoang et al scaling
• =9 for Wong et al scaling
• =10 for Gi-I et al scaling
• =11 for Gi-II et al scaling

switch for beta limit scaling (constraint equation 24)

• =0 apply limit to total beta
• =1 apply limit to thermal beta
• =2 apply limit to thermal + neutral beam beta
• =3 apply limit to toroidal beta

switch for plasma current scaling to use

• =1 Peng analytic fit
• =2 Peng double null divertor scaling (ST)
• =3 simple ITER scaling (k = 2.2, d = 0.6)
• =4 later ITER scaling, a la Uckan
• =5 Todd empirical scaling I
• =6 Todd empirical scaling II
• =7 Connor-Hastie model
• =8 Sauter scaling allowing negative triangularity
• =9 FIESTA ST fit

switch for diamagnetic current scaling

• =0 Do not calculate
• =1 Use original TART scaling
• =2 Use SCENE scaling

switch for density limit to enforce (constraint equation 5)

• =1 old ASDEX
• =2 Borrass model for ITER (I)
• =3 Borrass model for ITER (II)
• =4 JET edge radiation
• =5 JET simplified
• =6 Hugill-Murakami Mq limit
• =7 Greenwald limit

number of divertors (calculated from i_single_null)

switch for fast alpha pressure calculation

• =0 ITER physics rules (Uckan) fit
• =1 Modified fit (D. Ward) - better at high temperature

switch for ignition assumption. Obviously, ignite must be zero if current drive is required. If ignite is 1, any auxiliary power is assumed to be used only during plasma start-up, and is excluded from all steady-state power balance calculations.

• =0 do not assume plasma ignition
• =1 assume ignited (but include auxiliary power in costs)</UL

switch for inverse quadrature in L-mode scaling laws 5 and 9:

• =0 inverse quadrature not used
• =1 inverse quadrature with Neo-Alcator tau-E used

switch for pedestal profiles:

• =0 use original parabolic profiles
• =1 use pedestal profile

switch for Pfirsch-Schlüter current scaling (issue #413):

• =0 Do not calculate
• =1 Use SCENE scaling

electron density of pedestal [m-3] (`ipedestal==1)

electron density at separatrix [m-3] (`ipedestal==1)

critical ballooning parameter value

critical electron density at separatrix [m-3]

plasma resistivity pre-factor

r/a of density pedestal (ipedestal==1)

r/a of temperature pedestal (ipedestal==1)

r/a where the temperature gradient is largest (ipedestal==0)

r/a where the density gradient is largest (ipedestal==0)

temperature profile index beta (`ipedestal==1)

electron temperature of pedestal (keV) (ipedestal==1)

electron temperature at separatrix (keV) (ipedestal==1) calculated if reinke criterion is used (icc=78)

switch for current profile consistency:

• =0 use input values for alphaj, rli, dnbeta
• =1 make these consistent with input q, q_0 values (recommend i_plasma_current=4 with this option)
• =2 use input values for alphaj, rli. Scale dnbeta with aspect ratio (original scaling)
• =3 use input values for alphaj, rli. Scale dnbeta with aspect ratio (Menard scaling)
• =4 use input values for alphaj, dnbeta. Set rli from elongation (Menard scaling)
• =5 use input value for alphaj. Set rli and dnbeta from Menard scaling
• =6 use input values for alphaj, c_beta. Set rli from Menard and dnbeta from Tholerus

switch for radiation loss term usage in power balance (see User Guide):

• =0 total power lost is scaling power plus radiation
• =1 total power lost is scaling power plus core radiation only
• =2 total power lost is scaling power only, with no additional allowance for radiation. This is not recommended for power plant models.

switch for energy confinement time scaling law (see description in tauscl)

tauscl(ipnlaws) : labels describing energy confinement scaling laws:

• ( 1) Neo-Alcator (ohmic)
• ( 2) Mirnov (H-mode)
• ( 3) Merezkhin-Muhkovatov (L-mode)
• ( 4) Shimomura (H-mode)
• ( 5) Kaye-Goldston (L-mode)
• ( 6) ITER 89-P (L-mode)
• ( 7) ITER 89-O (L-mode)
• ( 8) Rebut-Lallia (L-mode)
• ( 9) Goldston (L-mode)
• (10) T10 (L-mode)
• (11) JAERI-88 (L-mode)
• (12) Kaye-Big Complex (L-mode)
• (13) ITER H90-P (H-mode)
• (14) ITER Mix (L-mode)
• (15) Riedel (L-mode)
• (16) Christiansen (L-mode)
• (17) Lackner-Gottardi (L-mode)
• (18) Neo-Kaye (L-mode)
• (19) Riedel (H-mode)
• (20) ITER H90-P amended (H-mode)
• (21) LHD (stellarator)
• (22) Gyro-reduced Bohm (stellarator)
• (23) Lackner-Gottardi (stellarator)
• (24) ITER-93H (H-mode)
• (25) OBSOLETE
• (26) ITER H-97P ELM-free (H-mode)
• (27) ITER H-97P ELMy (H-mode)
• (28) ITER-96P (=ITER-97L) (L-mode)
• (29) Valovic modified ELMy (H-mode)
• (30) Kaye PPPL April 98 (L-mode)
• (31) ITERH-PB98P(y) (H-mode)
• (32) IPB98(y) (H-mode)
• (33) IPB98(y,1) (H-mode)
• (34) IPB98(y,2) (H-mode)
• (35) IPB98(y,3) (H-mode)
• (36) IPB98(y,4) (H-mode)
• (37) ISS95 (stellarator)
• (38) ISS04 (stellarator)
• (39) DS03 (H-mode)
• (40) Murari et al non-power law (H-mode)
• (41) Petty 2008 (H-mode)
• (42) Lang et al. 2012 (H-mode)
• (43) Hubbard 2017 (I-mode) - nominal
• (44) Hubbard 2017 (I-mode) - lower bound
• (45) Hubbard 2017 (I-mode) - upper bound
• (46) NSTX (H-mode; Spherical tokamak)
• (47) NSTX-Petty08 Hybrid (H-mode)
• (48) NSTX gyro-Bohm (Buxton) (H-mode; Spherical tokamak)
• (49) Use input tauee_in

switch for plasma-first wall clearances:

• =0 use 10% of rminor
• =1 use input (scrapli and scraplo)

switch for plasma cross-sectional shape calculation:

• =0 use input kappa, triang to calculate 95% values
• =1 scale qlim, kappa, triang with aspect ratio (ST)
• =2 set kappa to the natural elongation value (Zohm ITER scaling), triang input
• =3 set kappa to the natural elongation value (Zohm ITER scaling), triang95 input
• =4 use input kappa95, triang95 to calculate separatrix values
• =5 use input kappa95, triang95 to calculate separatrix values based on MAST scaling (ST)
• =6 use input kappa, triang to calculate 95% values based on MAST scaling (ST)
• =7 use input kappa95, triang95 to calculate separatrix values based on fit to FIESTA (ST)
• =8 use input kappa, triang to calculate 95% values based on fit to FIESTA (ST)
• =9 set kappa to the natural elongation value, triang input
• =10 set kappa to maximum stable value at a given aspect ratio (2.6<A<3.6)), triang input (#1399)
• =11 set kappa Menard 2016 aspect-ratio-dependent scaling, triang input (#1439)

switch for spherical tokamak (ST) models:

• =0 use conventional aspect ratio models
• =1 use spherical tokamak models

switch for Spherical Tokamak PF models:

• =0 use Peng and Strickler (1986) model
• =1 use conventional aspect ratio model

switch for neutron wall load calculation:

• =1 use scaled plasma surface area
• =2 use first wall area directly

plasma separatrix elongation (calculated if ishape = 1-5, 7 or 9-10)

plasma elongation at 95% surface (calculated if ishape = 0-3, 6, or 8-10)

plasma elongation calculated as xarea/(pi.a^2)

Volume measure of plasma elongation

central electron density (/m3)

central ion density (/m3)

margin to vertical stability

central total plasma pressure (Pa)

Volume averaged plasma pressure (Pa)

branching ratio for DD -> T

Alpha power per volume just from plasma [MW/m3]

Alpha power per volume from plasma and beams [MW/m3]

Alpha power per volume to electrons [MW/m3]

alpha power escaping plasma and reaching first wall (MW)

alpha power per volume to ions (MW/m3)

Alpha power from only the plasma (MW)

Total alpha power from plasma and beams (MW)

alpha power from hot neutral beam ions (MW)

non-alpha charged particle fusion power (MW)

Total charged particle fusion power [MW]

Non-alpha charged particle fusion power per volume [MW/m3]

profile factor (= n-weighted T / average T)

radiation power from inner zone (MW)

total core radiation power per volume (MW/m3)

deuterium-deuterium fusion power (MW)

deuterium-helium3 fusion power (MW)

power to conducted to the divertor region (MW)

power conducted to the lower divertor region (calculated if i_single_null = 0) (MW)

power conducted to the upper divertor region (calculated if i_single_null = 0) (MW)

power conducted to the divertor with most load (calculated if i_single_null = 0) (MW)

Total deuterium-tritium fusion power, from plasma and beams [MW]

Deuterium-tritium fusion power, just from plasma [MW]

radiation power from outer zone (MW)

edge radiation power per volume (MW/m3)

internal plasma V-s

Nominal mean radiation load on inside surface of reactor (MW/m2)

ion/electron equilibration power per volume (MW/m3)

plasma current (A)

Neutron fusion power from just the plasma [MW]

Total neutron fusion power from plasma and beams [MW]

neutron fusion power per volume from beams and plasma (MW/m3)

neutron fusion power per volume just from plasma (MW/m3)

ohmic heating power (MW)

ohmic heating power per volume (MW/m3)

heating power (= transport loss power) (MW) used in confinement time calculation

fusion power (MW)

plasma poloidal perimeter (m)

total radiation power from inside LCFS (MW)

total radiation power per volume (MW/m3)

radiation power from SoL (MW)

Proton production rate [particles/m3/sec]

SOL radiation power (MW) (stellarator only)

synchrotron radiation power per volume (MW/m3)

switch for L-H mode power threshold scaling to use (see pthrmw for list)

L-H mode power threshold (MW) (chosen via ilhthresh, and enforced if constraint equation 15 is on)

L-H power threshold for various scalings (MW)

• =1 ITER 1996 scaling: nominal
• =2 ITER 1996 scaling: upper bound
• =3 ITER 1996 scaling: lower bound
• =4 ITER 1997 scaling: excluding elongation
• =5 ITER 1997 scaling: including elongation
• =6 Martin 2008 scaling: nominal
• =7 Martin 2008 scaling: 95% upper bound
• =8 Martin 2008 scaling: 95% lower bound
• =9 Snipes 2000 scaling: nominal
• =10 Snipes 2000 scaling: upper bound
• =11 Snipes 2000 scaling: lower bound
• =12 Snipes 2000 scaling (closed divertor): nominal
• =13 Snipes 2000 scaling (closed divertor): upper bound
• =14 Snipes 2000 scaling (closed divertor): lower bound
• =15 Hubbard et al. 2012 L-I threshold scaling: nominal
• =16 Hubbard et al. 2012 L-I threshold scaling: lower bound
• =17 Hubbard et al. 2012 L-I threshold scaling: upper bound
• =18 Hubbard et al. 2017 L-I threshold scaling
• =19 Martin 2008 aspect ratio corrected scaling: nominal
• =20 Martin 2008 aspect ratio corrected scaling: 95% upper bound
• =21 Martin 2008 aspect ratio corrected scaling: 95% lower bound

electron transport power (MW)

electron transport power per volume (MW/m3)

ion transport power (MW)

Total transport power from scaling law (MW)

ion transport power per volume (MW/m3)

Safety factor 'near' plasma edge (iteration variable 18) equal to q95 (unless i_plasma_current=2 (ST current scaling), in which case q = mean edge safety factor qbar)

safety factor on axis

safety factor at 95% surface

plasma fuelling rate (nucleus-pairs/s)

tauratio /1.0/ : ratio of He and pellet particle confinement times

lower limit for edge safety factor

cylindrical safety factor

SoL radiation fraction

Radiation fraction total = SoL + LCFS radiation / total power deposited in plasma

thermal alpha density/electron density (iteration variable 109)

Seeded protium density / electron density.

plasma normalised internal inductance (calculated from alphaj if iprofile=1)

plasma inductance (H)

plasma major radius (m) (iteration variable 3)

plasma minor radius (m)

hot beam density / n_e (iteration variable 7)

n_carbon / n_e

fuel burnup rate (reactions/second)

n_highZ / n_e

n_oxygen / n_e

neo-classical correction factor to rplas

plasma resistance (ohm)

plasma current resistive diffusion time (s)

plasma surface area

outboard plasma surface area

shape factor = plasma poloidal perimeter / (2.pi.rminor)

switch for single null / double null plasma:

• =0 for double null
• =1 for single null (diverted side down)

synchrotron wall reflectivity factor

electron energy confinement time (sec)

Input electron energy confinement time (sec) (isc=48 only)

global thermal energy confinement time (sec)

ion energy confinement time (sec)

alpha particle confinement time (sec)

volume averaged electron temperature (keV) (iteration variable 4)

central electron temperature (keV)

density weighted average electron temperature (keV)

volume averaged ion temperature (keV). N.B. calculated from te if tratio > 0.0

central ion temperature (keV)

density weighted average ion temperature (keV)

ion temperature / electron temperature(used to calculate ti if tratio > 0.0

plasma separatrix triangularity (calculated if ishape = 1, 3-5 or 7)

plasma triangularity at 95% surface (calculated if ishape = 0-2, 6, 8 or 9)

plasma volume (m3)

V-s needed during flat-top (heat + burn times) (Wb)

plasma/device midplane vertical shift - single null

internal and external plasma inductance V-s (Wb)

resistive losses in startup V-s (Wb)

total V-s needed (Wb)

average neutron wall load (MW/m2)

mass of fuel used per day (g)

plasma cross-sectional area (m2)

plasma effective charge

mass weighted plasma effective charge

allowable first wall/blanket neutron fluence (MW-yr/m2) (blktmodel=0)

allowable divertor heat fluence (MW-yr/m2)

blanket direct cost (M$)

total account 221 cost (M$) - first wall, blanket, shield, support structure and div plates

total account 222 cost (M$) - TF coils + PF coils

total capital cost including interest (M$)

fixed cost of superconducting cable ($/m)

cost of PF coil steel conduit/sheath ($/m)

cost of TF coil steel conduit/sheath ($/m)

current drive direct costs (M$)

total plant direct cost (M$)

Full power year lifetime of heating/current drive system (y)

Calendar year lifetime of heating/current drive system (y)

Total plant availability fraction; input if iavail=0

Total plant capacity factor

indirect cost factor (func of lsa) (cost model = 0)

cost of land (M$)

cost of electricity ($/MW-hr)

capital cost of electricity (m$/kW-hr)

'fuel' (including replaceable components) contribution to cost of electricity (m$/kW-hr)

operation and maintenance contribution to cost of electricity (m$/kW-hr)

plant construction cost (M$)

cost exponent for scaling in 2015 costs model

cost exponent for pebbles in 2015 costs model

cost scaling factor for buildings

cost scaling factor for land

cost scaling factor for TF coils

cost scaling factor for fwbs

cost scaling factor for remote handling

cost scaling factor for vacuum vessel

cost scaling factor for energy conversion system

cost scaling factor for remaining subsystems

Maintenance cost factor: first wall, blanket, shield, divertor

Maintenance cost factor: All other components except coils, vacuum vessel, thermal shield, cryostat, land

amortization factor (fixed charge factor) "A" (years)

Switch for cost model:

• =0 use $ 1990 PROCESS model
• =1 use $ 2014 Kovari model
• =2 use user-provided model

Switch for the centrepost lifetime constraint 0 : The CP full power year lifetime is set by the user via cplife_input 1 : The CP lifetime is equal to the divertor lifetime 2 : The CP lifetime is equal to the breeding blankets lifetime 3 : The CP lifetime is equal to the plant lifetime

owner cost factor

User input full power year lifetime of the centrepost (years) (i_cp_lifetime = 0)

Calculated full power year lifetime of centrepost (years)

Calculated calendar year lifetime of centrepost (years)

ST centrepost direct cost (M$)

allowable ST centrepost neutron fluence (MW-yr/m2)

reactor core costs (categories 221, 222 and 223)

allowance for site costs (M$)

cost of turbine building (M$)

proportion of constructed cost required for decommissioning fund

diff between borrowing and saving interest rates

divertor direct cost (M$)

Full power lifetime of divertor (y)

Calendar year lifetime of divertor (y)

period prior to the end of the plant life that the decommissioning fund is used (years)

average cost of money for construction of plant assuming design/construction time of six years

average cost of money for replaceable components assuming lead time for these of two years

fraction of current drive cost treated as fuel (if ifueltyp = 1)

project contingency factor

fixed charge rate during construction

multiplier for Nth of a kind costs

first wall cost (M$)

Switch for plant availability model:

• =0 use input value for cfactr
• =1 calculate cfactr using Taylor and Ward 1999 model
• =2 calculate cfactr using new (2015) model
• =3 calculate cfactr using ST model

Switch for fw/blanket lifetime calculation in availability module:

• =0 use neutron fluence model
• =1 use fusion power model (DEMO only)

Allowable DPA from DEMO fw/blanket lifetime calculation in availability module

Number of fusion cycles to reach allowable DPA from DEMO fw/blanket lifetime calculation

Minimum availability (constraint equation 61)

Unit cost for tokamak complex buildings, including building and site services ($/m3)

Unit cost for unshielded non-active buildings ($/m3)

F-value for minimum availability (constraint equation 61)

Number of remote handling systems (1-10)

c parameter, which determines the temperature margin at which magnet lifetime starts to decline

Divertor probability of failure (per op day)

Divertor unplanned maintenance time (years)

Reference value for cycle cycle life of divertor

The cycle when the divertor fails with 100% probability

Reference value for cycle life of blanket

The cycle when the blanket fails with 100% probability

Fwbs probability of failure (per op day)

Fwbs unplanned maintenance time (years)

Vacuum system pump redundancy level (%)

Number of redundant vacuum pumps

Operational time (yrs)

time taken to replace blanket (y) (iavail=1)

time taken to replace both blanket and divertor (y) (iavail=1)

time taken to replace divertor (y) (iavail=1)

unplanned unavailability factor for balance of plant (iavail=1)

unplanned unavailability factor for current drive (iavail=1)

unplanned unavailability factor for divertor (iavail=1)

unplanned unavailability factor for fuel system (iavail=1)

unplanned unavailability factor for first wall (iavail=1)

unplanned unavailability factor for magnets (iavail=1)

unplanned unavailability factor for vessel (iavail=1)

Switch for fuel type:

• =2 treat initial blanket, divertor, first wall as capital costs. Treat all later items and fraction fcdfuel of CD equipment as fuel costs
• =1 treat blanket divertor, first wall and fraction fcdfuel of CD equipment as fuel cost
• =0 treat these as capital cost

Switch for net electric power calculation:

• =0 scale so that always > 0
• =1 let go < 0 (no c-o-e)

Switch for net electric power and cost of electricity calculations:

• =0 do not calculate MW(electric) or c-o-e
• =1 calculate MW(electric) and c-o-e

Level of safety assurance switch (generally, use 3 or 4):

• =1 truly passively safe plant
• =2,3 in-between
• =4 like current fission plant

interest portion of capital cost (M$)

Switch for costs output:

• =0 do not write cost-related outputs to file
• =1 write cost-related outputs to file

effective cost of money in constant dollars

ratio of additional HCD power for start-up to flat-top operational requirements

cost associated with additional HCD system power required on start-up ($)

Switch for superconductor cost model:

• =0 use $/kg
• =1 use $/kAm

Full power year plant lifetime (years)

Maintenance time for replacing CP (years) (iavail = 3)

User-input CP unplanned unavailability (iavail = 3)

unit cost for administration buildings (M$/m3)

unit cost for aux facility power equipment ($)

unit cost for aux heat transport equipment ($/W**exphts)

unit cost of auxiliary transformer ($/kVA)

unit cost for blanket beryllium ($/kg)

unit cost for breeder material ($/kg) (blktmodel>0)

unit cost for blanket lithium ($/kg) (30% Li6)

unit cost for blanket Li_2O ($/kg)

unit cost for blanket Li-Pb ($/kg) (30% Li6)

unit cost for blanket stainless steel ($/kg)

unit cost for blanket vanadium ($/kg)

vacuum system backing pump cost ($)

cost of aluminium bus for TF coil ($/A-m)

cost of superconductor case ($/kg)

unit cost for control buildings (M$/m3)

cost of high strength tapered copper ($/kg)

cost of TF outboard leg plate coils ($/kg)

vacuum system cryopump cost ($)

unit cost for cryogenic building (M$/vol)

heat transport system cryoplant costs ($/W**expcry)

unit cost for vacuum vessel ($/kg)

unit cost for copper in superconducting cable ($/kg)

cost per 8 MW diesel generator ($)

cost of divertor blade ($)

detritiation, air cleanup cost ($/10000m3/hr)

vacuum system duct cost ($/m)

ECH system cost ($/W)

unit cost for electrical equipment building (M$/m3)

MGF (motor-generator flywheel) cost factor ($/MVA**0.8)

MGF (motor-generator flywheel) cost factor ($/MJ**0.8)

cost of fuelling system ($)

outer PF coil fence support cost ($/kg)

cost of 60g/day tritium processing unit ($)

unit cost of D-T fuel (M$/year/1200MW)

first wall armour cost ($/m2)

first wall passive stabiliser cost ($)

first wall structure cost ($/m2)

cost of reactor structure ($/kg)

cost of helium-3 ($/kg)

cost of heat rejection system ($)

cost of heat transport system equipment per loop ($/W); dependent on coolant type (coolwh)

cost of instrumentation, control & diagnostics ($)

ICH system cost ($/W)

superconductor intercoil structure cost ($/kg)

lower hybrid system cost ($/W)

low voltage system cost ($/kVA)

unit cost for reactor maintenance building (M$/m3)

cost of maintenance equipment ($)

miscellaneous plant allowance ($)

NBI system cost ($/W)

cost of nuclear building ventilation ($/m3)

annual cost of operation and maintenance (M$/year/1200MW**0.5)

penetration shield cost ($/kg)

cost of PF coil buses ($/kA-m)

cost of PF coil DC breakers ($/MVA**0.7)

cost of PF burn power supplies ($/kW**0.7)

cost of PF coil AC breakers ($/circuit)

cost factor for dump resistors ($/MJ)

cost of PF instrumentation and control ($/channel)

cost of PF coil pulsed power supplies ($/MVA)

primary heat transport cost ($/W**exphts)

cost of primary power transformers ($/kVA**0.9)

cost of reactor building (M$/m3)

cost of superconductor ($/kg)

cost of superconductor ($/kA m) at 6.4 T, 4.2 K

cost of shops and warehouses (M$/m3)

cost of shield structural steel ($/kg)

switchyard equipment costs ($)

cost of TF coil breakers ($/W**0.7)

cost of TF coil bus ($/kg)

cost of TF coil dump resistors ($/J)

additional cost of TF coil dump resistors ($/coil)

cost of TF coil instrumentation and control ($/coil/30)

cost of TF coil power supplies ($/W**0.7)

cost of TF coil slow dump switches ($/A)

cost of turbomolecular pump ($)

cost of tritium building ($/m3)

cost of turbine plant equipment ($) (dependent on coolant type coolwh)

vacuum system valve cost ($)

vacuum duct shield cost ($/kg)

vacuum system instrumentation and control cost ($)

cost of PF coil superconductor windings ($/m)

cost of TF coil superconductor windings ($/m)

cost of active assembly shop ($/m3)

cost of waste disposal (M$/y/1200MW)

error_id : identifier for final message encountered

error_status : overall status flag for a run; on exit:

• 0 all okay
• 1 informational messages have been encountered
• 2 warning (non-fatal) messages have been encountered
• 3 severe (fatal) errors have occurred

thickness of REBCO layer in tape (m) (iteration variable 138)

thickness of copper layer in tape (m) (iteration variable 139)

thickness of Hastelloy layer in tape (m)

Mean width of tape (m)

thickness of tape, inc. all layers (hts, copper, substrate, etc.) (m)

Outer diameter of CroCo strand (m)

Inner diameter of CroCo copper tube (m)

Thickness of CroCo copper tube (m) (iteration variable 158)

residual resistivity ratio copper in TF superconducting cable

TF coil current / copper area (A/m2)

Maximum TF coil current / copper area (A/m2)

f-value for constraint 75: TF coil current / copper area < copperA_m2_max

CS coil current / copper area (A/m2) (sweep variable 61)

Maximum CS coil current / copper area (A/m2)

f-value for constraint 88: CS coil current / copper area < copperA_m2_max

Index of impurity to be iterated for Reinke divertor detachment criterion

Connection length factor L|| = lhat qstar R for Reinke criterion, default value from Post et al. 1995 J. Nucl. Mat. 220-2 1014

Minimum impurity fraction necessary for detachment. This is the impurity at the SOL/Div.

Actual impurity fraction of divertor impurity (impvardiv) in the SoL (taking impurity_enrichment into account) (iteration variable 148)

Switch for Reinke criterion H/I mode:

• =0 H-mode
• =1 I-mode

ambient air temperature (degrees Celsius)

water temperature (degrees Celsius)

wind speed (m/s)

density of water (kg/m3) for simplicity, set to static value applicable to water at 21 degC

latent heat of vaporization (J/kg) for simplicity, set to static value applicable at 1 atm (100 kPa) air pressure

volumetric heat of vaporization (J/m3)

evaporation ratio: ratio of the heat used to evaporate water to the total heat discharged through the tower

evaporated volume of water (m3)

input waste (heat) energy cooled per evaporated volume (J/m3)

volume evaporated by units of heat energy (m3/MJ)

total volume of water used in cooling tower (m3)

total volume of water used in recirculating system (m3)

total volume of water used in once-through system (m3)

intercoil structure mass (kg)

gravity support structure for TF coil, PF coil and intercoil support systems (kg)

total mass of components at cryogenic temperatures (kg)

PF coil outer support fence mass (kg)

reactor core gravity support mass (kg)

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