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PROCESS Variable Descriptions

Introduction

Variables marked with an * are private variables and cannot be accessed outside of their Fortran module scope.

The PROCESS convention on inputs dictates that module variables which can be set from the input file should be initialised in a routine called init_mod where mod is replaced with the Fortran module name. However, some variables can also be initialised here too and will register as inputs when they are not.

Output types signify that these module variables are set by models. This does necessarily mean an "output" will appear in the MFile/Outfile.

blanket_library

Name Type Datatype Default Value Description
volshldi Output real -

Volume of inboard and outboard shield (m3)
volshldo Output real -

Volume of inboard and outboard shield (m3)
volvvi Output real -

Volume of inboard and outboard Vacuum Vessel (m3)
volvvo Output real -

Volume of inboard and outboard Vacuum Vessel (m3)
hcryopf Output real -

Clearance between uppermost PF coil and cryostat lid (m)
vfblkti Output real -

Inboard/outboard void fraction of blanket
vfblkto Output real -

Inboard/outboard void fraction of blanket
bldepti Output real -

Inboard/outboard blanket coolant channel length (radial direction) (m)
bldepto Output real -

Inboard/outboard blanket coolant channel length (radial direction) (m)
blwidti Output real -

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

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

Inboard/outboard blanket segment poloidal length (m)
bllengo Output real -

Inboard/outboard blanket segment poloidal length (m)
bzfllengi Output real -

Inboard/outboard primary blanket flow lengths (m)
bzfllengo Output real -

Inboard/outboard primary blanket flow lengths (m)
bzfllengi_liq Output real -

Inboard/outboard secondary blanket flow lengths (m)
bzfllengo_liq Output real -

Inboard/outboard secondary blanket flow lengths (m)
pnucfwi Output real -

Inboard/outboard first wall nuclear heating (MW)
pnucfwo Output real -

Inboard/outboard first wall nuclear heating (MW)
tpeakfwi Output real -

Inboard/outboard first wall peak temperature (K)
tpeakfwo Output real -

Inboard/outboard first wall peak temperature (K)
mffwi Output real -

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

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

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

Inboard/utboard total number of pipes
npfwo Output real -

Inboard/utboard total number of pipes
mffwpi Output real -

Inboard/outboard mass flow rate per coolant pipe (kg/s)
mffwpo Output real -

Inboard/outboard mass flow rate per coolant pipe (kg/s)
pnucblkti Output real -

Neutron power deposited inboard/outboard blanket blanket (MW)
pnucblkto Output real -

Neutron power deposited inboard/outboard blanket blanket (MW)
mfblkti Output real -

Inboard/outboard blanket mass flow rate for coolant (kg/s)
mfblkto Output real -

Inboard/outboard blanket mass flow rate for coolant (kg/s)
mfblkt Output real -

Inboard/outboard blanket mass flow rate for coolant (kg/s)
mfblkti_liq Output real -

Inboard/outboard blanket mass flow rate for liquid breeder (kg/s)
mfblkto_liq Output real -

Inboard/outboard blanket mass flow rate for liquid breeder (kg/s)
mfblkt_liq Output real -

Inboard/outboard blanket mass flow rate for liquid breeder (kg/s)
mftotal Output real -

Total mass flow rate for coolant (kg/s)
npblkti Output real -

Inboard/outboard total num of pipes
npblkto Output real -

Inboard/outboard total num of pipes
mfblktpi Output real -

Inboard/outboard mass flow rate per coolant pipe (kg/s)
mfblktpo Output real -

Inboard/outboard mass flow rate per coolant pipe (kg/s)
velblkti Output real -

Inboard/outboard coolant velocity in blanket (m/s)
velblkto Output real -

Inboard/outboard coolant velocity in blanket (m/s)
htpmw_fwi Output real -

Inboard/outboard first wall pumping power (MW)
htpmw_fwo Output real -

Inboard/outboard first wall pumping power (MW)
htpmw_blkti Output real -

Inboard/outboard blanket pumping power (MW)
htpmw_blkto Output real -

Inboard/outboard blanket pumping power (MW)
htpmw_fw_blkti Output real -

Inboard/outboard fw and blanket pumping power (MW)
htpmw_fw_blkto Output real -

Inboard/outboard fw and blanket pumping power (MW)
hblnkt Output real -

Blanket internal half-height (m)
hshld Output real -

Shield internal half-height (m)
hvv Output real -

Vacuum vessel internal half-height (m)
icomponent Output integer -

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

physics_module

Name Type Datatype Default Value Description
iscz Output integer -
err242 Output integer -
err243 Output integer -
rad_fraction_lcfs Output real -
total_plasma_internal_energy Output real -
total_loss_power Output real -
total_energy_conf_time Output real -
ptarmw Output real -
lambdaio Output real -
drsep Output real -
fio Output real -
fli Output real -
flo Output real -
fui Output real -
fuo Output real -
plimw Output real -
plomw Output real -
puimw Output real -
puomw Output real -
rho_star Output real -
nu_star Output real -
beta_mcdonald Output real -
itart_r Output real -
first_call Input integer 1

pfcoil_variables

Name Type Datatype Default Value Description
ngrpmx Parameter integer 10

maximum number of groups of PF coils
nclsmx Parameter integer 2

maximum number of PF coils in a given group
nptsmx Parameter integer 32

maximum number of points across the midplane of the plasma at which the field from the PF coils is fixed
nfixmx Parameter integer 64

maximum number of fixed current PF coils
ngc Parameter integer ngrpmx*nclsmx

maximum total number of coils across all groups
ngc2 Parameter integer ngc+2

new variable to include 2 additional circuits: plasma and central solenoid
alfapf Input real 5e-10

smoothing parameter used in PF coil current calculation at the beginning of pulse (BoP)
alstroh Input real 400000000.0

allowable hoop stress in Central Solenoid structural material (Pa)
i_cs_stress Output integer -

Switch for CS stress calculation:

  • =0 Hoop stress only
  • =1 Hoop + Axial stress
areaoh Output real -

Central solenoid vertical cross-sectional area (m2)
a_oh_turn Output real -

Central solenoid (OH) trun cross-sectional area (m2)
awpoh Output real -

central solenoid conductor+void area with area of steel subtracted (m2)
bmaxoh Output real -

maximum field in central solenoid at end of flat-top (EoF) (T)
bmaxoh0 Output real -

maximum field in central solenoid at beginning of pulse (T)
bpf Output real -

peak field at coil i (T)
ccl0_ma Output real -

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

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

Central solenoid overall current density at beginning of pulse (A/m2)
coheof Input real 18500000.0

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

current per turn in coil i at time j (A)
cptdin Input real [40000. 40000. 40000. 40000. 40000. 40000. 40000. 40000. 40000. 40000. 40000. 40000. 40000. 40000. 40000. 40000. 40000. 40000. 40000. 40000. 40000. 40000.]

peak current per turn input for PF coil i (A)
curpfb Output real -

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

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

PF coil current array, at end of pulse (MA) Indexed by coil number, not group number
etapsu Input real 0.9

Efficiency of transfer of PF stored energy into or out of storage.
fcohbof Output real -

ratio of central solenoid overall current density at beginning of flat-top / end of flat-top
fcohbop Input real 0.9

ratio of central solenoid overall current density at beginning of pulse / end of flat-top (iteration variable 41)
fcuohsu Input real 0.7

copper fraction of strand in central solenoid
fcupfsu Input real 0.69

copper fraction of cable conductor (PF coils)
fvssu Input real 1.0

F-value for constraint equation 51
ipfloc Input integer [2 2 3 0 0 0 0 0 0 0]

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)
ipfres Output integer -

switch for PF & CS coil conductor type:

  • =0 superconducting PF coils
  • =1 resistive PF coils
itr_sum Output real -

total sum of I x turns x radius for all PF coils and CS (Am)
isumatoh Input integer 1

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
isumatpf Input integer 1

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
j_crit_str_cs Output real -

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

superconductor strand critical current density under operating conditions in PF coils (A/m2). Necessary for the cost calculation in $/kA m
i_pf_current Input integer 1

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)
i_sup_pf_shape Output integer -

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
jscoh_bop Output real -

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

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

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

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

number of PF circuits (including central solenoid and plasma)
ncls Input integer [1 1 2 0 0 0 0 0 0 0 0 0]

number of PF coils in group j
nfxfh Input integer 7

number of filaments the top and bottom of the central solenoid should be broken into during scaling (5 - 10 is good)
ngrp Input integer 3

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

number of PF coils (excluding the central solenoid) + 1
ohhghf Input real 0.71

Central solenoid height / TF coil internal height
oh_steel_frac Input real 0.5

central solenoid steel fraction (iteration variable 122)
pf_current_safety_factor Input real 1.0

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

steel case thickness for PF coil i (m)
pfclres Input real 2.5e-08

PF coil resistivity (if ipfres=1) (Ohm-m)
rhopfbus Input real 3.93e-08

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

mass of heaviest PF coil (tonnes)
pfrmax Output real -

radius of largest PF coil (m)
pfwpmw Output real -

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

central solenoid resistive power during flattop (W)
powpfres Output real -

total PF coil resistive losses during flattop (W)
ra Output real -

inner radius of coil i (m)
rb Output real -

outer radius of coil i (m)
ric Output real -

peak current in coil i (MA-turns)
rjconpf Input real [30000000. 30000000. 30000000. 30000000. 30000000. 30000000. 30000000. 30000000. 30000000. 30000000. 30000000. 30000000. 30000000. 30000000. 30000000. 30000000. 30000000. 30000000. 30000000. 30000000. 30000000. 30000000.]

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

allowable central solenoid current density at end of flat-top (A/m2)
rjohc0 Output real -

allowable central solenoid current density at beginning of pulse (A/m2)
rjpfalw Output real -

allowable winding pack current density of PF coil i (A/m2)
rohc Output real -

radius to the centre of the central solenoid (m)
routr Input real 1.5

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

radius of PF coil i (m)
rpf1 Output real -

offset (m) of radial position of ipfloc=1 PF coils from being directly above the central solenoid
rpf2 Input real -1.63

offset (m) of radial position of ipfloc=2 PF coils from being at rmajor (offset = rpf2triangrminor)
rref Input real [7. 7. 7. 7. 7. 7. 7. 7. 7. 7.]

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)
s_tresca_oh Output real -

Maximum shear stress (Tresca criterion) coils/central solenoid [MPa]
sigpfcalw Input real 500.0

maximum permissible tensile stress (MPa) in steel coil cases for superconducting PF coils (ipfres=0)
sigpfcf Input real 1.0

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

mutual inductance matrix (H)
tmargoh Output real -

Central solenoid temperature margin (K)
turns Output real -

number of turns in PF coil i
vf Input real [0.3 0.3 0.3 0.3 0.3 0.3 0.3 0.3 0.3 0.3 0.3 0.3 0.3 0.3 0.3 0.3 0.3 0.3 0.3 0.3 0.3 0.3]

winding pack void fraction of PF coil i for coolant
vfohc Input real 0.3

void fraction of central solenoid conductor for coolant
vsbn Output real -

total flux swing available for burn (Wb)
vsefbn Output real -

flux swing from PF coils for burn (Wb)
vsefsu Output real -

flux swing from PF coils for startup (Wb)
vseft Output real -

total flux swing from PF coils (Wb)
vsoh Output real -

total flux swing from the central solenoid (Wb)
vsohbn Output real -

central solenoid flux swing for burn (Wb)
vsohsu Output real -

central solenoid flux swing for startup (Wb)
vssu Output real -

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

total flux swing for pulse (Wb)
waves Output real -

used in current waveform of PF coils/central solenoid
whtpf Output real -

total mass of the PF coil conductor (kg)
whtpfs Output real -

total mass of the PF coil structure (kg)
wtc Output real -

conductor mass for PF coil i (kg)
wts Output real -

structure mass for PF coil i (kg)
zh Output real -

upper point of PF coil i (m)
zl Output real -

lower point of PF coil i (m)
zpf Output real -

z (height) location of PF coil i (m)
zref Input real [3.6 1.2 2.5 1. 1. 1. 1. 1. 1. 1. ]

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
  • for groups j with ipfloc(j) = 4; zref(j) = ratio of height of coil group j to plasma minor radius
    		•
    bmaxcs_lim Input real 13.0

    Central solenoid max field limit [T]
    fbmaxcs Input real 1.0

    F-value for CS mmax field (cons. 79, itvar 149)
    ld_ratio_cst Input real 3.0

    Ratio of CS coil turn conduit length to depth
    l_cond_cst Output real -

    Length of CS of CS coil turn conduit
    d_cond_cst Output real -

    Depth/width of CS of CS coil turn conduit
    r_out_cst Input real 0.003

    Length of CS of CS coil turn conduit length
    r_in_cst Output real -

    Length of CS of CS coil turn conduit length

    global_variables

    Name Type Datatype Default Value Description
    icase Input character b'Steady-state tokamak model '

    power plant type
    runtitle Input character b"Run Title (change this line using input variable 'runtitle') "

    short descriptive title for the run
    verbose Output integer -

    switch for turning on/off diagnostic messages

    • =0 turn off diagnostics
    • =1 turn on diagnostics
    run_tests Output integer -

    turns on built-in tests if set to 1
    maxcal Input integer 200

    maximum number of VMCON iterations
    fileprefix Input character b' '

    input file prefix
    output_prefix Input character b' '

    output file prefix
    xlabel Input character b' '

    scan parameter description label
    vlabel Input character b' '

    scan value name label
    xlabel_2 Input character b' '

    scan parameter description label (2nd dimension)
    vlabel_2 Input character b' '

    scan value name label (2nd dimension)
    iscan_global Output integer -

    Makes iscan available globally.
    convergence_parameter Output real -

    VMCON convergence parameter "sum"

    build_variables

    Name Type Datatype Default Value Description
    aplasmin Input real 0.25

    minimum minor radius (m)
    available_radial_space Output real -

    Minimal radial space between plasma and coils (m)
    blarea Output real -

    blanket total surface area (m2)
    blareaib Output real -

    inboard blanket surface area (m2)
    blareaob Output real -

    outboard blanket surface area (m2)
    blbmith Input real 0.17

    inboard blanket box manifold thickness (m) (blktmodel>0)
    blbmoth Input real 0.27

    outboard blanket box manifold thickness (m) (blktmodel>0)
    blbpith Input real 0.3

    inboard blanket base plate thickness (m) (blktmodel>0)
    blbpoth Input real 0.35

    outboard blanket base plate thickness (m) (blktmodel>0)
    blbuith Input real 0.365

    inboard blanket breeding zone thickness (m) (blktmodel>0) (iteration variable 90)
    blbuoth Input real 0.465

    outboard blanket breeding zone thickness (m) (blktmodel>0) (iteration variable 91)
    blnkith Input real 0.115

    inboard blanket thickness (m); (calculated if blktmodel>0) (=0.0 if iblnkith=0)
    blnkoth Input real 0.235

    outboard blanket thickness (m); calculated if blktmodel>0
    blnktth Output real -

    top blanket thickness (m), = mean of inboard and outboard blanket thicknesses
    bore Input real 1.42

    central solenoid inboard radius (m) (iteration variable 29)
    clhsf Input real 4.268

    cryostat lid height scaling factor (tokamaks)
    ddwex Input real 0.07

    cryostat thickness (m)
    d_vv_in Input real 0.07

    vacuum vessel inboard thickness (TF coil / shield) (m)
    d_vv_out Input real 0.07

    vacuum vessel outboard thickness (TF coil / shield) (m)
    d_vv_top Input real 0.07

    vacuum vessel topside thickness (TF coil / shield) (m) (= d_vv_bot if double-null)
    d_vv_bot Input real 0.07

    vacuum vessel underside thickness (TF coil / shield) (m)
    f_avspace Input real 1.0

    F-value for stellarator radial space check (constraint equation 83)
    fcspc Input real 0.6

    Fraction of space occupied by CS pre-compression structure
    fseppc Input real 350000000.0

    Separation force in CS coil pre-compression structure
    fwarea Output real -

    first wall total surface area (m2)
    fwareaib Output real -

    inboard first wall surface area (m2)
    fwareaob Output real -

    outboard first wall surface area (m2)
    fwith Output real -

    inboard first wall thickness, initial estimate as calculated (m)
    fwoth Output real -

    outboard first wall thickness, initial estimate as calculated (m)
    gapds Input real 0.155

    gap between inboard vacuum vessel and thermal shield (m) (iteration variable 61)
    gapoh Input real 0.08

    gap between central solenoid and TF coil (m) (iteration variable 42)
    gapomin Input real 0.234

    minimum gap between outboard vacuum vessel and TF coil (m) (iteration variable 31)
    gapsto Output real -

    gap between outboard vacuum vessel and TF coil (m)
    hmax Output real -

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

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

    height to top of (upper) TF coil leg (m)
    hr1 Output real -

    half-height of TF coil inboard leg straight section (m)
    iohcl Input integer 1

    Switch for existence of central solenoid:

    • =0 central solenoid not present
    • =1 central solenoid exists
    iprecomp Input integer 1

    Switch for existence of central solenoid pre-compression structure:

    • =0 no pre-compression structure
    • =1 calculated pre-compression structure
    tf_in_cs Output integer -

    Switch for placing the TF coil inside the CS

    • = 0 TF coil is outside the CS (default)
    • = 1 TF coil is inside the CS
    ohcth Input real 0.811

    Central solenoid thickness (m) (iteration variable 16)
    precomp Output real -

    CS coil precompression structure thickness (m)
    rbld Output real -

    sum of thicknesses to the major radius (m)
    required_radial_space Output real -

    Required space between coil and plasma for blanket shield wall etc (m)
    rinboard Input real 0.651

    plasma inboard radius (m) (consistency equation 29)
    rsldi Output real -

    radius to inboard shield (inside point) (m)
    rsldo Output real -

    radius to outboard shield (outside point) (m)
    r_vv_inboard_out Output real -

    Radial plasma facing side position of inboard vacuum vessel [m]
    r_sh_inboard_in Output real -

    Radial inner side position of inboard neutronic shield [m]
    r_sh_inboard_out Output real -

    Radial plasma facing side position of inboard neutronic shield [m]
    r_tf_inboard_in Output real -

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

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

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

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

    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
    r_cp_top Output real -

    Top outer radius of the centropost (ST only) (m)
    f_r_cp Input real 1.4

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

    TF coil horizontal inner bore (m)
    dh_tf_inner_bore Output real -

    TF coil vertical inner bore (m)
    scrapli Input real 0.14

    Gap between plasma and first wall, inboard side (m) (if iscrp=1) Iteration variable: ixc = 73 Scan variable: nsweep = 58
    scraplo Input real 0.15

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

    shield total surface area (m2)
    shareaib Output real -

    inboard shield surface area (m2)
    shareaob Output real -

    outboard shield surface area (m2)
    shldith Input real 0.69

    inboard shield thickness (m) (iteration variable 93)
    shldlth Input real 0.7

    lower (under divertor) shield thickness (m)
    shldoth Input real 1.05

    outboard shield thickness (m) (iteration variable 94)
    shldtth Input real 0.6

    upper/lower shield thickness (m); calculated if blktmodel > 0 (= shldlth if double-null)
    sigallpc Input real 300000000.0

    allowable stress in CSpre-compression structure (Pa)
    tfcth Output real -

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

    vertical distance between centre of TF coils and centre of plasma (m)
    tfootfi Input real 1.19

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

    Outboard TF coil thickness (m)
    tftsgap Input real 0.05

    Minimum metal-to-metal gap between TF coil and thermal shield (m)
    thshield_ib Input real 0.05

    TF-VV thermal shield thickness, inboard (m)
    thshield_ob Input real 0.05

    TF-VV thermal shield thickness, outboard (m)
    thshield_vb Input real 0.05

    TF-VV thermal shield thickness, vertical build (m)
    vgap_vv_thermalshield Input real 0.163

    vertical gap between vacuum vessel and thermal shields (m)
    vgap_xpoint_divertor Output real -

    vertical gap between x-point and divertor (m) (if = 0, it is calculated)
    vgaptop Input real 0.6

    vertical gap between top of plasma and first wall (m) (= vgap_xpoint_divertor if double-null)
    vvblgap Input real 0.05

    gap between vacuum vessel and blanket (m)
    plleni Input real 1.0

    length of inboard divertor plate (m)
    plleno Input real 1.0

    length of outboard divertor plate (m)
    plsepi Input real 1.0

    poloidal length, x-point to inboard strike point (m)
    plsepo Input real 1.5

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

    outboard strike point radius (m)

    heat_transport_variables

    Name Type Datatype Default Value Description
    baseel Input real 5000000.0

    base plant electric load (W)
    crypmw Output real -

    cryogenic plant power (MW)
    crypmw_max Input real 50.0

    Maximum cryogenic plant power (MW) Constraint equation icc = 87 Scan variable nwseep = 56
    f_crypmw Input real 1.0

    f-value for maximum cryogenic plant power Iteration variable ixc = 164 Constraint equation icc = 87
    etatf Input real 0.9

    AC to resistive power conversion for TF coils
    etath Input real 0.35

    thermal to electric conversion efficiency if secondary_cycle=2; otherwise calculated.
    etath_liq Input real 0.35
    fachtmw Output real -

    facility heat removal (MW)
    fcsht Output real -

    total baseline power required at all times (MW)
    fgrosbop Output real -

    scaled fraction of gross power to balance-of-plant
    fmgdmw Output real -

    power to mgf (motor-generator flywheel) units (MW) (ignored if iscenr=2)
    fpumpblkt Input real 0.005

    fraction of total blanket thermal power required to drive the blanket coolant pumps (default assumes water coolant) (secondary_cycle=0)
    fpumpdiv Input real 0.005

    fraction of total divertor thermal power required to drive the divertor coolant pumps (default assumes water coolant)
    fpumpfw Input real 0.005

    fraction of total first wall thermal power required to drive the FW coolant pumps (default assumes water coolant) (secondary_cycle=0)
    fpumpshld Input real 0.005

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

    Minimum total electrical power for primary coolant pumps (MW) (NOT RECOMMENDED)
    helpow Output real -

    Heat removal at cryogenic temperature tmpcry (W)
    helpow_cryal Output real -

    Heat removal at cryogenic temperature tcoolin (W)
    htpmw Output real -

    heat transport system electrical pump power (MW)
    htpmw_blkt Output real -

    blanket primary coolant mechanical pumping power (MW)
    htpmw_blkt_liq Output real -

    blanket secondary coolant mechanical pumping power (MW)
    htpmw_blkt_tot Output real -

    blanket primary + secondary coolant mechanical pumping power (MW)
    htpmw_div Output real -

    divertor coolant mechanical pumping power (MW)
    htpmw_fw Output real -

    first wall coolant mechanical pumping power (MW)
    htpmw_shld Output real -

    shield and vacuum vessel coolant mechanical pumping power (MW)
    htpsecmw Output real -

    Waste power lost from primary coolant pumps (MW)
    ipowerflow Input integer 1

    switch for power flow model:

    • =0 pre-2014 version
    • =1 comprehensive 2014 model
    iprimshld Input integer 1

    Switch for shield thermal power destiny:

    • =0 does not contribute to energy generation cycle
    • =1 contributes to energy generation cycle
    nphx Output integer -

    number of primary heat exchangers
    pacpmw Output real -

    total pulsed power system load (MW)
    peakmva Output real -

    peak MVA requirement
    pfwdiv Output real -

    heat removal from first wall/divertor (MW)
    pgrossmw Output real -

    gross electric power (MW)
    pinjht Output real -

    power dissipated in heating and current drive system (MW)
    pinjmax Input real 120.0

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

    injector wall plug power (MW)
    pinjwpfix Output real -

    secondary injector wall plug power (MW)
    pnetelmw Output real -

    net electric power (MW)
    precircmw Output real -

    recirculating electric power (MW)
    priheat Output real -

    total thermal power removed from fusion core (MW)
    psecdiv Output real -

    Low-grade heat lost in divertor (MW)
    psechcd Output real -

    Low-grade heat lost into HCD apparatus (MW)
    psechtmw Output real -

    Low-grade heat (MW)
    pseclossmw Output real -

    Low-grade heat (VV + lost)(MW)
    psecshld Output real -

    Low-grade heat deposited in shield (MW)
    pthermmw Output real -

    High-grade heat useful for electric production (MW)
    pwpm2 Input real 150.0

    base AC power requirement per unit floor area (W/m2)
    tfacpd Output real -

    total steady state TF coil AC power demand (MW)
    tlvpmw Output real -

    estimate of total low voltage power (MW)
    trithtmw Input real 15.0

    power required for tritium processing (MW)
    tturb Output real -

    coolant temperature at turbine inlet (K) (secondary_cycle = 3,4)
    vachtmw Input real 0.5

    vacuum pump power (MW)

    vacuum_variables

    Name Type Datatype Default Value Description
    vacuum_model Input character b'old '

    switch for vacuum pumping model:

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

    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')
    ntype Input integer 1

    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)
    nvduct Output integer -

    number of ducts (torus to pumps)
    dlscal Output real -

    vacuum system duct length scaling
    pbase Input real 0.0005

    base pressure during dwell before gas pre-fill(Pa)
    prdiv Input real 0.36

    divertor chamber pressure during burn (Pa)
    pumptp Input real 1.2155e+22

    Pump throughput (molecules/s) (default is ITER value)
    rat Input real 1.3e-08

    plasma chamber wall outgassing rate (Pa-m/s)
    tn Input real 300.0

    neutral gas temperature in chamber (K)
    vacdshm Output real -

    mass of vacuum duct shield (kg)
    vcdimax Output real -

    diameter of duct passage (m)
    vpumpn Output integer -

    number of high vacuum pumps
    dwell_pump Output integer -

    switch for dwell pumping options:

    • =0 pumping only during tdwell
    • =1 pumping only during tramp
    • =2 pumping during tdwell + tramp
    pumpareafraction Input real 0.0203

    area of one pumping port as a fraction of plasma surface area
    pumpspeedmax Input real 27.3

    maximum pumping speed per unit area for deuterium & tritium, molecular flow
    pumpspeedfactor Input real 0.167

    effective pumping speed reduction factor due to duct impedance
    initialpressure Input real 1.0

    initial neutral pressure at the beginning of the dwell phase (Pa)
    outgasindex Input real 1.0

    outgassing decay index
    outgasfactor Input real 0.0235

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

    dcll_module

    Name Type Datatype Default Value Description
    r_fci Output real -

    Radial BZ thickness [m]
    r_backwall Output real -

    Radial BZ thickness [m]
    bz_r_ib Output real -

    Structure/coolant compositional fractions
    bz_r_ob Output real -

    Structure/coolant compositional fractions
    f_vol_stff_plates Output real -

    MF/BSS compositional fractions
    f_vol_stl_bz_struct Output real -

    MF/BSS compositional fractions
    f_vol_stl_back_wall Output real -

    MF/BSS compositional fractions
    f_vol_stl_fw Output real -

    MF/BSS compositional fractions
    f_vol_mfbss_stl Output real -

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

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

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

    BZ masses by composition [kg]
    vol_bz_struct Output real -

    BZ masses by composition [kg]
    vol_bz_liq Output real -

    BZ masses by composition [kg]
    vol_bz_liq_ib Output real -

    BZ masses by composition [kg]
    vol_bz_liq_ob Output real -

    BZ masses by composition [kg]
    vol_bw Output real -

    BZ masses by composition [kg]
    vol_bss Output real -

    BZ masses by composition [kg]
    wht_cer Output real -

    Backwall masses by composition [kg]
    wht_stl_struct Output real -

    Backwall masses by composition [kg]
    wht_cool_struct Output real -

    Backwall masses by composition [kg]
    wht_bw_stl Output real -

    MF/BSS masses by composition [kg]
    wht_bw_cool Output real -

    MF/BSS masses by composition [kg]
    wht_mfbss_stl Output real -

    FW masses by composition [kg]
    wht_mfbss_cool Output real -

    FW masses by composition [kg]
    wht_mfbss_pbli Output real -

    FW masses by composition [kg]
    fwmass_stl Output real -

    Total masses of material in blanket [kg]
    fwmass_cool Output real -

    Total masses of material in blanket [kg]
    mass_cool_blanket Output real -

    Total mass for an inboard/outboard reactor segment [kg]
    mass_liq_blanket Output real -

    Total mass for an inboard/outboard reactor segment [kg]
    mass_stl_blanket Output real -

    Total mass for an inboard/outboard reactor segment [kg]
    mass_segm_ib Output real -
    mass_segm_ob Output real -

    sctfcoil_module

    Name Type Datatype Default Value Description
    tf_fit_t Output real -

    Dimensionless winding pack width
    tf_fit_z Output real -

    Dimensionless winding pack radial thickness
    tf_fit_y Output real -

    Ratio of peak field with ripple to nominal axisymmetric peak field
    tfc_current Output real -

    Current in each TF coil
    awpc Output real -

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

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

    Inboard coil steel coil cross-sectional area [m2]
    a_tf_ins Output real -

    Inboard coil insulation cross-section per coil [m2]
    f_tf_steel Output real -

    Inboard coil steel fraction [-]
    f_tf_ins Output real -

    Inboard coil insulation fraction [-]
    h_cp_top Output real -

    Vertical distance from the midplane to the top of the tapered section [m]
    r_tf_outboard_in Output real -

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

    Radial position of outer edge of TF coil inboard leg [m]
    r_wp_inner Output real -

    Radial position of inner edge and centre of winding pack [m]
    r_wp_outer Output real -

    Radial position of outer edge and centre of winding pack [m]
    r_wp_centre Output real -

    Radial position of centre and centre of winding pack [m]
    dr_tf_wp_top Output real -

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

    CP turn insulation volume [m3]
    vol_gr_ins_cp Output real -

    CP ground insulation volume [m3]
    vol_case_cp Output real -

    Volume of the CP outer casing cylinder
    t_wp_toroidal Output real -

    Minimal toroidal thickness of of winding pack [m]
    t_wp_toroidal_av Output real -

    Averaged toroidal thickness of of winding pack [m]
    t_lat_case_av Output real -

    Average lateral casing thickness [m]
    a_case_front Output real -

    Front casing area [m2]
    a_case_nose Output real -

    Nose casing area [m2]
    a_ground_ins Output real -

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

    TF ouboard leg turn insulation area per coil [m2]
    a_leg_gr_ins Output real -

    TF outboard leg ground insulation area per coil [m2]
    a_leg_cond Output real -

    Exact TF ouboard leg conductor area [m2]
    theta_coil Output real -

    Half toroidal angular extent of a single TF coil inboard leg
    tan_theta_coil Output real -

    Tan half toroidal angular extent of a single TF coil inboard leg
    t_conductor_radial Output real -

    Conductor area radial and toroidal dimension (integer turn only) [m]
    t_conductor_toroidal Output real -

    Conductor area radial and toroidal dimension (integer turn only) [m]
    t_cable_radial Output real -

    Cable area radial and toroidal dimension (integer turn only) [m]
    t_cable_toroidal Output real -

    Cable area radial and toroidal dimension (integer turn only) [m]
    t_turn_radial Output real -

    Turn radial and toroidal dimension (integer turn only) [m]
    t_turn_toroidal Output real -

    Turn radial and toroidal dimension (integer turn only) [m]
    t_cable Output real -

    Cable area averaged dimension (square shape) [m]
    vforce_inboard_tot Output real -

    Total inboard vertical tension (all coils) [N]
    vv_stress_quench Output real -

    The Tresca stress experienced by the Vacuum Vessel when the SCTF coil quenches [Pa]
    copper* Variable type -
    hastelloy* Variable type -
    solder* Variable type -
    jacket* Variable type -
    helium* Variable type -
    croco_strand_area Output real -
    croco_strand_critical_current Output real -
    conductor_copper_area Output real -
    conductor_copper_fraction Output real -
    conductor_copper_bar_area Output real -
    conductor_hastelloy_area Output real -
    conductor_hastelloy_fraction Output real -
    conductor_helium_area Output real -
    conductor_helium_fraction Output real -
    conductor_solder_area Output real -
    conductor_solder_fraction Output real -
    conductor_jacket_area Output real -
    conductor_jacket_fraction Output real -
    conductor_rebco_area Output real -
    conductor_rebco_fraction Output real -
    conductor_critical_current Output real -
    conductor_acs Output real -
    conductor_area Output real -

    Area of cable space inside jacket
    t1 Output real -
    time2 Output real -
    tau2 Output real -
    estotft Output real -
    is_leg_cp_temp_same Output integer -

    stellarator_module

    Name Type Datatype Default Value Description
    f_n Output real -
    f_r Output real -
    f_aspect Output real -
    f_b Output real -
    f_i Output real -
    f_a Output real -
    first_call Variable logical .true.
    first_call_stfwbs Variable logical .true.

    buildings_variables

    Name Type Datatype Default Value Description
    admv Input real 100000.0

    administration building volume (m3)
    admvol Output real -

    volume of administration buildings (m3)
    aux_build_l Input real 60.0

    aux building supporting tokamak processes length, width, height (m)
    aux_build_w Input real 30.0

    aux building supporting tokamak processes length, width, height (m)
    aux_build_h Input real 5.0

    aux building supporting tokamak processes length, width, height (m)
    auxcool_l Input real 20.0

    Site-Wide Auxiliary Cooling Water facility length, width, height (m)
    auxcool_w Input real 20.0

    Site-Wide Auxiliary Cooling Water facility length, width, height (m)
    auxcool_h Input real 5.0

    Site-Wide Auxiliary Cooling Water facility length, width, height (m)
    bioshld_thk Input real 2.5

    Radial thickness of bio-shield around reactor (m)
    chemlab_l Input real 50.0

    Chemistry labs and treatment buldings length, width, height (m)
    chemlab_w Input real 30.0

    Chemistry labs and treatment buldings length, width, height (m)
    chemlab_h Input real 6.0

    Chemistry labs and treatment buldings length, width, height (m)
    clh1 Input real 2.5

    vertical clearance from TF coil to cryostat (m) (calculated for tokamaks)
    clh2 Input real 15.0

    clearance beneath TF coil to foundation (including basement) (m)
    control_buildings_l Input real 80.0

    control building length, width, height (m)
    control_buildings_w Input real 60.0

    control building length, width, height (m)
    control_buildings_h Input real 6.0

    control building length, width, height (m)
    conv Input real 60000.0

    control building volume (m3)
    convol Output real -

    volume of control, protection and i&c building (m3)
    crane_arm_h Input real 10.0

    vertical dimension of crane arm, operating over reactor (m)
    crane_clrnc_h Input real 4.0

    horizontal clearance to building wall for crane operation (m)
    crane_clrnc_v Input real 3.0

    vertical clearance for crane operation (m)
    cryomag_l Input real 120.0

    Cryogenic Buildings for Magnet and Fuel Cycle length, width, height (m)
    cryomag_w Input real 90.0

    Cryogenic Buildings for Magnet and Fuel Cycle length, width, height (m)
    cryomag_h Input real 5.0

    Cryogenic Buildings for Magnet and Fuel Cycle length, width, height (m)
    cryostore_l Input real 160.0

    Magnet Cryo Storage Tanks length, width, height (m)
    cryostore_w Input real 30.0

    Magnet Cryo Storage Tanks length, width, height (m)
    cryostore_h Input real 20.0

    Magnet Cryo Storage Tanks length, width, height (m)
    cryostat_clrnc Input real 2.5

    vertical clearance from TF coil to cryostat (m)
    cryvol Output real -

    volume of cryoplant building (m3)
    efloor Output real -

    effective total floor space (m2)
    elecdist_l Input real 380.0

    Transformers and electrical distribution facilities length, width, height (m)
    elecdist_w Input real 350.0

    Transformers and electrical distribution facilities length, width, height (m)
    elecdist_h Input real 5.0

    Transformers and electrical distribution facilities length, width, height (m)
    elecload_l Input real 100.0

    Electric (eesential and non-essential) load centres length, width, height (m)
    elecload_w Input real 90.0

    Electric (eesential and non-essential) load centres length, width, height (m)
    elecload_h Input real 3.0

    Electric (eesential and non-essential) load centres length, width, height (m)
    elecstore_l Input real 100.0

    Energy Storage facilities length, width, height (m)
    elecstore_w Input real 60.0

    Energy Storage facilities length, width, height (m)
    elecstore_h Input real 12.0

    Energy Storage facilities length, width, height (m)
    elevol Output real -

    volume of electrical equipment building (m3)
    esbldgm3 Input real 1000.0

    volume of energy storage equipment building (m3) (not used if lpulse=0)
    fc_building_l Input real 60.0

    Fuel Cycle facilities length, width (m)
    fc_building_w Input real 60.0

    Fuel Cycle facilities length, width (m)
    fndt Input real 2.0

    foundation thickness (m)
    gas_buildings_l Input real 25.0

    air & gas supply (amalgamated) buildings length, width, height (m)
    gas_buildings_w Input real 15.0

    air & gas supply (amalgamated) buildings length, width, height (m)
    gas_buildings_h Input real 5.0

    air & gas supply (amalgamated) buildings length, width, height (m)
    ground_clrnc Input real 5.0

    clearance beneath TF coil (m)
    hcd_building_l Input real 70.0

    HCD building length, width, height (m)
    hcd_building_w Input real 40.0

    HCD building length, width, height (m)
    hcd_building_h Input real 25.0

    HCD building length, width, height (m)
    hccl Input real 5.0

    clearance around components in hot cell (m)
    hcwt Input real 1.5

    hot cell wall thickness (m)
    heat_sink_l Input real 160.0

    heat sinks length, width, height (m)
    heat_sink_w Input real 80.0

    heat sinks length, width, height (m)
    heat_sink_h Input real 12.0

    heat sinks length, width, height (m)
    hot_sepdist Input real 2.0

    hot cell storage component separation distance (m)
    hotcell_h Input real 12.0

    hot cell storage and maintenance facility height (m)
    hw_storage_l Input real 20.0

    hazardous waste storage building length, width, height (m)
    hw_storage_w Input real 10.0

    hazardous waste storage building length, width, height (m)
    hw_storage_h Input real 5.0

    hazardous waste storage building length, width, height (m)
    i_bldgs_size Output integer -

    switch between routines estimating building sizes (0 = default; 1 = updated)
    i_bldgs_v Output integer -

    switch to select verbose output for buildings (1 = verbose)
    ilw_smelter_l Input real 50.0

    radioactive waste smelting facility length, width, height (m)
    ilw_smelter_w Input real 30.0

    radioactive waste smelting facility length, width, height (m)
    ilw_smelter_h Input real 30.0

    radioactive waste smelting facility length, width, height (m)
    ilw_storage_l Input real 120.0

    ILW waste storage building length, width, height (m)
    ilw_storage_w Input real 100.0

    ILW waste storage building length, width, height (m)
    ilw_storage_h Input real 8.0

    ILW waste storage building length, width, height (m)
    llw_storage_l Input real 45.0

    LLW waste storage building length, width, height (m)
    llw_storage_w Input real 20.0

    LLW waste storage building length, width, height (m)
    llw_storage_h Input real 5.0

    LLW waste storage building length, width, height (m)
    magnet_pulse_l Input real 105.0

    pulsed magnet power building length, width, height (m)
    magnet_pulse_w Input real 40.0

    pulsed magnet power building length, width, height (m)
    magnet_pulse_h Input real 5.0

    pulsed magnet power building length, width, height (m)
    magnet_trains_l Input real 120.0

    steady state magnet power trains building length, width, height (m)
    magnet_trains_w Input real 90.0

    steady state magnet power trains building length, width, height (m)
    magnet_trains_h Input real 5.0

    steady state magnet power trains building length, width, height (m)
    maint_cont_l Input real 125.0

    maintenance control building length, width, height (m)
    maint_cont_w Input real 100.0

    maintenance control building length, width, height (m)
    maint_cont_h Input real 6.0

    maintenance control building length, width, height (m)
    mbvfac Input real 2.8

    maintenance building volume multiplication factor
    nbi_sys_l Input real 225.0

    NBI system length, width (m)
    nbi_sys_w Input real 185.0

    NBI system length, width (m)
    pfbldgm3 Input real 20000.0

    volume of PF coil power supply building (m3)
    pibv Input real 20000.0

    power injection building volume (m3)
    qnty_sfty_fac Input real 2.0

    quantity safety factor for component use during plant lifetime
    rbvfac Input real 1.6

    reactor building volume multiplication factor
    rbrt Input real 1.0

    reactor building roof thickness (m)
    rbvol Output real -

    reactor building volume (m3)
    rbwt Input real 2.0

    reactor building wall thickness (m)
    reactor_clrnc Input real 4.0

    clearance around reactor (m)
    reactor_fndtn_thk Input real 2.0

    reactor building foundation thickness (m)
    reactor_hall_l Output real -

    reactor building length, width, height (m)
    reactor_hall_w Output real -

    reactor building length, width, height (m)
    reactor_hall_h Output real -

    reactor building length, width, height (m)
    reactor_roof_thk Input real 1.0

    reactor building roof thickness (m)
    reactor_wall_thk Input real 2.0

    reactor building wall thickness (m)
    rmbvol Output real -

    volume of maintenance and assembly building (m3)
    robotics_l Input real 50.0

    robotics buildings length, width, height (m)
    robotics_w Input real 30.0

    robotics buildings length, width, height (m)
    robotics_h Input real 30.0

    robotics buildings length, width, height (m)
    row Input real 4.0

    clearance to building wall for crane operation (m)
    rxcl Input real 4.0

    clearance around reactor (m)
    sec_buildings_l Input real 30.0

    security & safety buildings length, width, height (m)
    sec_buildings_w Input real 25.0

    security & safety buildings length, width, height (m)
    sec_buildings_h Input real 6.0

    security & safety buildings length, width, height (m)
    shmf Input real 0.5

    fraction of shield mass per TF coil to be moved in the maximum shield lift
    shov Input real 100000.0

    shops and warehouse volume (m3)
    shovol Output real -

    volume of shops and buildings for plant auxiliaries (m3)
    staff_buildings_area Input real 480000.0

    footprint of staff buildings (m2)
    staff_buildings_h Input real 5.0

    staff buildings height (m)
    stcl Input real 3.0

    clearance above crane to roof (m)
    tfcbv Input real 20000.0

    volume of TF coil power supply building (m3) (calculated if TF coils are superconducting)
    transp_clrnc Input real 1.0

    transportation clearance between components (m)
    trcl Input real 1.0

    transportation clearance between components (m)
    triv Input real 40000.0

    volume of tritium, fuel handling and health physics buildings (m3)
    turbine_hall_l Input real 109.0

    turbine hall length, width, height (m)
    turbine_hall_w Input real 62.0

    turbine hall length, width, height (m)
    turbine_hall_h Input real 15.0

    turbine hall length, width, height (m)
    tw_storage_l Input real 90.0

    tritiated waste storage building length, width, height (m)
    tw_storage_w Input real 30.0

    tritiated waste storage building length, width, height (m)
    tw_storage_h Input real 5.0

    tritiated waste storage building length, width, height (m)
    volrci Output real -

    internal volume of reactor building (m3)
    volnucb Output real -

    sum of nuclear buildings volumes (m3)
    warm_shop_l Input real 100.0

    warm shop length, width, height (m)
    warm_shop_w Input real 50.0

    warm shop length, width, height (m)
    warm_shop_h Input real 10.0

    warm shop length, width, height (m)
    water_buildings_l Input real 110.0

    water, laundry & drainage buildings length, width, height (m)
    water_buildings_w Input real 10.0

    water, laundry & drainage buildings length, width, height (m)
    water_buildings_h Input real 5.0

    water, laundry & drainage buildings length, width, height (m)
    wgt Input real 500000.0

    reactor building crane capacity (kg) (calculated if 0 is input)
    wgt2 Input real 100000.0

    hot cell crane capacity (kg) (calculated if 0 is input)
    workshop_l Input real 150.0

    [cold] workshop buildings length, width, height (m)
    workshop_w Input real 125.0

    [cold] workshop buildings length, width, height (m)
    workshop_h Input real 10.0

    [cold] workshop buildings length, width, height (m)
    wrbi Output real -

    distance from centre of machine to building wall (m)
    wsvol Output real -

    volume of warm shop building (m3)
    wsvfac Input real 1.9

    warm shop building volume multiplication factor
    a_reactor_bldg Input real 8320.0

    Floor area of reactor building in m^2
    a_ee_ps_bldg Input real 21330.0

    Floor area of electrical equipment and power supply building in m^2
    a_aux_services_bldg Input real 1000.0

    Floor area of auxiliary services building in m^2
    a_hot_cell_bldg Input real 8430.0

    Floor area of hot cell building in m^2
    a_reactor_service_bldg Input real 2440.0

    Floor area of reactor service building in m^2
    a_service_water_bldg Input real 1567.0

    Floor area of service water building in m^2
    a_fuel_handling_bldg Input real 1670.0

    Floor area of fuel handling and storage building in m^2
    a_control_room_bldg Input real 2880.0

    Floor area of controlroom building in m^2
    a_ac_ps_bldg Input real 6423.0

    Floor area of AC power supply building in m^2
    a_admin_bldg Input real 25674.0

    Floor area of admin building in m^2
    a_site_service_bldg Input real 8300.0

    Floor area of site service building in m^2
    a_cryo_inert_gas_bldg Input real 18380.0

    Floor area of cryogenics and inert gas storage building in m^2
    a_security_bldg Input real 4552.0

    Floor area of security building in m^2

    times_variables

    Name Type Datatype Default Value Description
    pulsetimings Input real 1.0

    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
    tburn Input real 1000.0

    burn time (s) (calculated if lpulse=1)
    tburn0 Output real -

    burn time (s) - used for internal consistency
    tcycle Output real -

    full cycle time (s)
    tdown Output real -

    down time (s)
    tdwell Input real 1800.0

    time between pulses in a pulsed reactor (s) (iteration variable 17)
    t_fusion_ramp Input real 10.0

    heating time, after current ramp up (s)
    tim Output real -

    array of time points during plasma pulse (s)
    timelabel Input character [b'Start ' b'BOP ' b'EOR ' b'BOF ' b'EOF ' b'EOP ']

    array of time labels during plasma pulse (s)
    intervallabel Input character [b'tramp ' b'tohs ' b't_fusion_ra' b'tburn ' b'tqnch ']

    time intervals - as strings (s)
    tohs Input real 30.0

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

    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
    tpulse Output real -

    pulse length = tohs + t_fusion_ramp + tburn + tqnch
    tqnch Input real 15.0

    shut down time for PF coils (s); if pulsed, = tohs
    tramp Input real 15.0

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

    physics_variables

    Name Type Datatype Default Value Description
    ipnlaws Parameter integer 50

    number of energy confinement time scaling laws
    abeam Output real -

    beam ion mass (amu)
    afuel Output real -

    average mass of fuel portion of ions (amu)
    aion Output real -

    average mass of all ions (amu)
    alphaj Input real 1.0

    current profile index (calculated from q_0 and q if iprofile=1)
    alphan Input real 0.25

    density profile index
    alphap Output real -

    pressure profile index
    alpha_rate_density_total Output real -

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

    Alpha particle production rate per unit volume, just from plasma [particles/m3/sec]
    alphat Input real 0.5

    temperature profile index
    aspect Input real 2.907

    aspect ratio (iteration variable 1)
    beamfus0 Input real 1.0

    multiplier for beam-background fusion calculation
    beta Input real 0.042

    total plasma beta (iteration variable 5) (calculated if stellarator)
    betaft Output real -

    fast alpha beta component
    betalim Output real -

    allowable beta
    betalim_lower Output real -

    allowable lower beta
    beta_beam Output real -

    neutral beam beta component
    betap Output real -

    poloidal beta
    normalised_total_beta Output real -

    normaised total beta
    betbm0 Input real 1.5

    leading coefficient for NB beta fraction
    bp Output real -

    poloidal field (T)
    bt Input real 5.68

    toroidal field on axis (T) (iteration variable 2)
    btot Output real -

    total toroidal + poloidal field (T)
    burnup Output real -

    fractional plasma burnup
    burnup_in Output real -

    fractional plasma burnup user input
    bvert Output real -

    vertical field at plasma (T)
    c_beta Input real 0.5

    Destabalisation parameter for iprofile=6 beta limit
    csawth Input real 1.0

    coeff. for sawteeth effects on burn V-s requirement
    cvol Input real 1.0

    multiplying factor times plasma volume (normally=1)
    cwrmax Input real 1.35

    maximum ratio of conducting wall distance to plasma minor radius for vertical stability (constraint equation 23)
    dene Input real 9.8e+19

    electron density (/m3) (iteration variable 6)
    deni Output real -

    fuel ion density (/m3)
    dlamee Output real -

    electron-electron coulomb logarithm
    dlamie Output real -

    ion-electron coulomb logarithm
    dlimit Output real -

    density limit (/m3) as calculated using various models
    dnalp Output real -

    thermal alpha density (/m3)
    dnbeam Output real -

    hot beam ion density, variable (/m3)
    beam_density_out Output real -

    hot beam ion density from calculation (/m3)
    dnbeta Input real 3.5

    Troyon-like coefficient for beta scaling
    dnelimt Output real -

    density limit (/m3)
    dnitot Output real -

    total ion density (/m3)
    dnla Output real -

    line averaged electron density (/m3)
    dnprot Output real -

    proton ash density (/m3)
    dntau Output real -

    plasma average "n-tau" (seconds/m3)
    dnz Output real -

    high Z ion density (/m3)
    gradient_length_ne Output real -

    Max. normalized gradient length in el. density (ipedestal==0 only)
    gradient_length_te Output real -

    Max. normalized gradient length in el. temperature (ipedestal==0 only)
    epbetmax Input real 1.38

    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
    eps Input real 0.34399724802

    inverse aspect ratio
    aux_current_fraction Output real -

    fraction of plasma current produced by auxiliary current drive
    inductive_current_fraction Output real -

    fraction of plasma current produced inductively
    f_alpha_electron Output real -

    fraction of alpha energy to electrons
    f_alpha_plasma Input real 0.95

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

    fraction of alpha power to ions
    f_deuterium Input real 0.5

    deuterium fuel fraction
    ftar Input real 1.0

    fraction of power to the lower divertor in double null configuration (i_single_null = 0 only) (default assumes SN)
    ffwal Input real 0.92

    factor to convert plasma surface area to first wall area in neutron wall load calculation (iwalld=1)
    fgwped Input real 0.85

    fraction of Greenwald density to set as pedestal-top density. If <0, pedestal-top density set manually using neped (ipedestal==1). (iteration variable 145)
    fgwsep Input real 0.5

    fraction of Greenwald density to set as separatrix density. If <0, separatrix density set manually using nesep (ipedestal==1). (iteration variable 152)
    f_helium3 Output real -

    helium-3 fuel fraction
    figmer Output real -

    physics figure of merit (= plasma_currentaspect*sbar, where sbar=1)
    fkzohm Input real 1.0

    Zohm elongation scaling adjustment factor (ishape=2, 3)
    fplhsep Input real 1.0

    F-value for Psep >= Plh + Paux (constraint equation 73)
    fpdivlim Input real 1.0

    F-value for minimum pdivt (constraint equation 80)
    fne0 Input real 1.0

    f-value for the constraint ne(0) > ne(ped) (constraint equation 81) (Iteration variable 154)
    f_tritium Input real 0.5

    tritium fuel fraction
    fusion_rate_density_total Output real -

    fusion reaction rate, from beams and plasma (reactions/m3/sec)
    fusion_rate_density_plasma Output real -

    fusion reaction rate, just from plasma (reactions/m3/sec)
    fvsbrnni Input real 1.0

    fraction of the plasma current produced by non-inductive means (iteration variable 44)
    gamma Input real 0.4

    Ejima coefficient for resistive startup V-s formula
    gammaft Output real -

    ratio of (fast alpha + neutral beam beta) to thermal beta
    hfac Output real -

    H factors for an ignited plasma for each energy confinement time scaling law
    hfact Input real 1.0

    H factor on energy confinement times, radiation corrected (iteration variable 10).
    taumax Input real 10.0

    Maximum allowed energy confinement time (s)
    i_bootstrap_current Input integer 3

    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
    iculbl Output integer -

    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
    i_plasma_current Input integer 4

    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
    i_diamagnetic_current Output integer -

    switch for diamagnetic current scaling

    • =0 Do not calculate
    • =1 Use original TART scaling
    • =2 Use SCENE scaling
    idensl Input integer 7

    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
    idivrt Input integer 2

    number of divertors (calculated from i_single_null)
    ifalphap Input integer 1

    switch for fast alpha pressure calculation

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

    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
    iinvqd Input integer 1

    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
    ipedestal Input integer 1

    switch for pedestal profiles:

    • =0 use original parabolic profiles
    • =1 use pedestal profile
    i_pfirsch_schluter_current Output integer -

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

    • =0 Do not calculate
    • =1 Use SCENE scaling
    neped Input real 4e+19

    electron density of pedestal [m-3] (`ipedestal==1)
    nesep Input real 3e+19

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

    critical ballooning parameter value
    nesep_crit Output real -

    critical electron density at separatrix [m-3]
    plasma_res_factor Input real 1.0

    plasma resistivity pre-factor
    rhopedn Input real 1.0

    r/a of density pedestal (ipedestal==1)
    rhopedt Input real 1.0

    r/a of temperature pedestal (ipedestal==1)
    rho_te_max Output real -

    r/a where the temperature gradient is largest (ipedestal==0)
    rho_ne_max Output real -

    r/a where the density gradient is largest (ipedestal==0)
    tbeta Input real 2.0

    temperature profile index beta (`ipedestal==1)
    teped Input real 1.0

    electron temperature of pedestal (keV) (ipedestal==1)
    tesep Input real 0.1

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

    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
    iradloss Input integer 1

    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.
    isc Input integer 34

    switch for energy confinement time scaling law (see description in tauscl)
    tauscl Parameter character (/'Neo-Alcator      (ohmic)', 'Mirnov               (H)', 'Merezkhin-Muhkovatov (L)', 'Shimomura            (H)', 'Kaye-Goldston        (L)', 'ITER 89-P            (L)', 'ITER 89-O            (L)', 'Rebut-Lallia         (L)', 'Goldston             (L)', 'T10                  (L)', 'JAERI-88             (L)', 'Kaye-Big Complex     (L)', 'ITER H90-P           (H)', 'ITER Mix             (L)', 'Riedel               (L)', 'Christiansen         (L)', 'Lackner-Gottardi     (L)', 'Neo-Kaye             (L)', 'Riedel               (H)', 'ITER H90-P amended   (H)', 'LHD              (stell)', 'Gyro-reduced Bohm(stell)', 'Lackner-Gottardi (stell)', 'ITER-93H             (H)', 'TITAN RFP OBSOLETE      ', 'ITER H-97P ELM-free  (H)', 'ITER H-97P ELMy      (H)', 'ITER-96P             (L)', 'Valovic modified ELMy(H)', 'Kaye PPPL April 98   (L)', 'ITERH-PB98P(y)       (H)', 'IPB98(y)             (H)', 'IPB98(y,1)           (H)', 'IPB98(y,2)           (H)', 'IPB98(y,3)           (H)', 'IPB98(y,4)           (H)', 'ISS95            (stell)', 'ISS04            (stell)', 'DS03                 (H)', 'Murari et al NPL     (H)', 'Petty 2008           (H)', 'Lang et al. 2012     (H)', 'Hubbard 2017 - nom   (I)', 'Hubbard 2017 - lower (I)', 'Hubbard 2017 - upper (I)', 'NSTX (Spherical)     (H)', 'NSTX-Petty08 Hybrid  (H)', 'NSTX gyro-Bohm Buxton(H)', 'Input tauee_in          ', 'ITPA20               (H)'/)

    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

    iscrp Input integer 1

    switch for plasma-first wall clearances:

    • =0 use 10% of rminor
    • =1 use input (scrapli and scraplo)
    ishape Output integer -

    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)
    itart Output integer -

    switch for spherical tokamak (ST) models:

    • =0 use conventional aspect ratio models
    • =1 use spherical tokamak models
    itartpf Output integer -

    switch for Spherical Tokamak PF models:

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

    switch for neutron wall load calculation:

    • =1 use scaled plasma surface area
    • =2 use first wall area directly
    kappa Input real 1.792

    plasma separatrix elongation (calculated if ishape = 1-5, 7 or 9-10)
    kappa95 Input real 1.6

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

    plasma elongation calculated as xarea/(pi.a^2)
    kappaa_ipb Output real -

    Volume measure of plasma elongation
    ne0 Output real -

    central electron density (/m3)
    ni0 Output real -

    central ion density (/m3)
    m_s_limit Input real 0.3

    margin to vertical stability
    p0 Output real -

    central total plasma pressure (Pa)
    vol_avg_pressure Output real -

    Volume averaged plasma pressure (Pa)
    f_dd_branching_trit Output real -

    branching ratio for DD -> T
    alpha_power_density_plasma Output real -

    Alpha power per volume just from plasma [MW/m3]
    alpha_power_density_total Output real -

    Alpha power per volume from plasma and beams [MW/m3]
    alpha_power_electron_density Output real -

    Alpha power per volume to electrons [MW/m3]
    palpfwmw Output real -

    alpha power escaping plasma and reaching first wall (MW)
    alpha_power_ions_density Output real -

    alpha power per volume to ions (MW/m3)
    alpha_power_plasma Output real -

    Alpha power from only the plasma (MW)
    alpha_power_total Output real -

    Total alpha power from plasma and beams (MW)
    alpha_power_beams Output real -

    alpha power from hot neutral beam ions (MW)
    non_alpha_charged_power Output real -

    non-alpha charged particle fusion power (MW)
    charged_particle_power Output real -

    Total charged particle fusion power [MW]
    charged_power_density Output real -

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

    profile factor (= n-weighted T / average T)
    pinnerzoneradmw Output real -

    radiation power from inner zone (MW)
    pcoreradpv Output real -

    total core radiation power per volume (MW/m3)
    dd_power Output real -

    deuterium-deuterium fusion power (MW)
    dhe3_power Output real -

    deuterium-helium3 fusion power (MW)
    pdivt Output real -

    power to conducted to the divertor region (MW)
    pdivl Output real -

    power conducted to the lower divertor region (calculated if i_single_null = 0) (MW)
    pdivu Output real -

    power conducted to the upper divertor region (calculated if i_single_null = 0) (MW)
    pdivmax Output real -

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

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

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

    radiation power from outer zone (MW)
    pedgeradpv Output real -

    edge radiation power per volume (MW/m3)
    phiint Output real -

    internal plasma V-s
    photon_wall Output real -

    Nominal mean radiation load on inside surface of reactor (MW/m2)
    piepv Output real -

    ion/electron equilibration power per volume (MW/m3)
    plasma_current Output real -

    plasma current (A)
    neutron_power_plasma Output real -

    Neutron fusion power from just the plasma [MW]
    neutron_power_total Output real -

    Total neutron fusion power from plasma and beams [MW]
    neutron_power_density_total Output real -

    neutron fusion power per volume from beams and plasma (MW/m3)
    neutron_power_density_plasma Output real -

    neutron fusion power per volume just from plasma (MW/m3)
    pohmmw Output real -

    ohmic heating power (MW)
    pohmpv Output real -

    ohmic heating power per volume (MW/m3)
    powerht Output real -

    heating power (= transport loss power) (MW) used in confinement time calculation
    fusion_power Output real -

    fusion power (MW)
    pperim Output real -

    plasma poloidal perimeter (m)
    pradmw Output real -

    total radiation power from inside LCFS (MW)
    pradpv Output real -

    total radiation power per volume (MW/m3)
    pradsolmw Output real -

    radiation power from SoL (MW)
    proton_rate_density Output real -

    Proton production rate [particles/m3/sec]
    psolradmw Output real -

    SOL radiation power (MW) (stellarator only)
    psyncpv Output real -

    synchrotron radiation power per volume (MW/m3)
    ilhthresh Input integer 19

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

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

    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
    ptremw Output real -

    electron transport power (MW)
    ptrepv Output real -

    electron transport power per volume (MW/m3)
    ptrimw Output real -

    ion transport power (MW)
    pscalingmw Output real -

    Total transport power from scaling law (MW)
    ptripv Output real -

    ion transport power per volume (MW/m3)
    q Input real 3.0

    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)
    q0 Input real 1.0

    safety factor on axis
    q95 Output real -

    safety factor at 95% surface
    qfuel Output real -

    plasma fuelling rate (nucleus-pairs/s)
    tauratio Input real 1.0

    tauratio /1.0/ : ratio of He and pellet particle confinement times
    qlim Output real -

    lower limit for edge safety factor
    qstar Output real -

    cylindrical safety factor
    rad_fraction_sol Input real 0.8

    SoL radiation fraction
    rad_fraction_total Output real -

    Radiation fraction total = SoL + LCFS radiation / total power deposited in plasma
    ralpne Input real 0.1

    thermal alpha density/electron density (iteration variable 109)
    protium Output real -

    Seeded protium density / electron density.
    rli Input real 0.9

    plasma normalised internal inductance (calculated from alphaj if iprofile=1)
    rlp Output real -

    plasma inductance (H)
    rmajor Input real 8.14

    plasma major radius (m) (iteration variable 3)
    rminor Output real -

    plasma minor radius (m)
    rnbeam Input real 0.005

    hot beam density / n_e (iteration variable 7)
    rncne Output real -

    n_carbon / n_e
    rndfuel Output real -

    fuel burnup rate (reactions/second)
    rnfene Output real -

    n_highZ / n_e
    rnone Output real -

    n_oxygen / n_e
    rpfac Output real -

    neo-classical correction factor to rplas
    rplas Output real -

    plasma resistance (ohm)
    res_time Output real -

    plasma current resistive diffusion time (s)
    sarea Output real -

    plasma surface area
    sareao Output real -

    outboard plasma surface area
    sf Output real -

    shape factor = plasma poloidal perimeter / (2.pi.rminor)
    i_single_null Input integer 1

    switch for single null / double null plasma:

    • =0 for double null
    • =1 for single null (diverted side down)
    ssync Input real 0.6

    synchrotron wall reflectivity factor
    tauee Output real -

    electron energy confinement time (sec)
    tauee_in Output real -

    Input electron energy confinement time (sec) (isc=48 only)
    taueff Output real -

    global thermal energy confinement time (sec)
    tauei Output real -

    ion energy confinement time (sec)
    taup Output real -

    alpha particle confinement time (sec)
    te Input real 12.9

    volume averaged electron temperature (keV) (iteration variable 4)
    te0 Output real -

    central electron temperature (keV)
    ten Output real -

    density weighted average electron temperature (keV)
    ti Input real 12.9

    volume averaged ion temperature (keV). N.B. calculated from te if tratio > 0.0
    ti0 Output real -

    central ion temperature (keV)
    tin Output real -

    density weighted average ion temperature (keV)
    tratio Input real 1.0

    ion temperature / electron temperature(used to calculate ti if tratio > 0.0
    triang Input real 0.36

    plasma separatrix triangularity (calculated if ishape = 1, 3-5 or 7)
    triang95 Input real 0.24

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

    plasma volume (m3)
    vsbrn Output real -

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

    plasma/device midplane vertical shift - single null
    vsind Output real -

    internal and external plasma inductance V-s (Wb)
    vsres Output real -

    resistive losses in startup V-s (Wb)
    vsstt Output real -

    total V-s needed (Wb)
    wallmw Output real -

    average neutron wall load (MW/m2)
    wtgpd Output real -

    mass of fuel used per day (g)
    xarea Output real -

    plasma cross-sectional area (m2)
    zeff Output real -

    plasma effective charge
    zeffai Output real -

    mass weighted plasma effective charge

    cost_variables

    Name Type Datatype Default Value Description
    abktflnc Input real 5.0

    allowable first wall/blanket neutron fluence (MW-yr/m2) (blktmodel=0)
    adivflnc Input real 7.0

    allowable divertor heat fluence (MW-yr/m2)
    blkcst Output real -

    blanket direct cost (M$)
    c221 Output real -

    total account 221 cost (M$) - first wall, blanket, shield, support structure and div plates
    c222 Output real -

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

    total capital cost including interest (M$)
    cconfix Input real 80.0

    fixed cost of superconducting cable ($/m)
    cconshpf Input real 70.0

    cost of PF coil steel conduit/sheath ($/m)
    cconshtf Input real 75.0

    cost of TF coil steel conduit/sheath ($/m)
    cdcost Output real -

    current drive direct costs (M$)
    cdirt Output real -

    total plant direct cost (M$)
    cdrlife Output real -

    Full power year lifetime of heating/current drive system (y)
    cdrlife_cal Output real -

    Calendar year lifetime of heating/current drive system (y)
    cfactr Input real 0.75

    Total plant availability fraction; input if iavail=0
    cpfact Output real -

    Total plant capacity factor
    cfind Input real [0.244 0.244 0.244 0.29 ]

    indirect cost factor (func of lsa) (cost model = 0)
    cland Input real 19.2

    cost of land (M$)
    coe Output real -

    cost of electricity ($/MW-hr)
    coecap Output real -

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

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

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

    plant construction cost (M$)
    costexp Input real 0.8

    cost exponent for scaling in 2015 costs model
    costexp_pebbles Input real 0.6

    cost exponent for pebbles in 2015 costs model
    cost_factor_buildings Input real 1.0

    cost scaling factor for buildings
    cost_factor_land Input real 1.0

    cost scaling factor for land
    cost_factor_tf_coils Input real 1.0

    cost scaling factor for TF coils
    cost_factor_fwbs Input real 1.0

    cost scaling factor for fwbs
    cost_factor_rh Input real 1.0

    cost scaling factor for remote handling
    cost_factor_vv Input real 1.0

    cost scaling factor for vacuum vessel
    cost_factor_bop Input real 1.0

    cost scaling factor for energy conversion system
    cost_factor_misc Input real 1.0

    cost scaling factor for remaining subsystems
    maintenance_fwbs Input real 0.2

    Maintenance cost factor: first wall, blanket, shield, divertor
    maintenance_gen Input real 0.05

    Maintenance cost factor: All other components except coils, vacuum vessel, thermal shield, cryostat, land
    amortization Input real 13.6

    amortization factor (fixed charge factor) "A" (years)
    cost_model Input integer 1

    Switch for cost model:

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

    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
    cowner Input real 0.15

    owner cost factor
    cplife_input Input real 2.0

    User input full power year lifetime of the centrepost (years) (i_cp_lifetime = 0)
    cplife Output real -

    Calculated full power year lifetime of centrepost (years)
    cplife_cal Output real -

    Calculated calendar year lifetime of centrepost (years)
    cpstcst Output real -

    ST centrepost direct cost (M$)
    cpstflnc Input real 10.0

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

    reactor core costs (categories 221, 222 and 223)
    csi Input real 16.0

    allowance for site costs (M$)
    cturbb Input real 38.0

    cost of turbine building (M$)
    decomf Input real 0.1

    proportion of constructed cost required for decommissioning fund
    dintrt Output real -

    diff between borrowing and saving interest rates
    divcst Output real -

    divertor direct cost (M$)
    divlife Output real -

    Full power lifetime of divertor (y)
    divlife_cal Output real -

    Calendar year lifetime of divertor (y)
    dtlife Output real -

    period prior to the end of the plant life that the decommissioning fund is used (years)
    fcap0 Input real 1.165

    average cost of money for construction of plant assuming design/construction time of six years
    fcap0cp Input real 1.08

    average cost of money for replaceable components assuming lead time for these of two years
    fcdfuel Input real 0.1

    fraction of current drive cost treated as fuel (if ifueltyp = 1)
    fcontng Input real 0.195

    project contingency factor
    fcr0 Input real 0.0966

    fixed charge rate during construction
    fkind Input real 1.0

    multiplier for Nth of a kind costs
    fwallcst Output real -

    first wall cost (M$)
    iavail Input integer 2

    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
    ibkt_life Output integer -

    Switch for fw/blanket lifetime calculation in availability module:

    • =0 use neutron fluence model
    • =1 use fusion power model (DEMO only)
    life_dpa Input real 50.0

    Allowable DPA from DEMO fw/blanket lifetime calculation in availability module
    bktcycles Input real 1000.0

    Number of fusion cycles to reach allowable DPA from DEMO fw/blanket lifetime calculation
    avail_min Input real 0.75

    Minimum availability (constraint equation 61)
    tok_build_cost_per_vol Input real 1283.0

    Unit cost for tokamak complex buildings, including building and site services ($/m3)
    light_build_cost_per_vol Input real 270.0

    Unit cost for unshielded non-active buildings ($/m3)
    favail Input real 1.0

    F-value for minimum availability (constraint equation 61)
    num_rh_systems Input integer 4

    Number of remote handling systems (1-10)
    conf_mag Input real 0.99

    c parameter, which determines the temperature margin at which magnet lifetime starts to decline
    div_prob_fail Input real 0.0002

    Divertor probability of failure (per op day)
    div_umain_time Input real 0.25

    Divertor unplanned maintenance time (years)
    div_nref Input real 7000.0

    Reference value for cycle cycle life of divertor
    div_nu Input real 14000.0

    The cycle when the divertor fails with 100% probability
    fwbs_nref Input real 20000.0

    Reference value for cycle life of blanket
    fwbs_nu Input real 40000.0

    The cycle when the blanket fails with 100% probability
    fwbs_prob_fail Input real 0.0002

    Fwbs probability of failure (per op day)
    fwbs_umain_time Input real 0.25

    Fwbs unplanned maintenance time (years)
    redun_vacp Input real 25.0

    Vacuum system pump redundancy level (%)
    redun_vac Output integer -

    Number of redundant vacuum pumps
    t_operation Output real -

    Operational time (yrs)
    tbktrepl Input real 0.5

    time taken to replace blanket (y) (iavail=1)
    tcomrepl Input real 0.5

    time taken to replace both blanket and divertor (y) (iavail=1)
    tdivrepl Input real 0.25

    time taken to replace divertor (y) (iavail=1)
    uubop Input real 0.02

    unplanned unavailability factor for balance of plant (iavail=1)
    uucd Input real 0.02

    unplanned unavailability factor for current drive (iavail=1)
    uudiv Input real 0.04

    unplanned unavailability factor for divertor (iavail=1)
    uufuel Input real 0.02

    unplanned unavailability factor for fuel system (iavail=1)
    uufw Input real 0.04

    unplanned unavailability factor for first wall (iavail=1)
    uumag Input real 0.02

    unplanned unavailability factor for magnets (iavail=1)
    uuves Input real 0.04

    unplanned unavailability factor for vessel (iavail=1)
    ifueltyp Output integer -

    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
    ipnet Output integer -

    Switch for net electric power calculation:

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

    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
    lsa Input integer 4

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

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

    interest portion of capital cost (M$)
    output_costs Input integer 1

    Switch for costs output:

    • =0 do not write cost-related outputs to file
    • =1 write cost-related outputs to file
    discount_rate Input real 0.0435

    effective cost of money in constant dollars
    startupratio Input real 1.0

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

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

    Switch for superconductor cost model:

    • =0 use $/kg
    • =1 use $/kAm
    tlife Input real 30.0

    Full power year plant lifetime (years)
    tmain Output real -

    Maintenance time for replacing CP (years) (iavail = 3)
    u_unplanned_cp Output real -

    User-input CP unplanned unavailability (iavail = 3)
    ucad Parameter real 180.0D0

    unit cost for administration buildings (M$/m3)
    ucaf Parameter real 1.5D6

    unit cost for aux facility power equipment ($)
    ucahts Parameter real 31.0D0

    unit cost for aux heat transport equipment ($/W**exphts)
    ucap Parameter real 17.0D0

    unit cost of auxiliary transformer ($/kVA)
    ucblbe Input real 260.0

    unit cost for blanket beryllium ($/kg)
    ucblbreed Input real 875.0

    unit cost for breeder material ($/kg) (blktmodel>0)
    ucblli Input real 875.0

    unit cost for blanket lithium ($/kg) (30% Li6)
    ucblli2o Input real 600.0

    unit cost for blanket Li_2O ($/kg)
    ucbllipb Input real 10.3

    unit cost for blanket Li-Pb ($/kg) (30% Li6)
    ucblss Input real 90.0

    unit cost for blanket stainless steel ($/kg)
    ucblvd Input real 200.0

    unit cost for blanket vanadium ($/kg)
    ucbpmp Parameter real 2.925D5

    vacuum system backing pump cost ($)
    ucbus Input real 0.123

    cost of aluminium bus for TF coil ($/A-m)
    uccase Input real 50.0

    cost of superconductor case ($/kg)
    ucco Parameter real 350.0D0

    unit cost for control buildings (M$/m3)
    uccpcl1 Input real 250.0

    cost of high strength tapered copper ($/kg)
    uccpclb Input real 150.0

    cost of TF outboard leg plate coils ($/kg)
    uccpmp Parameter real 3.9D5

    vacuum system cryopump cost ($)
    uccr Parameter real 460.0D0

    unit cost for cryogenic building (M$/vol)
    uccry Input real 93000.0

    heat transport system cryoplant costs ($/W**expcry)
    uccryo Input real 32.0

    unit cost for vacuum vessel ($/kg)
    uccu Input real 75.0

    unit cost for copper in superconducting cable ($/kg)
    ucdgen Parameter real 1.7D6

    cost per 8 MW diesel generator ($)
    ucdiv Input real 280000.0

    cost of divertor blade ($)
    ucdtc Parameter real 13.0D0

    detritiation, air cleanup cost ($/10000m3/hr)
    ucduct Parameter real 4.225D4

    vacuum system duct cost ($/m)
    ucech Input real 3.0

    ECH system cost ($/W)
    ucel Parameter real 380.0D0

    unit cost for electrical equipment building (M$/m3)
    uces1 Parameter real 3.2D4

    MGF (motor-generator flywheel) cost factor ($/MVA**0.8)
    uces2 Parameter real 8.8D3

    MGF (motor-generator flywheel) cost factor ($/MJ**0.8)
    ucf1 Input real 22300000.0

    cost of fuelling system ($)
    ucfnc Input real 35.0

    outer PF coil fence support cost ($/kg)
    ucfpr Parameter real 4.4D7

    cost of 60g/day tritium processing unit ($)
    ucfuel Input real 3.45

    unit cost of D-T fuel (M$/year/1200MW)
    ucfwa Parameter real 6.0D4

    first wall armour cost ($/m2)
    ucfwps Parameter real 1.0D7

    first wall passive stabiliser cost ($)
    ucfws Parameter real 5.3D4

    first wall structure cost ($/m2)
    ucgss Parameter real 35.0D0

    cost of reactor structure ($/kg)
    uche3 Input real 1000000.0

    cost of helium-3 ($/kg)
    uchrs Input real 87900000.0

    cost of heat rejection system ($)
    uchts Input real [15.3 19.1]

    cost of heat transport system equipment per loop ($/W); dependent on coolant type (coolwh)
    uciac Input real 150000000.0

    cost of instrumentation, control & diagnostics ($)
    ucich Input real 3.0

    ICH system cost ($/W)
    ucint Parameter real 35.0D0

    superconductor intercoil structure cost ($/kg)
    uclh Input real 3.3

    lower hybrid system cost ($/W)
    uclv Parameter real 16.0D0

    low voltage system cost ($/kVA)
    ucmb Parameter real 260.0D0

    unit cost for reactor maintenance building (M$/m3)
    ucme Input real 125000000.0

    cost of maintenance equipment ($)
    ucmisc Input real 25000000.0

    miscellaneous plant allowance ($)
    ucnbi Input real 3.3

    NBI system cost ($/W)
    ucnbv Parameter real 1000.0D0

    cost of nuclear building ventilation ($/m3)
    ucoam Input real [68.8 68.8 68.8 74.4]

    annual cost of operation and maintenance (M$/year/1200MW**0.5)
    ucpens Input real 32.0

    penetration shield cost ($/kg)
    ucpfb Input real 210.0

    cost of PF coil buses ($/kA-m)
    ucpfbk Input real 16600.0

    cost of PF coil DC breakers ($/MVA**0.7)
    ucpfbs Input real 4900.0

    cost of PF burn power supplies ($/kW**0.7)
    ucpfcb Input real 75000.0

    cost of PF coil AC breakers ($/circuit)
    ucpfdr1 Input real 150.0

    cost factor for dump resistors ($/MJ)
    ucpfic Input real 10000.0

    cost of PF instrumentation and control ($/channel)
    ucpfps Input real 35000.0

    cost of PF coil pulsed power supplies ($/MVA)
    ucphx Parameter real 15.0D0

    primary heat transport cost ($/W**exphts)
    ucpp Parameter real 48.0D0

    cost of primary power transformers ($/kVA**0.9)
    ucrb Input real 400.0

    cost of reactor building (M$/m3)
    ucsc Input real [ 600. 600. 300. 600. 600. 600. 300. 1200. 1200.]

    cost of superconductor ($/kg)
    sc_mat_cost_0 Input real [ 4.8 2. 1. 4.8 4.8 47.4 1. 47.4 47.4]

    cost of superconductor ($/kA m) at 6.4 T, 4.2 K
    ucsh Parameter real 115.0D0

    cost of shops and warehouses (M$/m3)
    ucshld Input real 32.0

    cost of shield structural steel ($/kg)
    ucswyd Parameter real 1.84D7

    switchyard equipment costs ($)
    uctfbr Input real 1.22

    cost of TF coil breakers ($/W**0.7)
    uctfbus Input real 100.0

    cost of TF coil bus ($/kg)
    uctfdr Parameter real 1.75D-4

    cost of TF coil dump resistors ($/J)
    uctfgr Parameter real 5000.0D0

    additional cost of TF coil dump resistors ($/coil)
    uctfic Parameter real 1.0D4

    cost of TF coil instrumentation and control ($/coil/30)
    uctfps Input real 24.0

    cost of TF coil power supplies ($/W**0.7)
    uctfsw Input real 1.0

    cost of TF coil slow dump switches ($/A)
    uctpmp Parameter real 1.105D5

    cost of turbomolecular pump ($)
    uctr Parameter real 370.0D0

    cost of tritium building ($/m3)
    ucturb Input real [2.30e+08 2.45e+08]

    cost of turbine plant equipment ($) (dependent on coolant type coolwh)
    ucvalv Parameter real 3.9D5

    vacuum system valve cost ($)
    ucvdsh Parameter real 26.0D0

    vacuum duct shield cost ($/kg)
    ucviac Parameter real 1.3D6

    vacuum system instrumentation and control cost ($)
    ucwindpf Input real 465.0

    cost of PF coil superconductor windings ($/m)
    ucwindtf Input real 480.0

    cost of TF coil superconductor windings ($/m)
    ucws Parameter real 460.0D0

    cost of active assembly shop ($/m3)
    ucwst Input real [0. 3.94 5.91 7.88]

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

    process_input

    Name Type Datatype Default Value Description
    nin Parameter integer 10
    maxlen* Parameter integer 2000
    line* Variable character -
    linelen* Variable integer -
    lineno* Variable integer -
    iptr* Variable integer -
    infile* Variable integer -
    outfile* Variable integer -
    report_changes* Variable integer -
    icode* Variable integer -
    subscript_present* Variable logical -
    error* Variable logical -
    error_message* Variable character -
    show_changes* Variable integer -
    constraints_exist* Variable logical -

    reinke_module

    Name Type Datatype Default Value Description
    vcritx Output real -

    error_handling

    Name Type Datatype Default Value Description
    errors_on Output logical -
    error_okay* Parameter integer 0
    error_info* Parameter integer 1
    error_warn* Parameter integer 2
    error_severe* Parameter integer 3
    error_id* Variable integer -

    error_id : identifier for final message encountered
    error_status Output integer -

    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
    int_default* Parameter integer -999999
    flt_default* Parameter real real(INT_DEFAULT, kind(1.0D0))
    idiags Input integer [-999999 -999999 -999999 -999999 -999999 -999999 -999999 -999999]
    fdiags Input real [-999999. -999999. -999999. -999999. -999999. -999999. -999999. -999999.]
    error_head* Variable type -
    error_tail* Variable type -
    error_type* Variable type -

    rebco_variables

    Name Type Datatype Default Value Description
    rebco_thickness Input real 1e-06

    thickness of REBCO layer in tape (m) (iteration variable 138)
    copper_thick Input real 0.0001

    thickness of copper layer in tape (m) (iteration variable 139)
    hastelloy_thickness Input real 5e-05

    thickness of Hastelloy layer in tape (m)
    tape_width Input real 0.004

    Mean width of tape (m)
    tape_thickness Input real 6.5e-05

    thickness of tape, inc. all layers (hts, copper, substrate, etc.) (m)
    croco_od Output real -

    Outer diameter of CroCo strand (m)
    croco_id Output real -

    Inner diameter of CroCo copper tube (m)
    croco_thick Input real 0.0025

    Thickness of CroCo copper tube (m) (iteration variable 158)
    copper_rrr Input real 100.0

    residual resistivity ratio copper in TF superconducting cable
    coppera_m2 Output real -

    TF coil current / copper area (A/m2)
    coppera_m2_max Input real 100000000.0

    Maximum TF coil current / copper area (A/m2)
    f_coppera_m2 Input real 1.0

    f-value for constraint 75: TF coil current / copper area < copperA_m2_max
    copperaoh_m2 Output real -

    CS coil current / copper area (A/m2) (sweep variable 61)
    copperaoh_m2_max Input real 100000000.0

    Maximum CS coil current / copper area (A/m2)
    f_copperaoh_m2 Input real 1.0

    f-value for constraint 88: CS coil current / copper area < copperA_m2_max
    stack_thickness Output real -
    tapes Output real -
    rebco_area Output real -
    copper_area Output real -
    hastelloy_area Output real -
    solder_area Output real -
    croco_area Output real -

    reinke_variables

    Name Type Datatype Default Value Description
    impvardiv Input integer 9

    Index of impurity to be iterated for Reinke divertor detachment criterion
    lhat Input real 4.33

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

    Minimum impurity fraction necessary for detachment. This is the impurity at the SOL/Div.
    fzactual Input real 0.001

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

    Switch for Reinke criterion H/I mode:

    • =0 H-mode
    • =1 I-mode

    water_usage_variables

    Name Type Datatype Default Value Description
    airtemp Input real 15.0

    ambient air temperature (degrees Celsius)
    watertemp Input real 5.0

    water temperature (degrees Celsius)
    windspeed Input real 4.0

    wind speed (m/s)
    waterdens Input real 998.02

    density of water (kg/m3) for simplicity, set to static value applicable to water at 21 degC
    latentheat Input real 2257000.0

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

    volumetric heat of vaporization (J/m3)
    evapratio Output real -

    evaporation ratio: ratio of the heat used to evaporate water to the total heat discharged through the tower
    evapvol Output real -

    evaporated volume of water (m3)
    energypervol Output real -

    input waste (heat) energy cooled per evaporated volume (J/m3)
    volperenergy Output real -

    volume evaporated by units of heat energy (m3/MJ)
    waterusetower Output real -

    total volume of water used in cooling tower (m3)
    wateruserecirc Output real -

    total volume of water used in recirculating system (m3)
    wateruseonethru Output real -

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

    structure_variables

    Name Type Datatype Default Value Description
    aintmass Output real -

    intercoil structure mass (kg)
    clgsmass Output real -

    gravity support structure for TF coil, PF coil and intercoil support systems (kg)
    coldmass Output real -

    total mass of components at cryogenic temperatures (kg)
    fncmass Output real -

    PF coil outer support fence mass (kg)
    gsmass Output real -

    reactor core gravity support mass (kg)

    fwbs_variables

    Name Type Datatype Default Value Description
    bktlife Output real -

    Full power blanket lifetime (years)
    bktlife_cal Output real -

    Calendar year blanket lifetime (years)
    coolmass Output real -

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

    vacuum vessel mass [kg]
    denstl Input real 7800.0

    density of steel [kg m^-3]
    denw Input real 19250.0

    density of tungsten [kg m^-3]
    denwc Input real 15630.0

    density of tungsten carbide [kg m^-3]
    dewmkg Output real -

    total mass of vacuum vessel + cryostat [kg] (calculated if blktmodel>0)
    emult Input real 1.269

    energy multiplication in blanket and shield
    emultmw Output real -

    power due to energy multiplication in blanket and shield [MW]
    fblss Input real 0.09705

    KIT blanket model: steel fraction of breeding zone
    fdiv Input real 0.115

    Solid angle fraction taken by one divertor
    fhcd Output real -

    area fraction covered by heating/current drive apparatus plus diagnostics
    fhole Output real -

    area fraction taken up by other holes (IFE)
    fwbsshape Input integer 2

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

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

    first wall full-power year lifetime (y)
    fwmass Output real -

    first wall mass [kg]
    fw_armour_mass Output real -

    first wall armour mass [kg]
    fw_armour_thickness Input real 0.005

    first wall armour thickness [m]
    fw_armour_vol Output real -

    first wall armour volume [m^3]
    iblanket Input integer 1

    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.
    iblnkith Input integer 1

    switch for inboard blanket:

    • =0 No inboard blanket (blnkith=0.0)
    • =1 Inboard blanket present
    inuclear Output integer -

    switch for nuclear heating in the coils:

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

    nuclear heating in the coils (W) (inuclear=1)
    li6enrich Input real 30.0

    lithium-6 enrichment of breeding material (%)
    pnucblkt Output real -

    nuclear heating in the blanket [MW]
    pnuc_cp Output real -

    Total nuclear heating in the ST centrepost [MW]
    pnuc_cp_sh Output real -

    Neutronic shield nuclear heating in the ST centrepost [MW]
    pnuc_cp_tf Output real -

    TF neutronic nuclear heating in the ST centrepost [MW]
    pnucdiv Output real -

    nuclear heating in the divertor [MW]
    pnucfw Output real -

    nuclear heating in the first wall [MW]
    pnuchcd Output real -

    nuclear heating in the HCD apparatus and diagnostics [MW]
    pnucloss Output real -

    nuclear heating lost via holes [MW]
    pnucvvplus Output real -

    nuclear heating to vacuum vessel and beyond [MW]
    pnucshld Output real -

    nuclear heating in the shield [MW]
    whtblkt Output real -

    mass of blanket [kg]
    whtblss Output real -

    mass of blanket - steel part [kg]
    armour_fw_bl_mass Output real -

    Total mass of armour, first wall and blanket [kg]
    breeder_f Input real 0.5

    Volume ratio: Li4SiO4/(Be12Ti+Li4SiO4) (iteration variable 108)
    breeder_multiplier Input real 0.75

    combined breeder/multipler fraction of blanket by volume
    vfcblkt Input real 0.05295

    He coolant fraction of blanket by volume (iblanket= 1,3 (CCFE HCPB))
    vfpblkt Input real 0.1

    He purge gas fraction of blanket by volume (iblanket= 1,3 (CCFE HCPB))
    whtblli4sio4 Output real -

    mass of lithium orthosilicate in blanket [kg] (iblanket=1,3 (CCFE HCPB))
    whtbltibe12 Output real -

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

    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 Input real -1.0

    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 )
    vffwi Output real -

    Inboard/outboard FW coolant void fraction
    vffwo Output real -

    Inboard/outboard FW coolant void fraction
    psurffwi Output real -

    Surface heat flux on first wall [MW] (sum = pradfw)
    psurffwo Output real -

    Surface heat flux on first wall [MW] (sum = pradfw)
    volfw Output real -

    First wall volume [m3]
    fblss_ccfe Output real -

    Fractions of blanket by volume: steel, lithium orthosilicate, titanium beryllide
    fblli2sio4 Output real -

    Fractions of blanket by volume: steel, lithium orthosilicate, titanium beryllide
    fbltibe12 Output real -

    Fractions of blanket by volume: steel, lithium orthosilicate, titanium beryllide
    breedmat Input integer 1

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

    • =1 Lithium orthosilicate
    • =2 Lithium methatitanate
    • =3 Lithium zirconate
    densbreed Output real -

    density of breeder material [kg m^-3] (iblanket=2 (KIT HCPB))
    fblbe Input real 0.6

    beryllium fraction of blanket by volume (if iblanket=2, is Be fraction of breeding zone)
    fblbreed Input real 0.154

    breeder fraction of blanket breeding zone by volume (iblanket=2 (KIT HCPB))
    fblhebmi Input real 0.4

    helium fraction of inboard blanket box manifold by volume (iblanket=2 (KIT HCPB))
    fblhebmo Input real 0.4

    helium fraction of outboard blanket box manifold by volume (iblanket=2 (KIT HCPB))
    fblhebpi Input real 0.6595

    helium fraction of inboard blanket back plate by volume (iblanket=2 (KIT HCPB))
    fblhebpo Input real 0.6713

    helium fraction of outboard blanket back plate by volume (iblanket=2 (KIT HCPB))
    hcdportsize Input integer 1

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

    • =1 'small'
    • =2 'large'
    nflutf Output real -

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

    number of divertor ports (iblanket=2 (KIT HCPB))
    nphcdin Input integer 2

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

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

    tritium breeding ratio (iblanket=2,3 (KIT HCPB/HCLL))
    tritprate Output real -

    tritium production rate [g day^-1] (iblanket=2 (KIT HCPB))
    wallpf Input real 1.21

    neutron wall load peaking factor (iblanket=2 (KIT HCPB))
    whtblbreed Output real -

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

    mass of blanket - beryllium part [kg]
    iblanket_thickness Input integer 2

    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
    primary_pumping Input integer 2

    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
    i_shield_mat Output integer -

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

    • =0 Tungsten (default)
    • =1 Tungsten carbide
    secondary_cycle Output integer -

    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
    secondary_cycle_liq Input integer 4

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

    • =2 user input thermal-electric efficiency (etath)
    • =4 supercritical CO2 cycle
    coolwh Input integer 1

    Switch for blanket coolant (set via blkttype):

    • =1 helium
    • =2 pressurized water
    afwi Input real 0.008

    inner radius of inboard first wall/blanket coolant channels (stellarator only) [m]
    afwo Input real 0.008

    inner radius of outboard first wall/blanket coolant channels (stellarator only) [m]
    fwcoolant Input character b'helium'

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

    • 'helium'
    • 'water'
    fw_wall Input real 0.003

    wall thickness of first wall coolant channels [m]
    afw Input real 0.006

    radius of first wall cooling channels [m]
    pitch Input real 0.02

    pitch of first wall cooling channels [m]
    fwinlet Input real 573.0

    inlet temperature of first wall coolant [K]
    fwoutlet Input real 823.0

    outlet temperature of first wall coolant [K]
    fwpressure Input real 15500000.0

    first wall coolant pressure [Pa] (secondary_cycle>1)
    tpeak Input real 873.0

    peak first wall temperature [K]
    roughness Input real 1e-06

    first wall channel roughness epsilon [m]
    fw_channel_length Input real 4.0

    Length of a single first wall channel (all in parallel) [m] (iteration variable 114, useful for constraint equation 39)
    peaking_factor Input real 1.0

    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.)
    blpressure Input real 15500000.0

    blanket coolant pressure [Pa] (secondary_cycle>1)
    inlet_temp Input real 573.0

    inlet temperature of blanket coolant [K] (secondary_cycle>1)
    outlet_temp Input real 823.0

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

    • input if coolwh=1 (helium)
    • calculated if coolwh=2 (water)
    coolp Input real 15500000.0

    blanket coolant pressure [Pa] (stellarator only)
    nblktmodpo Input integer 8

    number of outboard blanket modules in poloidal direction (secondary_cycle>1)
    nblktmodpi Input integer 7

    number of inboard blanket modules in poloidal direction (secondary_cycle>1)
    nblktmodto Input integer 48

    number of outboard blanket modules in toroidal direction (secondary_cycle>1)
    nblktmodti Input integer 32

    number of inboard blanket modules in toroidal direction (secondary_cycle>1)
    tfwmatmax Input real 823.0

    maximum temperature of first wall material [K] (secondary_cycle>1)
    fw_th_conductivity Input real 28.34

    thermal conductivity of first wall material at 293 K (W/m/K) (Temperature dependence is as for unirradiated Eurofer)
    fvoldw Input real 1.74

    area coverage factor for vacuum vessel volume
    fvolsi Input real 1.0

    area coverage factor for inboard shield volume
    fvolso Input real 0.64

    area coverage factor for outboard shield volume
    fwclfr Input real 0.15

    first wall coolant fraction (calculated if lpulse=1 or ipowerflow=1)
    praddiv Output real -

    Radiation power incident on the divertor (MW)
    pradfw Output real -

    Radiation power incident on the first wall (MW)
    pradhcd Output real -

    Radiation power incident on the heating and current drive system (MW)
    pradloss Output real -

    Radiation power lost through holes (eventually hits shield) (MW) Only used for stellarator
    ptfnuc Output real -

    nuclear heating in the TF coil (MW)
    ptfnucpm3 Output real -

    nuclear heating in the TF coil (MW/m3) (blktmodel>0)
    rdewex Output real -

    cryostat radius [m]
    zdewex Output real -

    cryostat height [m]
    rpf2dewar Input real 0.5

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

    cryostat volume [m^3]
    vdewin Output real -

    vacuum vessel volume [m^3]
    vfshld Input real 0.25

    coolant void fraction in shield
    volblkt Output real -

    volume of blanket [m^3]
    volblkti Output real -

    volume of inboard blanket [m^3]
    volblkto Output real -

    volume of outboard blanket [m^3]
    volshld Output real -

    volume of shield [m^3]
    whtshld Output real -

    mass of shield [kg]
    wpenshld Output real -

    mass of the penetration shield [kg]
    wtshldi Output real -

    mass of inboard shield [kg]
    wtshldo Output real -

    mass of outboard shield [kg]
    irefprop Input integer 1

    Switch to use REFPROP routines (stellarator only)
    fblli Output real -

    lithium fraction of blanket by volume (stellarator only)
    fblli2o Input real 0.08

    lithium oxide fraction of blanket by volume (stellarator only)
    fbllipb Input real 0.68

    lithium lead fraction of blanket by volume (stellarator only)
    fblvd Output real -

    vanadium fraction of blanket by volume (stellarator only)
    wtblli2o Output real -

    mass of blanket - Li_2O part [kg]
    wtbllipb Output real -

    mass of blanket - Li-Pb part [kg]
    whtblvd Output real -

    mass of blanket - vanadium part [kg]
    whtblli Output real -

    mass of blanket - lithium part [kg]
    vfblkt Input real 0.25

    coolant void fraction in blanket.
    blktmodel Output integer -

    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
    declblkt Input real 0.075

    neutron power deposition decay length of blanket structural material [m] (stellarators only)
    declfw Input real 0.075

    neutron power deposition decay length of first wall structural material [m] (stellarators only)
    declshld Input real 0.075

    neutron power deposition decay length of shield structural material [m] (stellarators only)
    blkttype Input integer 3

    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 Input real 0.85

    isentropic efficiency of FW and blanket coolant pumps
    etahtp Input real 0.95

    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
    ipump Output integer -

    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_bb_liq Output integer -

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

    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.
    ifci Output integer -

    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
    ims Output integer -

    Switch for Multi Module Segment (MMS) or Single Modle Segment (SMS) - =0 MMS - =1 SMS
    n_liq_recirc Input integer 10

    Number of liquid metal breeder recirculations per day, for use with icooldual=1
    r_f_liq_ib Input real 0.5

    Radial fraction of BZ liquid channels
    r_f_liq_ob Input real 0.5

    Radial fraction of BZ liquid channels
    w_f_liq_ib Input real 0.5

    Toroidal fraction of BZ liquid channels
    w_f_liq_ob Input real 0.5

    Toroidal fraction of BZ liquid channels
    den_ceramic Input real 3210.0

    FCI material density
    th_wall_secondary Input real 0.0125

    Liquid metal coolant/breeder wall thickness thin conductor or FCI [m]
    bz_channel_conduct_liq Input real 833000.0

    Liquid metal coolant/breeder thin conductor or FCI wall conductance [A V^-1 m^-1]
    a_bz_liq Input real 0.2

    Toroidal width of the rectangular cooling channel [m] for long poloidal sections of blanket breeding zone
    b_bz_liq Input real 0.2

    Radial width of the rectangular cooling channel [m] for long poloidal sections of blanket breeding zone
    nopol Input integer 2

    Number of poloidal sections in a liquid metal breeder/coolant channel for module/segment
    nopipes Input integer 4

    Number of Liquid metal breeder/coolant channels per module/segment
    den_liq Input real 9500.0

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

    Liquid metal
    wht_liq_ib Output real -

    Liquid metal
    wht_liq_ob Output real -

    Liquid metal
    specific_heat_liq Input real 190.0

    Liquid metal breeder/coolant specific heat [J kg^-1 K^-1]
    thermal_conductivity_liq Input real 30.0

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

    Liquid metal breeder/coolant dynamic viscosity [Pa s]
    electrical_conductivity_liq Output real -

    Liquid metal breeder/coolant electrical conductivity [Ohm m]
    hartmann_liq Output real -

    Hartmann number
    b_mag_blkt Input real [5. 5.]

    Toroidal Magnetic feild strength for IB/OB blanket [T]
    etaiso_liq Input real 0.85

    Isentropic efficiency of blanket liquid breeder/coolant pumps
    blpressure_liq Input real 1700000.0

    blanket liquid metal breeder/coolant pressure [Pa]
    inlet_temp_liq Input real 570.0

    Inlet (scan var 68) and Outlet (scan var 69) temperature of the liquid breeder/coolant [K]
    outlet_temp_liq Input real 720.0

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

    Density of the FW primary coolant
    visc_fw Output real -

    Viscosity of the FW primary coolant
    rhof_bl Output real -

    Density of the blanket primary coolant
    visc_bl Output real -

    Viscosity of the blanket primary coolant
    cp_fw Output real -

    Spesific heat for FW and blanket primary coolant(s)
    cv_fw Output real -

    Spesific heat for FW and blanket primary coolant(s)
    cp_bl Output real -

    Spesific heat for FW and blanket primary coolant(s)
    cv_bl Output real -

    Spesific heat for FW and blanket primary coolant(s)
    f_nuc_pow_bz_struct Input real 0.34

    For a dual-coolant blanket, fraction of BZ power cooled by primary coolant
    f_nuc_pow_bz_liq Input real 0.66

    For a dual-coolant blanket, fraction of BZ self-cooled power (secondary coolant)
    pnuc_fw_ratio_dcll Input real 0.14

    For a dual-coolant blanket, ratio of FW/Blanket nuclear power as fraction of total
    pnuc_blkt_ratio_dcll Input real 0.86

    For a dual-coolant blanket, ratio of FW/Blanket nuclear power as fraction of total
    bzfllengi_n_rad Input integer 4

    Number of radial and poloidal sections that make up the total primary coolant flow length in a blanket module (IB and OB)
    bzfllengi_n_pol Input integer 2

    Number of radial and poloidal sections that make up the total primary coolant flow length in a blanket module (IB and OB)
    bzfllengo_n_rad Input integer 4

    Number of radial and poloidal sections that make up the total primary coolant flow length in a blanket module (IB and OB)
    bzfllengo_n_pol Input integer 2

    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 Input integer 2

    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 Input integer 2

    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 Input integer 2

    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 Input integer 2

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

    constraint_variables

    Name Type Datatype Default Value Description
    auxmin Input real 0.1

    minimum auxiliary power (MW) (constraint equation 40)
    betpmx Input real 0.19

    maximum poloidal beta (constraint equation 48)
    bigqmin Input real 10.0

    minimum fusion gain Q (constraint equation 28)
    bmxlim Input real 12.0

    maximum peak toroidal field (T) (constraint equation 25)
    fauxmn Input real 1.0

    f-value for minimum auxiliary power (constraint equation 40, iteration variable 64)
    fbeta Input real 1.0

    f-value for epsilon beta-poloidal (constraint equation 6, iteration variable 8)
    fbetap Input real 1.0

    f-value for poloidal beta (constraint equation 48, iteration variable 79)
    fbetatry Input real 1.0

    f-value for beta limit (constraint equation 24, iteration variable 36)
    fbetatry_lower Input real 1.0

    f-value for (lower) beta limit (constraint equation 84, iteration variable 173)
    fcpttf Input real 1.0

    f-value for TF coil current per turn upper limit (constraint equation 77, iteration variable 146)
    fcwr Input real 1.0

    f-value for conducting wall radius / rminor limit (constraint equation 23, iteration variable 104)
    fdene Input real 1.0

    f-value for density limit (constraint equation 5, iteration variable 9) (invalid if ipedestal=3)
    fdivcol Input real 1.0

    f-value for divertor collisionality (constraint equation 22, iteration variable 34)
    fdtmp Input real 1.0

    f-value for first wall coolant temperature rise (constraint equation 38, iteration variable 62)
    fecrh_ignition Input real 1.0

    f-value for ecrh ignition constraint (constraint equation 91, iteration variable 168)
    fflutf Input real 1.0

    f-value for neutron fluence on TF coil (constraint equation 53, iteration variable 92)
    ffuspow Input real 1.0

    f-value for maximum fusion power (constraint equation 9, iteration variable 26)
    fgamcd Input real 1.0

    f-value for current drive gamma (constraint equation 37, iteration variable 40)
    fhldiv Input real 1.0

    f-value for divertor heat load (constraint equation 18, iteration variable 27)
    fiooic Input real 0.5

    f-value for TF coil operating current / critical current ratio (constraint equation 33, iteration variable 50)
    fipir Input real 1.0

    f-value for Ip/Irod upper limit constraint equation icc = 46 iteration variable ixc = 72
    fjohc Input real 1.0

    f-value for central solenoid current at end-of-flattop (constraint equation 26, iteration variable 38)
    fjohc0 Input real 1.0

    f-value for central solenoid current at beginning of pulse (constraint equation 27, iteration variable 39)
    fjprot Input real 1.0

    f-value for TF coil winding pack current density (constraint equation 35, iteration variable 53)
    flhthresh Input real 1.0

    f-value for L-H power threshold (constraint equation 15, iteration variable 103)
    fmva Input real 1.0

    f-value for maximum MVA (constraint equation 19, iteration variable 30)
    fnbshinef Input real 1.0

    f-value for maximum neutral beam shine-through fraction (constraint equation 59, iteration variable 105)
    fncycle Input real 1.0

    f-value for minimum CS coil stress load cycles (constraint equation 90, iteration variable 167)
    fnesep Input real 1.0

    f-value for Eich critical separatrix density (constraint equation 76, iteration variable 144)
    foh_stress Input real 1.0

    f-value for Tresca yield criterion in Central Solenoid (constraint equation 72, iteration variable 123)
    fpeakb Input real 1.0

    f-value for maximum toroidal field (constraint equation 25, iteration variable 35)
    fpinj Input real 1.0

    f-value for injection power (constraint equation 30, iteration variable 46)
    fpnetel Input real 1.0

    f-value for net electric power (constraint equation 16, iteration variable 25)
    fportsz Input real 1.0

    f-value for neutral beam tangency radius limit (constraint equation 20, iteration variable 33)
    fpsepbqar Input real 1.0

    f-value for maximum Psep*Bt/qAR limit (constraint equation 68, iteration variable 117)
    fpsepr Input real 1.0

    f-value for maximum Psep/R limit (constraint equation 56, iteration variable 97)
    fptemp Input real 1.0

    f-value for peak centrepost temperature (constraint equation 44, iteration variable 68)
    fptfnuc Input real 1.0

    f-value for maximum TF coil nuclear heating (constraint equation 54, iteration variable 95)
    fq Input real 1.0

    f-value for edge safety factor (constraint equation 45, iteration variable 71)
    fqval Input real 1.0

    f-value for Q (constraint equation 28, iteration variable 45)
    fradpwr Input real 0.99

    f-value for core radiation power limit (constraint equation 17, iteration variable 28)
    fradwall Input real 1.0

    f-value for upper limit on radiation wall load (constr. equ. 67, iteration variable 116)
    freinke Input real 1.0

    f-value for Reinke detachment criterion (constr. equ. 78, iteration variable 147)
    frminor Input real 1.0

    f-value for minor radius limit (constraint equation 21, iteration variable 32)
    fstrcase Input real 1.0

    f-value for maximum TF coil case Tresca yield criterion (constraint equation 31, iteration variable 48)
    fstrcond Input real 1.0

    f-value for maxiumum TF coil conduit Tresca yield criterion (constraint equation 32, iteration variable 49)
    fstr_wp Input real 1.0

    f-value for maxiumum TF coil strain absolute value (constraint equation 88, iteration variable 165)
    fmaxvvstress Input real 1.0

    f-value for maximum permitted stress of the VV (constraint equation 65, iteration variable 113)
    ftbr Input real 1.0

    f-value for minimum tritium breeding ratio (constraint equation 52, iteration variable 89)
    ftburn Input real 1.0

    f-value for minimum burn time (constraint equation 13, iteration variable 21)
    ftcycl Input real 1.0

    f-value for cycle time (constraint equation 42, iteration variable 67)
    ftmargoh Input real 1.0

    f-value for central solenoid temperature margin (constraint equation 60, iteration variable 106)
    ftmargtf Input real 1.0

    f-value for TF coil temperature margin (constraint equation 36, iteration variable 54)
    ftohs Input real 1.0

    f-value for plasma current ramp-up time (constraint equation 41, iteration variable 66)
    ftpeak Input real 1.0

    f-value for first wall peak temperature (constraint equation 39, iteration variable 63)
    fvdump Input real 1.0

    f-value for dump voltage (constraint equation 34, iteration variable 51)
    fvs Input real 1.0

    f-value for flux-swing (V-s) requirement (STEADY STATE) (constraint equation 12, iteration variable 15)
    fvvhe Input real 1.0

    f-value for vacuum vessel He concentration limit (iblanket = 2) (constraint equation 55, iteration variable 96)
    fwalld Input real 1.0

    f-value for maximum wall load (constraint equation 8, iteration variable 14)
    fzeffmax Input real 1.0

    f-value for maximum zeff (constraint equation 64, iteration variable 112)
    gammax Input real 2.0

    maximum current drive gamma (constraint equation 37)
    maxradwallload Input real 1.0

    Maximum permitted radiation wall load (MW/m^2) (constraint equation 67)
    mvalim Input real 40.0

    maximum MVA limit (constraint equation 19)
    nbshinefmax Input real 0.001

    maximum neutral beam shine-through fraction (constraint equation 59)
    nflutfmax Input real 1e+23

    max fast neutron fluence on TF coil (n/m2) (blktmodel>0) (constraint equation 53) Also used for demontable magnets (itart = 1) and superconducting coils (i_tf_sup = 1) To set the CP lifetime (constraint equation 85)
    pdivtlim Input real 150.0

    Minimum pdivt [MW] (constraint equation 80)
    peakfactrad Input real 3.33

    peaking factor for radiation wall load (constraint equation 67)
    peakradwallload Output real -

    Peak radiation wall load (MW/m^2) (constraint equation 67)
    pnetelin Input real 1000.0

    required net electric power (MW) (constraint equation 16)
    powfmax Input real 1500.0

    maximum fusion power (MW) (constraint equation 9)
    psepbqarmax Input real 9.5

    maximum ratio of Psep*Bt/qAR (MWT/m) (constraint equation 68)
    pseprmax Input real 25.0

    maximum ratio of power crossing the separatrix to plasma major radius (Psep/R) (MW/m) (constraint equation 56)
    ptfnucmax Input real 0.001

    maximum nuclear heating in TF coil (MW/m3) (constraint equation 54)
    tbrmin Input real 1.1

    minimum tritium breeding ratio (constraint equation 52)
    tbrnmn Input real 1.0

    minimum burn time (s) (KE - no longer itv., see issue #706)
    tcycmn Output real -

    minimum cycle time (s) (constraint equation 42)
    tohsmn Input real 1.0

    minimum plasma current ramp-up time (s) (constraint equation 41)
    vvhealw Input real 1.0

    allowed maximum helium concentration in vacuum vessel at end of plant life (appm) (iblanket =2) (constraint equation 55)
    walalw Input real 1.0

    allowable neutron wall-load (MW/m2) (constraint equation 8)
    taulimit Input real 5.0

    Lower limit on taup/taueff the ratio of alpha particle to energy confinement times (constraint equation 62)
    ftaulimit Input real 1.0

    f-value for lower limit on taup/taueff the ratio of alpha particle to energy confinement times (constraint equation 62, iteration variable 110)
    fniterpump Input real 1.0

    f-value for constraint that number of pumps < tfno (constraint equation 63, iteration variable 111)
    zeffmax Input real 3.6

    maximum value for Zeff (constraint equation 64)
    fpoloidalpower Input real 1.0

    f-value for constraint on rate of change of energy in poloidal field (constraint equation 66, iteration variable 115)
    fpsep Input real 1.0

    f-value to ensure separatrix power is less than value from Kallenbach divertor (Not required as constraint 69 is an equality)
    fcqt Input real 1.0

    TF coil quench temparature remains below tmax_croco (constraint equation 74, iteration variable 141)

    cs_fatigue_variables

    Name Type Datatype Default Value Description
    residual_sig_hoop Input real 240000000.0

    residual hoop stress in strucutal material (Pa)
    n_cycle Output real -

    Allowable number of cycles for CS stress model
    n_cycle_min Input real 20000.0

    Minimum llowable number of cycles for CS stress model
    t_crack_radial Input real 0.006

    Initial depth of crack in thickness of conduit (m)
    t_crack_vertical Input real 0.00089

    Inital vertical crack size (m)
    t_structural_radial Input real 0.07

    Thickness of CS conductor conduit (m)
    t_structural_vertical Input real 0.022

    Vertical thickness of CS conductor conduit (m)
    bkt_life_csf Output real -

    Switch to pass bkt_life cycles to n_cycle_min
    sf_vertical_crack Input real 2.0

    Safety factor for vertical crack size (-)
    sf_radial_crack Input real 2.0

    Safety factor for radial crack size (-)
    sf_fast_fracture Input real 1.5

    safety factor for stress intensity factor (-)
    paris_coefficient Input real 6.5e-13

    Paris equation material coefficient (-)
    paris_power_law Input real 3.5

    Paris equation material power law (-)
    walker_coefficient Input real 0.436

    walker coefficent (-)
    fracture_toughness Input real 200.0

    fracture toughness (MPa m^1/2)

    pf_power_variables

    Name Type Datatype Default Value Description
    acptmax Output real -

    average of currents in PF circuits (kA)
    ensxpfm Output real -

    maximum stored energy in the PF circuits (MJ)
    iscenr Input integer 2

    Switch for PF coil energy storage option:

    • =1 all power from MGF (motor-generator flywheel) units
    • =2 all pulsed power from line
    • =3 PF power from MGF, heating from line
    pfckts Output real -

    number of PF coil circuits
    spfbusl Output real -

    total PF coil circuit bus length (m)
    spsmva Output real -

    sum of PF power supply ratings (MVA)
    srcktpm Output real -

    sum of resistive PF coil power (kW)
    vpfskv Output real -

    PF coil voltage (kV)
    peakpoloidalpower Output real -

    Peak absolute rate of change of stored energy in poloidal field (MW)
    maxpoloidalpower Input real 1000.0

    Maximum permitted absolute rate of change of stored energy in poloidal field (MW)
    poloidalpower Output real -

    Poloidal power usage at time t (MW)

    define_iteration_variables

    Name Type Datatype Default Value Description
    dummy Output real -

    tfcoil_variables

    Name Type Datatype Default Value Description
    acasetf Output real -

    external case area per coil (inboard leg) (m2)
    acasetfo Output real -

    external case area per coil (outboard leg) (m2)
    acndttf Output real -

    area of the cable conduit (m2)
    acond Output real -

    Winding pack conductor area [m2] Does not include the area of voids and central helium channel
    acstf Output real -

    Cable space area (per turn) [m2] Includes the area of voids and central helium channel
    insulation_area Output real -

    single turn insulation area (m2)
    aiwp Output real -

    winding pack turn insulation area per coil (m2)
    sig_tf_case_max Input real 600000000.0

    Allowable maximum shear stress (Tresca criterion) in TF coil case (Pa)
    sig_tf_wp_max Input real 600000000.0

    Allowable maximum shear stress (Tresca criterion) in TF coil conduit (Pa)

    Allowable Tresca stress in TF coil structural material (Pa)
    arealeg Output real -

    outboard TF leg area (m2)
    aswp Output real -

    winding pack structure area (m2)
    avwp Output real -

    winding pack void (He coolant) area (m2)
    awphec Output real -

    winding pack He coil area (m2)
    bcritsc Input real 24.0

    upper critical field (T) for Nb3Sn superconductor at zero temperature and strain (i_tf_sc_mat=4, =bc20m)
    bmaxtf Output real -

    mean peak field at TF coil (T)
    bmaxtfrp Output real -

    peak field at TF conductor with ripple (T)
    casestr Output real -

    case strain
    casthi Output real -

    inboard TF coil case plasma side thickness (m) (calculated for stellarators)
    casthi_fraction Input real 0.05

    inboard TF coil case plasma side thickness as a fraction of tfcth
    casthi_is_fraction Output logical -

    logical switch to make casthi a fraction of TF coil thickness (casthi_fraction)
    casths Output real -

    inboard TF coil sidewall case thickness (m) (calculated for stellarators)
    casths_fraction Input real 0.06

    inboard TF coil sidewall case thickness as a fraction of tftort
    tfc_sidewall_is_fraction Output logical -

    logical switch to make casths a fraction of TF coil thickness (casths_fraction)
    t_conductor Output real -

    Conductor (cable + steel conduit) area averaged dimension [m]
    t_turn_tf Output real -

    TF coil turn edge length including turn insulation [m] If the turn is not a square (i_tf_turns_integer = 1) a squared turn of equivelent size is use to calculated this quantity If the t_turn_tf is non zero, cpttf is calculated
    t_turn_tf_is_input Output logical -

    Boolean switch to activated when the user set the TF coil turn dimensions Not an input
    f_t_turn_tf Input real 1.0

    f-value for TF turn edge length constraint If the turn is not a square (i_tf_turns_integer = 1) a squared turn of equivelent size is use for this constraint iteration variable ixc = 175 constraint equation icc = 86
    t_turn_tf_max Input real 0.05000000074505806

    TF turn edge length including turn insulation upper limit [m] If the turn is not a square (i_tf_turns_integer = 1) a squared turn of equivelent size is use for this constraint constraint equation icc = 86
    t_cable_tf Output real -

    TF coil superconducting cable squared/rounded dimensions [m] If the turn is not a square (i_tf_turns_integer = 1) a squared cable of equivelent size is use to calculated this quantity If the t_cable_tf is non zero, cpttf is calculated
    t_cable_tf_is_input Output logical -

    Boolean switch to activated when the user set the TF coil cable dimensions Not an input
    acs Output real -

    Area of space inside conductor (m2)
    cdtfleg Output real -

    TF outboard leg current density (A/m2) (resistive coils only)
    cforce Output real -

    centering force on inboard leg (per coil) (N/m)
    cplen Output real -

    length of TF coil inboard leg ('centrepost') (i_tf_sup = 1)
    cpttf Input real 70000.0

    TF coil current per turn (A). (calculated for stellarators) (calculated for integer-turn TF coils i_tf_turns_integer=1) (iteration variable 60)
    cpttf_max Input real 90000.0

    Max TF coil current per turn [A]. (for stellarators and i_tf_turns_integer=1) (constraint equation 77)
    dcase Input real 8000.0

    density of coil case (kg/m3)
    dcond Input real [6080. 6080. 6070. 6080. 6080. 8500. 6070. 8500. 8500.]

    density of superconductor type given by i_tf_sc_mat/isumatoh/isumatpf (kg/m3)
    dcondins Input real 1800.0

    density of conduit + ground-wall insulation (kg/m3)
    dhecoil Input real 0.005

    diameter of central helium channel in TF winding (m)
    estotftgj Output real -

    total stored energy in the toroidal field (GJ)
    b_crit_upper_nbti Input real 14.86

    upper critical field of GL_nbti
    t_crit_nbti Input real 9.04

    critical temperature of GL_nbti
    max_force_density Output real -

    Maximal (WP averaged) force density in TF coils at 1 point. (MN/m3)
    fcutfsu Input real 0.69

    copper fraction of cable conductor (TF coils) (iteration variable 59)
    fhts Input real 0.5

    technology adjustment factor for critical current density fit for isumat..=2 Bi-2212 superconductor, to describe the level of technology assumed (i.e. to account for stress, fatigue, radiation, AC losses, joints or manufacturing variations; 1.0 would be very optimistic)
    insstrain Output real -

    Radial strain in insulator
    i_tf_stress_model Input integer 1

    Switch for the TF coil stress model 0 : Generalized plane strain formulation, Issues #977 and #991, O(n^3) 1 : Old plane stress model (only for SC) 2 : Axisymmetric extended plane strain, Issues #1414 and #998, O(n)
    i_tf_tresca Output integer -

    Switch for TF coil conduit Tresca stress criterion: 0 : Tresca (no adjustment); 1 : Tresca with CEA adjustment factors (radial+2%, vertical+60%)

    i_tf_wp_geom Input integer -1

    Switch for TF WP geometry selection 0 : Rectangular geometry 1 : Double rectangular geometry 2 : Trapezoidal geometry (constant lateral casing thickness) Default setting for backward compatibility if i_tf_turns_integer = 0 : Double rectangular if i_tf_turns_integer = 1 : Rectangular
    i_tf_case_geom Output integer -

    Switch for TF case geometry selection 0 : Circular front case (ITER design) 1 : Straight front case
    i_tf_turns_integer Output integer -

    Switch for TF coil integer/non-integer turns: 0 : non-integer turns 1 : integer turns
    i_tf_sc_mat Input integer 1

    Switch for superconductor material in TF 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
    i_tf_sup Input integer 1

    Switch for TF coil conductor model:

    • =0 copper
    • =1 superconductor
    • =2 Cryogenic aluminium
    i_tf_shape Output integer -

    Switch for TF coil toroidal shape:

    • =0 Default value : Picture frame coil for TART / PROCESS D-shape for non itart
    • =1 PROCESS D-shape : parametrise with 2 arcs
    • =2 Picture frame coils
    i_tf_cond_eyoung_axial Output integer -

    Switch for the behavior of the TF coil conductor elastic axial properties

    • =0 Young's modulus is set to zero, and the conductor is not considered in the stress calculation. This corresponds to the case that the conductor is much less stiff than the conduit, or the case that the conductor is prevented (isolated) from taking axial loads.
    • =1 Elastic properties are set by user input, using the variable eyoung_cond_axial
    • =2 Elastic properties are set to reasonable defaults taking into account the superconducting material i_tf_sc_mat
    i_tf_cond_eyoung_trans Input integer 1

    Switch for the behavior of the elastic properties of the TF coil conductorin the transverse direction. Only active if i_tf_cond_eyoung_axial == 2

    • =0 Cable not potted in solder. Transverse Young's modulus set to zero.
    • =1 Cable potted in solder. If i_tf_cond_eyoung_axial == 2, the transverse Young's modulus of the conductor is equal to the axial, which is set to a sensible material-dependent default.
    n_pancake Input integer 10

    Number of pancakes in TF coil. Only used if i_tf_turns_integer=1
    n_layer Input integer 20

    Number of layers in TF coil. Only used if i_tf_turns_integer=1
    n_rad_per_layer Input integer 100

    Size of the arrays per layers storing the radial dependent stress quantities (stresses, strain displacement etc..)
    i_tf_bucking Input integer -1

    Switch for TF inboard suport structure design:

    Default setting for backward compatibility - if copper resistive TF (i_tf_sup = 0) : Free standing TF without bucking structure - if Superconducting TF (i_tf_sup = 1) : Free standing TF with a steel casing - if aluminium TF (i_tf_sup = 2) : Free standing TF with a bucking structure Rem : the case is a bucking structure - =0 : Free standing TF without case/bucking cyliner (only a conductor layer) - =1 : Free standing TF with a case/bucking cylinder made of - if copper resistive TF (i_tf_sup = 0) : used defined bucking cylinder - if Superconducting TF (i_tf_sup = 1) : Steel casing - if aluminium resisitive TF (i_tf_sup = 2) : used defined bucking cylinder - =2 : The TF is in contact with the CS : "bucked and wedged design" Fast version : thin TF-CS interface neglected in the stress calculations (3 layers) The CS is frictionally decoupled from the TF, does not carry axial tension - =3 : The TF is in contact with the CS : "bucked and wedged design" Full version : thin TF-CS Kapton interface introduced in the stress calculations (4 layers) The CS and kaptop are frictionally decoupled from the TF, do not carry axial tension
    n_tf_graded_layers Input integer 1

    Number of layers of different stress properties in the WP. If n_tf_graded_layers > 1, a graded coil is condidered
    n_tf_stress_layers Output integer -

    Number of layers considered for the inboard TF stress calculations set in initial.f90 from i_tf_bucking and n_tf_graded_layers
    n_tf_wp_layers Input integer 5

    Maximum number of layers that can be considered in the TF coil composited/smeared stress analysis. This is the layers of one turn, not the entire WP. Default: 5. void, conductor, copper, conduit, insulation.
    jbus Input real 1250000.0

    bussing current density (A/m2)
    j_crit_str_tf Output real -

    j_crit_str : superconductor strand critical current density under operating conditions (A/m2). Necessary for the cost calculation in $/kAm
    j_crit_str_0 Input real [5.96905476e+08 1.92550153e+09 7.24544683e+08 5.49858624e+08 6.69284510e+08 0.00000000e+00 8.98964415e+08 1.15875300e+09 8.65652123e+08]

    j_crit_str_pf_0 : superconductor strand critical current density at 6 T and 4.2 K (A/m2) Necessary for the cost calculation in $/kAm
    jwdgcrt Output real -

    critical current density for winding pack (A/m2)
    jwdgpro Output real -

    allowable TF coil winding pack current density, for dump temperature rise protection (A/m2)
    jwptf Output real -

    winding pack engineering current density (A/m2)
    oacdcp Output real -

    Overall current density in TF coil inboard legs midplane (A/m2) Rem SK : Not used in tfcoil to set the current any more. Should not be used as iteration variable 12 any more. It is now calculated.
    eyoung_ins Input real 100000000.0

    Insulator Young's modulus [Pa]. Default value (1.0D8) setup the following values - SC TF, eyoung_ins = 20 Gpa (default value from DDD11-2 v2 2 (2009)) - Al TF, eyoung_ins = 2.5 GPa (Kapton polymer)
    eyoung_steel Input real 205000000000.0

    Steel case Young's modulus (Pa) (default value from DDD11-2 v2 2 (2009))
    eyoung_cond_axial Input real 660000000.0

    SC TF coil conductor Young's modulus in the parallel (along the wire/tape) direction [Pa] Set by user input only if i_tf_cond_eyoung_axial == 1; otherwise set by the behavior of that switch.
    eyoung_cond_trans Output real -

    SC TF coil conductor Young's modulus in the transverse direction [Pa] Set by user input only if i_tf_cond_eyoung_axial == 1; otherwise set by the behavior of that switch.
    eyoung_res_tf_buck Input real 150000000000.0

    Resistive TF magnets bucking cylinder young modulus (Pa)
    eyoung_copper Input real 117000000000.0

    Copper young modulus. Default value taken from wikipedia
    eyoung_al Input real 69000000000.0

    Aluminium young modulus. Default value taken from wikipedia
    poisson_steel Input real 0.3

    Steel Poisson's ratio, Source : https://www.engineeringtoolbox.com/metals-poissons-ratio-d_1268.html
    poisson_copper Input real 0.35

    Copper Poisson's ratio. Source : https://www.engineeringtoolbox.com/poissons-ratio-d_1224.html
    poisson_al Input real 0.35

    Aluminium Poisson's ratio. Source : https://www.engineeringtoolbox.com/poissons-ratio-d_1224.html
    poisson_ins Input real 0.34

    Insulation Poisson's ratio. Default: Kapton. Source : DuPont™ Kapton® HN datasheet.
    poisson_cond_axial Input real 0.30000001192092896

    SC TF coil conductor Poisson's ratio in the parallel-transverse direction
    poisson_cond_trans Input real 0.30000001192092896

    SC TF coil conductor Poisson's ratio in the transverse-transverse direction
    rbmax Output real -

    Radius of maximum TF B-field (m)
    tflegres Output real -

    TF coil leg resistance (ohm)
    toroidalgap Input real 1.0

    Minimal distance between two toroidal coils. (m)
    ftoroidalgap Input real 1.0

    F-value for minimum tftort (constraint equation 82)
    ripmax Input real 1.0

    aximum allowable toroidal field ripple amplitude at plasma edge (%)
    ripple Output real -

    peak/average toroidal field ripple at plasma edge (%)
    ritfc Output real -

    total (summed) current in TF coils (A)
    n_radial_array Parameter integer 50

    Size of the radial distribution arrays per layers used for stress, strain and displacement distibution
    radial_array Output real -

    Array refining the radii of the stress calculations arrays
    sig_tf_r Output real -

    TF Inboard leg radial stress in steel r distribution at mid-plane [Pa]
    sig_tf_t Output real -

    TF Inboard leg tangential stress in steel r distribution at mid-plane [Pa]
    deflect Output real -

    TF coil radial deflection (displacement) radial distribution [m]
    sig_tf_z Output real -

    TF Inboard leg vertical tensile stress in steel at mid-plane [Pa]
    sig_tf_vmises Output real -

    TF Inboard leg Von-Mises stress in steel r distribution at mid-plane [Pa]
    sig_tf_tresca Output real -

    TF Inboard leg maximum shear stress (Tresca criterion) in steel r distribution at mid-plane [Pa]
    sig_tf_cs_bucked Output real -

    Maximum shear stress (Tresca criterion) in CS structures at CS flux swing [Pa]:

    • If superconducting CS (ipfres = 0): turn steel conduits stress
    • If resistive CS (ipfres = 1): copper conductor stress

    Quantity only computed for bucked and wedged design (i_tf_bucking >= 2) Def : CS Flux swing, instant when the current changes sign in CS (null current)
    sig_tf_case Output real -

    Maximum shear stress (Tresca criterion) in TF casing steel structures (Pa)
    sig_tf_wp Output real -
    str_cs_con_res Input real -0.005

    Residual manufacturing strain in CS superconductor material
    str_pf_con_res Input real -0.005

    Residual manufacturing strain in PF superconductor material
    str_tf_con_res Input real -0.005

    Residual manufacturing strain in TF superconductor material If i_str_wp == 0, used to compute the critical surface. Otherwise, the self-consistent winding pack str_wp is used.
    str_wp Output real -

    Axial (vertical) strain in the TF coil winding pack found by self-consistent stress/strain calculation. if i_str_wp == 1, used to compute the critical surface. Otherwise, the input value str_tf_con_res is used. Constrain the absolute value using constraint equation 88 You can't have constraint 88 and i_str_wp = 0 at the same time
    str_wp_max Input real 0.007

    Maximum allowed absolute value of the strain in the TF coil (Constraint equation 88)
    i_str_wp Input integer 1

    Switch for the behavior of the TF strain used to compute the strain-dependent critical surface:

    • =0 str_tf_con_res is used
    • =1 str_wp is used
    quench_model Input character b'exponential '

    switch for TF coil quench model (Only applies to REBCO magnet at present, issue #522):

    • ='exponential' exponential quench with constant discharge resistor
    • ='linear' quench with constant voltage
    time1 Output real -

    Time at which TF quench is detected (s)
    tcritsc Input real 16.0

    critical temperature (K) for superconductor at zero field and strain (i_tf_sc_mat=4, =tc0m)
    tdmptf Input real 10.0

    fast discharge time for TF coil in event of quench (s) (iteration variable 56)

    For REBCO model, meaning depends on quench_model:

    • exponential quench : e-folding time (s)`
    • linear quench : discharge time (s)
    tfareain Output real -

    Area of inboard midplane TF legs (m2)
    tfbusl Output real -

    TF coil bus length (m)
    tfbusmas Output real -

    TF coil bus mass (kg)
    tfckw Output real -

    available DC power for charging the TF coils (kW)
    tfcmw Output real -

    Peak power per TF power supply (MW)
    tfcpmw Output real -

    Peak resistive TF coil inboard leg power (MW)
    tfjtsmw Output real -

    TF joints resistive power losses (MW)
    tfcryoarea Output real -

    surface area of toroidal shells covering TF coils (m2)
    tficrn Output real -

    TF coil half-width - inner bore (m)
    tfind Output real -

    TF coil inductance (H)
    tfinsgap Input real 0.01

    TF coil WP insertion gap (m)
    tflegmw Output real -

    TF coil outboard leg resistive power (MW)
    rhocp Output real -

    TF coil inboard leg resistivity [Ohm-m]. If itart=0, this variable is the average resistivity over the whole magnet
    rhotfleg Output real -

    Resistivity of a TF coil leg (Ohm-m)
    rhotfbus Input real 2.62e-08

    Resistivity of a TF coil bus (Ohm-m). Default value takes the same res as the leg one
    frhocp Input real 1.0

    Centrepost resistivity enhancement factor. For itart=0, this factor is used for the whole magnet
    frholeg Input real 1.0

    Ouboard legs resistivity enhancement factor. Only used for itart=1.
    i_cp_joints Input integer -1

    Switch for CP demoutable joints type -= 0 : Clampled joints -= 1 : Sliding joints Default value (-1) choses : Sliding joints for resistive magnets (i_tf_sup = 0, 2) Clampled joints for superconducting magents (i_tf_sup = 1)
    rho_tf_joints Input real 2.5e-10

    TF joints surfacic resistivity [ohm.m]. Feldmetal joints assumed.
    n_tf_joints_contact Input integer 6

    Number of contact per turn
    n_tf_joints Input integer 4

    Number of joints Ex: n_tf_joints = 2 for top and bottom CP joints
    th_joint_contact Input real 0.03

    TF sliding joints contact pad width [m]
    pres_joints Output real -

    Calculated TF joints resistive power losses [W]
    tfleng Output real -

    TF coil circumference (m)
    eff_tf_cryo Input real -1.0

    TF cryoplant efficiency (compared to pefect Carnot cycle). Using -1 set the default value depending on magnet technology:

    • i_tf_sup = 1 : SC magnet, eff_tf_cryo = 0.13 (ITER design)
    • i_tf_sup = 2 : Cryo-aluminium, eff_tf_cryo = 0.4
    n_tf Input real 16.0

    Number of TF coils (default = 50 for stellarators). Number of TF coils outer legs for ST
    tfocrn Output real -

    TF coil half-width - outer bore (m)
    tfsai Output real -

    area of the inboard TF coil legs (m2)
    tfsao Output real -

    area of the outboard TF coil legs (m2)
    tftmp Input real 4.5

    peak helium coolant temperature in TF coils and PF coils (K)
    tftort Input real 1.0

    TF coil toroidal thickness (m)
    thicndut Input real 0.0008

    conduit insulation thickness (m)
    layer_ins Output real -

    Additional insulation thickness between layers (m)
    thkcas Input real 0.3

    inboard TF coil case outer (non-plasma side) thickness (m) (iteration variable 57) (calculated for stellarators)
    dr_tf_wp Output real -

    radial thickness of winding pack (m) (iteration variable 140) (issue #514)
    thwcndut Input real 0.008

    TF coil conduit case thickness (m) (iteration variable 58)
    tinstf Input real 0.018

    Thickness of the ground insulation layer surrounding (m) - Superconductor TF (i_tf_sup == 1) : The TF coil Winding packs - Resistive magnets (i_tf_sup /= 1) : The TF coil wedges Rem : Thickness calculated for stellarators.
    tmargmin_tf Output real -

    minimum allowable temperature margin : TF coils (K)
    tmargmin_cs Output real -

    minimum allowable temperature margin : CS (K)
    tmargmin Output real -

    minimum allowable temperature margin : TFC AND CS (K)
    temp_margin Output real -

    temperature margin (K)
    tmargtf Output real -

    TF coil temperature margin (K)
    tmaxpro Input real 150.0

    maximum temp rise during a quench for protection (K)
    tmax_croco Input real 200.0

    CroCo strand: maximum permitted temp during a quench (K)
    croco_quench_temperature Output real -

    CroCo strand: Actual temp reached during a quench (K)
    tmpcry Input real 4.5

    coil temperature for cryogenic plant power calculation (K)
    n_tf_turn Output real -

    number of turns per TF coil
    vdalw Input real 20.0

    max voltage across TF coil during quench (kV) (iteration variable 52)
    vforce Output real -

    vertical tension on inboard leg/coil (N)
    f_vforce_inboard Input real 0.5

    Fraction of the total vertical force taken by the TF inboard leg tension Not used for resistive itart=1 (sliding joints)
    vforce_outboard Output real -

    Vertical tension on outboard leg/coil (N)
    vftf Input real 0.4

    coolant fraction of TFC 'cable' (i_tf_sup=1), or of TFC leg (i_tf_ssup=0)
    voltfleg Output real -

    volume of each TF coil outboard leg (m3)
    vtfkv Output real -

    TF coil voltage for resistive coil including bus (kV)
    vtfskv Output real -

    voltage across a TF coil during quench (kV)
    whtcas Output real -

    mass per coil of external case (kg)
    whtcon Output real -

    TF coil conductor mass per coil (kg/coil). For itart=1, coil is return limb plus centrepost/n_tf
    whtconcu Output real -

    copper mass in TF coil conductor (kg/coil). For itart=1, coil is return limb plus centrepost/n_tf
    whtconal Output real -

    Aluminium mass in TF coil conductor (kg/coil). For itart=1, coil is return limb plus centrepost/n_tf
    whtconin Output real -

    conduit insulation mass in TF coil conductor (kg/coil)
    whtconsc Output real -

    superconductor mass in TF coil cable (kg/coil)
    whtconsh Output real -

    steel conduit mass in TF coil conductor (kg/coil)
    whtgw Output real -

    mass of ground-wall insulation layer per coil (kg/coil)
    whttf Output real -

    total mass of the TF coils (kg)
    wwp1 Output real -

    width of first step of winding pack (m)
    wwp2 Output real -

    width of second step of winding pack (m)
    dthet Output real -

    angle of arc i (rad)
    radctf Output real -

    radius of arc i (m)
    xarc Output real -

    x location of arc point i on surface (m)
    xctfc Output real -

    x location of arc centre i (m)
    yarc Output real -

    y location of arc point i on surface (m)
    yctfc Output real -

    y location of arc centre i (m)
    tfa Output real -

    Horizontal radius of inside edge of TF coil (m)
    tfb Output real -

    Vertical radius of inside edge of TF coil (m)
    drtop Output real -

    centrepost taper maximum radius adjustment (m)
    dztop Output real -

    centrepost taper height adjustment (m)
    etapump Input real 0.8

    centrepost coolant pump efficiency
    fcoolcp Input real 0.3

    coolant fraction of TF coil inboard legs (iteration variable 23)
    fcoolleg Input real 0.2

    coolant fraction of TF coil outboard legs
    a_cp_cool Output real -

    Centrepost cooling area toroidal cross-section (constant over the whole CP)
    ncool Output real -

    number of centrepost coolant tubes
    ppump Output real -

    centrepost coolant pump power (W)
    prescp Output real -

    resistive power in the centrepost (itart=1) [W]. If itart=0, this variable is the ressitive power on the whole magnet
    presleg Output real -

    Summed resistive power in the TF coil legs [W]. Remain 0 if itart=0.
    ptempalw Input real 473.15

    maximum peak centrepost temperature (K) (constraint equation 44)
    rcool Input real 0.005

    average radius of coolant channel (m) (iteration variable 69)
    tcoolin Input real 313.15

    centrepost coolant inlet temperature (K)
    dtiocool Output real -

    inlet / outlet TF coil coolant temperature rise (K)
    tcpav Input real 373.15

    Average temperature of centrepost called CP (K). Only used for resistive coils to compute the resisitive heating. Must be an iteration variable for ST (itart=1) (iteration variable 20)
    tcpav2 Output real -

    Computed centrepost average temperature (K) (for consistency)
    tlegav Input real -1.0

    Average temperature of the TF outboard legs [K]. If tlegav=-1.0, the ouboard legs and CP temperatures are the same. Fixed for now, should use a contraints eq like tcpav
    tcpmax Output real -

    peak centrepost temperature (K)
    vcool Input real 20.0

    inlet centrepost coolant flow speed at midplane (m/s) (iteration variable 70)
    vol_cond_cp Output real -

    Exact conductor volume in the centrepost (m3)
    whtcp Output real -

    mass of TF coil inboard legs (kg)
    whttflgs Output real -

    mass of the TF coil legs (kg)
    cryo_cool_req Output real -

    Cryo cooling requirement at helium temp 4.5K (kW)
    theta1_coil Input real 45.0

    The angle of the outboard arc forming the TF coil current center line [deg]
    theta1_vv Input real 1.0

    The angle of the outboard arc forming the Vacuum Vessel current center line [deg]
    max_vv_stress Input real 143000000.0

    The allowable peak maximum shear stress in the vacuum vessel due to quench and fast discharge of the TF coils [Pa]

    ife_variables

    Name Type Datatype Default Value Description
    maxmat Parameter integer 8

    Total number of materials in IFE device. Material numbers are as follows:

    • =0 void
    • =1 steel
    • =2 carbon cloth
    • =3 FLiBe
    • =4 lithium oxide Li2O
    • =5 concrete
    • =6 helium
    • =7 xenon
    • =8 lithium
    bldr Input real 1.0

    radial thickness of IFE blanket (m; calculated if ifetyp=4)
    bldrc Input real 1.0

    radial thickness of IFE curtain (m; ifetyp=4)
    bldzl Input real 4.0

    vertical thickness of IFE blanket below chamber (m)
    bldzu Input real 4.0

    vertical thickness of IFE blanket above chamber (m)
    blmatf Input real [[0.05 0. 0.45 0. 0.2 0. 0.3 0. 0. ] [0.05 0. 0.45 0. 0.2 0. 0.3 0. 0. ] [0.05 0. 0.45 0. 0.2 0. 0.3 0. 0. ]]

    IFE blanket material fractions
    blmatm Output real -

    IFE blanket material masses (kg)
    blmatv Output real -

    IFE blanket material volumes (m3)
    blvol Output real -

    IFE blanket volume (m3)
    cdriv0 Input real 154.3

    IFE generic/laser driver cost at edrive=0 (M$)
    cdriv1 Input real 163.2

    IFE low energy heavy ion beam driver cost extrapolated to edrive=0 (M$)
    cdriv2 Input real 244.9

    IFE high energy heavy ion beam driver cost extrapolated to edrive=0 (M$)
    cdriv3 Input real 1.463

    IFE driver cost ($/J wall plug) (ifedrv==3)
    chdzl Input real 9.0

    vertical thickness of IFE chamber below centre (m)
    chdzu Input real 9.0

    vertical thickness of IFE chamber above centre (m)
    chmatf Input real [1. 0. 0. 0. 0. 0. 0. 0. 0.]

    IFE chamber material fractions
    chmatm Output real -

    IFE chamber material masses (kg)
    chmatv Output real -

    IFE chamber material volumes (m3)
    chrad Input real 6.5

    radius of IFE chamber (m) (iteration variable 84)
    chvol Output real -

    IFE chamber volume (m3)
    dcdrv0 Input real 111.4

    IFE generic/laser driver cost gradient (M$/MJ)
    dcdrv1 Input real 78.0

    HIB driver cost gradient at low energy (M$/MJ)
    dcdrv2 Input real 59.9

    HIB driver cost gradient at high energy (M$/MJ)
    drveff Input real 0.28

    IFE driver wall plug to target efficiency (ifedrv=0,3) (iteration variable 82)
    edrive Input real 5000000.0

    IFE driver energy (J) (iteration variable 81)
    etadrv Output real -

    IFE driver wall plug to target efficiency
    etali Input real 0.4

    IFE lithium pump wall plug efficiency (ifetyp=4)
    etave Input real [0.082 0.079 0.076 0.073 0.069 0.066 0.062 0.059 0.055 0.051]

    IFE driver efficiency vs driver energy (ifedrv=-1)
    fauxbop Input real 0.06

    fraction of gross electric power to balance-of-plant (IFE)
    fbreed Input real 0.51

    fraction of breeder external to device core
    fburn Input real 0.3333

    IFE burn fraction (fraction of tritium fused/target)
    flirad Input real 0.78

    radius of FLiBe/lithium inlet (m) (ifetyp=3,4)
    frrmax Input real 1.0

    f-value for maximum IFE repetition rate (constraint equation 50, iteration variable 86)
    fwdr Input real 0.01

    radial thickness of IFE first wall (m)
    fwdzl Input real 0.01

    vertical thickness of IFE first wall below chamber (m)
    fwdzu Input real 0.01

    vertical thickness of IFE first wall above chamber (m)
    fwmatf Input real [[0.05 0. 0.95 0. 0. 0. 0. 0. 0. ] [0.05 0. 0.95 0. 0. 0. 0. 0. 0. ] [0.05 0. 0.95 0. 0. 0. 0. 0. 0. ]]

    IFE first wall material fractions
    fwmatm Output real -

    IFE first wall material masses (kg)
    fwmatv Output real -

    IFE first wall material volumes (kg)
    fwvol Output real -

    IFE first wall volume (m3)
    gain Output real -

    IFE target gain
    gainve Input real [ 60. 95. 115. 125. 133. 141. 152. 160. 165. 170.]

    IFE target gain vs driver energy (ifedrv=-1)
    htpmw_ife Output real -

    IFE heat transport system electrical pump power (MW)
    ife Output integer -

    Switch for IFE option:

    • =0 use tokamak, RFP or stellarator model
    • =1 use IFE model
    ifedrv Input integer 2

    Switch for type of IFE driver:

    • =-1 use gainve, etave for gain and driver efficiency
    • =0 use tgain, drveff for gain and driver efficiency
    • =1 use laser driver based on SOMBRERO design
    • =2 use heavy ion beam driver based on OSIRIS
    • =3 Input pfusife, rrin and drveff
    ifetyp Output integer -

    Switch for type of IFE device build:

    • =0 generic (cylindrical) build
    • =1 OSIRIS-like build
    • =2 SOMBRERO-like build
    • =3 HYLIFE-II-like build
    • =4 2019 build
    lipmw Output real -

    IFE lithium pump power (MW; ifetyp=4)
    mcdriv Input real 1.0

    IFE driver cost multiplier
    mflibe Output real -

    total mass of FLiBe (kg)
    pdrive Input real 23000000.0

    IFE driver power reaching target (W) (iteration variable 85)
    pfusife Input real 1000.0

    IFE input fusion power (MW) (ifedrv=3 only; itv 155)
    pifecr Input real 10.0

    IFE cryogenic power requirements (MW)
    ptargf Input real 2.0

    IFE target factory power at 6 Hz repetition rate (MW)
    r1 Output real -

    IFE device radial build (m)
    r2 Output real -

    IFE device radial build (m)
    r3 Output real -

    IFE device radial build (m)
    r4 Output real -

    IFE device radial build (m)
    r5 Output real -

    IFE device radial build (m)
    r6 Output real -

    IFE device radial build (m)
    r7 Output real -

    IFE device radial build (m)
    reprat Output real -

    IFE driver repetition rate (Hz)
    rrin Input real 6.0

    Input IFE repetition rate (Hz) (ifedrv=3 only; itv 156)
    rrmax Input real 20.0

    maximum IFE repetition rate (Hz)
    shdr Input real 1.7

    radial thickness of IFE shield (m)
    shdzl Input real 5.0

    vertical thickness of IFE shield below chamber (m)
    shdzu Input real 5.0

    vertical thickness of IFE shield above chamber (m)
    shmatf Input real [[0.05 0.19 0. 0. 0. 0.665 0.095 0. 0. ] [0.05 0.19 0. 0. 0. 0.665 0.095 0. 0. ] [0.05 0.19 0. 0. 0. 0.665 0.095 0. 0. ]]

    IFE shield material fractions
    shmatm Output real -

    IFE shield material masses (kg)
    shmatv Output real -

    IFE shield material volumes (kg)
    shvol Output real -

    IFE shield volume (m3)
    sombdr Input real 2.7

    radius of cylindrical blanket section below chamber (ifetyp=2)
    somtdr Input real 2.7

    radius of cylindrical blanket section above chamber (ifetyp=2)
    taufall Output real -

    Lithium Fall Time (s)
    tdspmw Input real 0.01

    IFE target delivery system power (MW)
    tfacmw Output real -

    IFE target factory power (MW)
    tgain Input real 85.0

    IFE target gain (if ifedrv = 0) (iteration variable 83)
    uccarb Input real 50.0

    cost of carbon cloth ($/kg)
    ucconc Input real 0.1

    cost of concrete ($/kg)
    ucflib Input real 84.0

    cost of FLiBe ($/kg)
    uctarg Input real 0.3

    cost of IFE target ($/target)
    v1dr Output real -

    radial thickness of IFE void between first wall and blanket (m)
    v1dzl Output real -

    vertical thickness of IFE void 1 below chamber (m)
    v1dzu Output real -

    vertical thickness of IFE void 1 above chamber (m)
    v1matf Input real [[1. 0. 0. 0. 0. 0. 0. 0. 0.] [1. 0. 0. 0. 0. 0. 0. 0. 0.] [1. 0. 0. 0. 0. 0. 0. 0. 0.]]

    IFE void 1 material fractions
    v1matm Output real -

    IFE void 1 material masses (kg)
    v1matv Output real -

    IFE void 1 material volumes (kg)
    v1vol Output real -

    IFE void 1 volume (m3)
    v2dr Input real 2.0

    radial thickness of IFE void between blanket and shield (m)
    v2dzl Input real 7.0

    vertical thickness of IFE void 2 below chamber (m)
    v2dzu Input real 7.0

    vertical thickness of IFE void 2 above chamber (m)
    v2matf Input real [[1. 0. 0. 0. 0. 0. 0. 0. 0.] [1. 0. 0. 0. 0. 0. 0. 0. 0.] [1. 0. 0. 0. 0. 0. 0. 0. 0.]]

    IFE void 2 material fractions
    v2matm Output real -

    IFE void 2 material masses (kg)
    v2matv Output real -

    IFE void 2 material volumes (kg)
    v2vol Output real -

    IFE void 2 volume (m3)
    v3dr Input real 43.3

    radial thickness of IFE void outside shield (m)
    v3dzl Input real 30.0

    vertical thickness of IFE void 3 below chamber (m)
    v3dzu Input real 20.0

    vertical thickness of IFE void 3 above chamber (m)
    v3matf Input real [[1. 0. 0. 0. 0. 0. 0. 0. 0.] [1. 0. 0. 0. 0. 0. 0. 0. 0.] [1. 0. 0. 0. 0. 0. 0. 0. 0.]]

    IFE void 3 material fractions
    v3matm Output real -

    IFE void 3 material masses (kg)
    v3matv Output real -

    IFE void 3 material volumes (kg)
    v3vol Output real -

    IFE void 3 volume (m3)
    zl1 Output real -

    IFE vertical build below centre (m)
    zl2 Output real -

    IFE vertical build below centre (m)
    zl3 Output real -

    IFE vertical build below centre (m)
    zl4 Output real -

    IFE vertical build below centre (m)
    zl5 Output real -

    IFE vertical build below centre (m)
    zl6 Output real -

    IFE vertical build below centre (m)
    zl7 Output real -

    IFE vertical build below centre (m)
    zu1 Output real -

    IFE vertical build above centre (m)
    zu2 Output real -

    IFE vertical build above centre (m)
    zu3 Output real -

    IFE vertical build above centre (m)
    zu4 Output real -

    IFE vertical build above centre (m)
    zu5 Output real -

    IFE vertical build above centre (m)
    zu6 Output real -

    IFE vertical build above centre (m)
    zu7 Output real -

    IFE vertical build above centre (m)

    stellarator_variables

    Name Type Datatype Default Value Description
    istell Output integer -

    Switch for stellarator option (set via device.dat):

    • =0 use tokamak model
    • =1 use stellarator model: Helias5
    • =2 use stellarator model: Helias4
    • =3 use stellarator model: Helias3
    • =4 use stellarator model: Wendelstein 7-X with 50 Coils
    • =5 use stellarator model: Wendelstein 7-X with 30 Coils
    • =6 use stellarator model: Use stella_conf.json file (any modulear stellarator, see documentation)
    bmn Input real 0.001

    relative radial field perturbation
    f_asym Input real 1.0

    divertor heat load peaking factor
    f_rad Input real 0.85

    radiated power fraction in SOL
    f_w Input real 0.5

    island size fraction factor
    fdivwet Input real 0.333333333333333

    wetted fraction of the divertor area
    flpitch Input real 0.001

    field line pitch (rad)
    hportamax Output real -

    maximum available area for horizontal ports (m2)
    hportpmax Output real -

    maximum available poloidal extent for horizontal ports (m)
    hporttmax Output real -

    maximum available toroidal extent for horizontal ports (m)
    iotabar Input real 1.0

    rotational transform (reciprocal of tokamak q) for stellarator confinement time scaling laws
    isthtr Input integer 3

    Switch for stellarator auxiliary heating method:

    • = 1electron cyclotron resonance heating
    • = 2lower hybrid heating
    • = 3neutral beam injection
    m_res Input integer 5

    poloidal resonance number (1)
    max_gyrotron_frequency Output real -

    Maximal available gyrotron frequency (input parameter) (Hz)
    n_res Input integer 5

    toroidal resonance number (1)
    shear Input real 0.5

    magnetic shear, derivative of iotabar (1)
    te0_ecrh_achievable Output real -

    maximal central electron temperature as achievable by the ECRH, input. (keV)
    vportamax Output real -

    maximum available area for vertical ports (m2)
    vportpmax Output real -

    maximum available poloidal extent for vertical ports (m)
    vporttmax Output real -

    maximum available toroidal extent for vertical ports (m)
    powerht_constraint Output real -
    powerscaling_constraint Output real -

    constants

    Name Type Datatype Default Value Description
    iotty Parameter integer 6
    nout Parameter integer 11
    nplot Parameter integer 12
    mfile Parameter integer 13
    vfile Parameter integer 14
    opt_file Parameter integer 15
    sig_file Parameter integer 16
    degrad Parameter real 0.01745329251D0
    electron_charge Parameter real 1.602176634D-19
    electron_volt Parameter real 1.602176634D-19
    kiloelectron_volt Parameter real 1.602176634D-16
    atomic_mass_unit Parameter real 1.66053906892D-27
    electron_mass Parameter real 9.1093837139D-31
    proton_mass Parameter real 1.67262192595D-27
    deuteron_mass Parameter real 3.3435837768D-27
    triton_mass Parameter real 5.0073567512D-27
    neutron_mass Parameter real 1.67492750056D-27
    alpha_mass Parameter real 6.6446573450D-27
    helion_mass Parameter real 5.0064127862D-27
    speed_light Parameter real 299792458D0
    d_t_energy Parameter real (((deuteron_mass+triton_mass)-(alpha_mass+neutron_mass))*speed_light**2)
    d_helium_energy Parameter real (((deuteron_mass+helion_mass)-(alpha_mass+proton_mass))*speed_light**2)
    dd_helium_energy Parameter real (((deuteron_mass+deuteron_mass)-(helion_mass+neutron_mass))*speed_light**2)
    dd_triton_energy Parameter real (((deuteron_mass+deuteron_mass)-(triton_mass+proton_mass))*speed_light**2)
    dt_neutron_energy_fraction Parameter real (alpha_mass/(neutron_mass+alpha_mass))
    dt_alpha_energy Parameter real (1.0D0-dt_neutron_energy_fraction)*d_t_energy
    dd_neutron_energy_fraction Parameter real (helion_mass/(neutron_mass+helion_mass))
    dd_proton_energy_fraction Parameter real (triton_mass/(proton_mass+triton_mass))
    dhelium_proton_energy_fraction Parameter real (alpha_mass/(proton_mass+alpha_mass))
    pi Parameter real 3.1415926535897932D0
    rmu0 Parameter real 1.256637062D-6
    twopi Parameter real 6.2831853071795862D0
    umass Parameter real 1.660538921D-27
    epsilon0 Parameter real 8.85418781D-12
    cph2o Parameter real 4180.0D0
    dcopper Input real 8900.0
    dalu Input real 2700.0
    denh2o Parameter real 985.0D0
    k_copper Parameter real 330.0D0
    kh2o Parameter real 0.651D0
    muh2o Parameter real 4.71D-4
    n_day_year Parameter real 365.2425D0

    stellarator_configuration

    Name Type Datatype Default Value Description
    stella_config_name Output character -
    stella_config_symmetry Output integer -
    stella_config_coilspermodule Output integer -
    stella_config_rmajor_ref Output real -
    stella_config_rminor_ref Output real -
    stella_config_coil_rmajor Output real -
    stella_config_coil_rminor Output real -
    stella_config_aspect_ref Output real -
    stella_config_bt_ref Output real -
    stella_config_wp_area Output real -
    stella_config_wp_bmax Output real -
    stella_config_i0 Output real -
    stella_config_a1 Output real -
    stella_config_a2 Output real -
    stella_config_dmin Output real -
    stella_config_inductance Output real -
    stella_config_coilsurface Output real -
    stella_config_coillength Output real -
    stella_config_max_portsize_width Output real -
    stella_config_maximal_coil_height Output real -
    stella_config_min_plasma_coil_distance Output real -
    stella_config_derivative_min_lcfs_coils_dist Output real -
    stella_config_plasma_volume Output real -
    stella_config_plasma_surface Output real -
    stella_config_wp_ratio Output real -
    stella_config_max_force_density Output real -
    stella_config_max_force_density_mnm Output real -
    stella_config_min_bend_radius Output real -
    stella_config_epseff Output real -
    stella_config_max_lateral_force_density Output real -
    stella_config_max_radial_force_density Output real -
    stella_config_centering_force_max_mn Output real -
    stella_config_centering_force_min_mn Output real -
    stella_config_centering_force_avg_mn Output real -
    stella_config_neutron_peakfactor Output real -
    sc_d11_star_mono_input Output real -
    sc_nu_star_mono_input Output real -

    pfcoil_module

    Name Type Datatype Default Value Description
    nef Output integer -
    nfxf Output integer -
    ricpf Output real -
    ssq0 Output real -
    sig_axial Output real -
    sig_hoop Output real -
    axial_force Output real -
    rfxf Output real -
    zfxf Output real -
    cfxf Output real -
    xind Output real -
    rcls Output real -
    zcls Output real -
    ccls Output real -
    ccl0 Output real -
    bpf2 Output real -
    vsdum Output real -
    first_call Input logical 1
    cslimit Output logical -
    conductorpf* Variable type -
    croco_strand* Variable type -

    scan_module

    Name Type Datatype Default Value Description
    ipnscns Parameter integer 1000

    Maximum number of scan points
    ipnscnv Parameter integer 81

    Number of available scan variables
    noutvars Parameter integer 84
    width Parameter integer 110
    scan_dim Input integer 1

    1-D or 2-D scan switch (1=1D, 2=2D)
    isweep Output integer -

    Number of scan points to calculate
    isweep_2 Output integer -

    Number of 2D scan points to calculate
    nsweep Input integer 1

    Switch denoting quantity to scan:

    • 1 aspect
    • 2 hldivlim
    • 3 pnetelin
    • 4 hfact
    • 5 oacdcp
    • 6 walalw
    • 7 beamfus0
    • 8 fqval
    • 9 te
    • 10 boundu(15: fvs)
    • 11 dnbeta
    • 12 bootstrap_current_fraction_max
    • 13 boundu(10: hfact)
    • 14 fiooic
    • 15 fjprot
    • 16 rmajor
    • 17 bmxlim
    • 18 gammax
    • 19 boundl(16: ohcth)
    • 20 tbrnmn
    • 21 not used
    • 22 cfactr (N.B. requires iavail=0)
    • 23 boundu(72: fipir)
    • 24 powfmax
    • 25 kappa
    • 26 triang
    • 27 tbrmin (for blktmodel > 0 only)
    • 28 bt
    • 29 coreradius
    • 30 fimpvar # OBSOLETE
    • 31 taulimit
    • 32 epsvmc
    • 33 ttarget
    • 34 qtargettotal
    • 35 lambda_q_omp
    • 36 lambda_target
    • 37 lcon_factor
    • 38 Neon upper limit
    • 39 Argon upper limit
    • 40 Xenon upper limit
    • 41 blnkoth
    • 42 Argon fraction fimp(9)
    • 43 normalised minor radius at which electron cyclotron current drive is maximum
    • 44 Allowable maximum shear stress (Tresca) in tf coil structural material
    • 45 Minimum allowable temperature margin ; tf coils
    • 46 boundu(150) fgwsep
    • 47 impurity_enrichment(9) Argon impurity enrichment
    • 48 TF coil - n_pancake (integer turn winding pack)
    • 49 TF coil - n_layer (integer turn winding pack)
    • 50 Xenon fraction fimp(13)
    • 51 Power fraction to lower DN Divertor ftar
    • 52 SoL radiation fraction
    • 54 GL_nbti upper critical field at 0 Kelvin
    • 55 shldith : Inboard neutron shield thickness
    • 56 crypmw_max: Maximum cryogenic power (ixx=164, ixc=87)
    • 57 bt lower boundary
    • 58 scrapli : Inboard plasma-first wall gap
    • 59 scraplo : Outboard plasma-first wall gap
    • 60 sig_tf_wp_max: Allowable stress in TF Coil conduit (Tresca)
    • 61 copperaoh_m2_max : CS coil current / copper area
    • 62 coheof : CS coil current density at EOF
    • 63 ohcth : CS thickness (m)
    • 64 ohhghf : CS height (m)
    • 65 n_cycle_min : Minimum cycles for CS stress model constraint 90
    • 66 oh_steel_frac: Steel fraction in CS coil
    • 67 t_crack_vertical: Initial crack vertical dimension (m)
  • 68 inlet_temp_liq' : Inlet temperature of blanket liquid metal coolant/breeder (K) <LI> 69outlet_temp_liq' : Outlet temperature of blanket liquid metal coolant/breeder (K)
  • 70 blpressure_liq' : Blanket liquid metal breeder/coolant pressure (Pa) <LI> 71n_liq_recirc' : Selected number of liquid metal breeder recirculations per day
  • 72 bz_channel_conduct_liq' : Conductance of liquid metal breeder duct walls (A V-1 m-1) <LI> 73pnuc_fw_ratio_dcll' : Ratio of FW nuclear power as fraction of total (FW+BB)
  • 74 `f_nuc_pow_bz_struct' : Fraction of BZ power cooled by primary coolant for dual-coolant balnket
  • 75 pitch : pitch of first wall cooling channels (m)
  • 76 etath : Thermal conversion eff.
  • 77 startupratio : Gyrotron redundancy
  • 78 fkind : Multiplier for Nth of a kind costs
  • 79 etaech : ECH wall plug to injector efficiency

    		•
    nsweep_2 Input integer 3

    nsweep_2 /3/ : switch denoting quantity to scan for 2D scan:
    sweep Output real -

    sweep(ipnscns) /../: actual values to use in scan
    sweep_2 Output real -

    sweep_2(ipnscns) /../: actual values to use in 2D scan
    first_call_1d Input logical 1
    first_call_2d Input logical 1

    neoclassics_constants

    Name Type Datatype Default Value Description
    no_roots Parameter integer 30

    neoclassics_module

    Name Type Datatype Default Value Description
    species Variable character (/"e", "D", "T", "a"/)
    densities Output real -
    temperatures Output real -
    dr_densities Output real -
    dr_temperatures Output real -
    roots Variable real 0
    weights Variable real 0
    nu Variable real 0
    nu_star Variable real 0
    nu_star_averaged Variable real 0
    vd Variable real 0
    kt Variable real 0
    er Variable real 0.0
    iota Variable real 1.0d0
    d11_mono Variable real 0
    d11_plateau Variable real 0
    d111 Variable real 0
    d112 Variable real 0
    d113 Variable real 0
    q_flux Variable real 0
    gamma_flux Variable real 0
    d31_mono Variable real 0
    eps_eff Variable real 1d-5
    r_eff Variable real 0

    primary_pumping_variables

    Name Type Datatype Default Value Description
    gamma_he Input real 1.667

    ratio of specific heats for helium (primary_pumping=3)
    t_in_bb Input real 573.13

    temperature in FW and blanket coolant at blanket entrance (primary_pumping=3) [K]
    t_out_bb Input real 773.13

    temperature in FW and blanket coolant at blanket exit (primary_pumping=3) [K]
    p_he Input real 8000000.0

    pressure in FW and blanket coolant at pump exit (primary_pumping=3) [Pa]
    dp_he Input real 550000.0

    pressure drop in FW and blanket coolant including heat exchanger and pipes (primary_pumping=3) [Pa]
    dp_fw_blkt Input real 150000.0

    pressure drop in FW and blanket coolant including heat exchanger and pipes (primary_pumping=3) [Pa]
    dp_fw Input real 150000.0

    pressure drop in FW coolant including heat exchanger and pipes (primary_pumping=3) [Pa]
    dp_blkt Input real 3500.0

    pressure drop in blanket coolant including heat exchanger and pipes (primary_pumping=3) [Pa]
    dp_liq Input real 10000000.0

    pressure drop in liquid metal blanket coolant including heat exchanger and pipes (primary_pumping=3) [Pa]
    htpmw_fw_blkt Output real -

    mechanical pumping power for FW and blanket including heat exchanger and pipes (primary_pumping=3) [MW]

    divertor_variables

    Name Type Datatype Default Value Description
    adas Output real -

    area divertor / area main plasma (along separatrix)
    anginc Input real 0.262

    angle of incidence of field line on plate (rad)
    beta_div Input real 1.0

    field line angle wrt divertor target plate (degrees)
    betai Input real 1.0

    poloidal plane angle between divertor plate and leg, inboard (rad)
    betao Input real 1.0

    poloidal plane angle between divertor plate and leg, outboard (rad)
    bpsout Input real 0.6

    reference B_p at outboard divertor strike point (T)
    c1div Input real 0.45

    fitting coefficient to adjust ptpdiv, ppdiv
    c2div Input real -7.0

    fitting coefficient to adjust ptpdiv, ppdiv
    c3div Input real 0.54

    fitting coefficient to adjust ptpdiv, ppdiv
    c4div Input real -3.6

    fitting coefficient to adjust ptpdiv, ppdiv
    c5div Input real 0.7

    fitting coefficient to adjust ptpdiv, ppdiv
    c6div Output real -

    fitting coefficient to adjust ptpdiv, ppdiv
    delld Input real 1.0

    coeff for power distribution along main plasma
    dendiv Output real -

    plasma density at divertor (10**20 /m3)
    densin Output real -

    density at plate (on separatrix) (10**20 /m3)
    divclfr Input real 0.3

    divertor coolant fraction
    divdens Input real 10000.0

    divertor structure density (kg/m3)
    divdum Output integer -

    switch for divertor Zeff model:

    • =0 calc
    • =1 input
    divfix Input real 0.2

    divertor structure vertical thickness (m)
    divmas Output real -

    divertor plate mass (kg)
    divplt Input real 0.035

    divertor plate thickness (m) (from Spears, Sept 1990)
    divsur Output real -

    divertor surface area (m2)
    fdfs Input real 10.0

    radial gradient ratio
    fdiva Input real 1.11

    divertor area fudge factor (for ITER, Sept 1990)
    fhout Output real -

    fraction of power to outboard divertor (for single null)
    fififi Input real 0.004

    coefficient for gamdiv
    flux_exp Input real 2.0

    The plasma flux expansion in the divertor (default 2; Wade 2020)
    frrp Input real 0.4

    fraction of radiated power to plate
    hldiv Output real -

    divertor heat load (MW/m2)
    i_hldiv Output integer -

    switch for user input hldiv:

    • = 0: divtart model turned off and user inputs hldiv
    • = 1: divtart model calculates hldiv
    • = 2: divwade model calculates hldiv
    hldivlim Input real 5.0

    heat load limit (MW/m2)
    ksic Input real 0.8

    power fraction for outboard double-null scrape-off plasma
    lamp Output real -

    power flow width (m)
    minstang Output real -

    minimum strike angle for heat flux calculation
    omegan Input real 1.0

    pressure ratio (nT)_plasma / (nT)_scrape-off
    omlarg Output real -

    power spillage to private flux factor
    ppdivr Output real -

    peak heat load at plate (with radiation) (MW/m2)
    prn1 Input real 0.285

    n-scrape-off / n-average plasma; (input for ipedestal=0, = nesep/dene if ipedestal>=1)
    ptpdiv Output real -

    peak temperature at the plate (eV)
    rconl Output real -

    connection length ratio, outboard side
    rlclolcn Output real -

    ratio of collision length / connection length
    rlenmax Input real 0.5

    maximum value for length ratio (rlclolcn) (constraintg eqn 22)
    rsrd Output real -

    effective separatrix/divertor radius ratio
    tconl Output real -

    main plasma connection length (m)
    tdiv Input real 2.0

    temperature at divertor (eV) (input for stellarator only, calculated for tokamaks)
    tsep Output real -

    temperature at the separatrix (eV)
    xparain Input real 2100.0

    parallel heat transport coefficient (m2/s)
    xpertin Input real 2.0

    perpendicular heat transport coefficient (m2/s)
    zeffdiv Input real 1.0

    Zeff in the divertor region (if divdum/=0)

    current_drive_variables

    Name Type Datatype Default Value Description
    beamwd Input real 0.58

    width of neutral beam duct where it passes between the TF coils (m) T Inoue et al, Design of neutral beam system for ITER-FEAT, Fusion Engineering and Design, Volumes 56-57, October 2001, Pages 517-521)
    bigq Output real -

    Fusion gain; P_fusion / (P_injection + P_ohmic)
    bootstrap_current_fraction Output real -

    bootstrap current fraction (enforced; see i_bootstrap_current)
    bootstrap_current_fraction_max Input real 0.9

    maximum fraction of plasma current from bootstrap; if bootstrap_current_fraction_max < 0, bootstrap fraction = abs(bootstrap_current_fraction_max)
    bscf_iter89 Output real -

    bootstrap current fraction, ITER 1989 model
    bscf_nevins Output real -

    bootstrap current fraction, Nevins et al model
    bscf_sauter Output real -

    bootstrap current fraction, Sauter et al model
    bscf_wilson Output real -

    bootstrap current fraction, Wilson et al model
    bscf_sakai Output real -

    Bootstrap current fraction, Sakai et al model
    bscf_aries Output real -

    Bootstrap current fraction, ARIES model
    bscf_andrade Output real -

    Bootstrap current fraction, Andrade et al model
    bscf_hoang Output real -

    Bootstrap current fraction, Hoang et al model
    bscf_wong Output real -

    Bootstrap current fraction, Wong et al model
    bscf_gi_i Output real -

    Bootstrap current fraction, first Gi et al model
    bscf_gi_ii Output real -

    Bootstrap current fraction, second Gi et al model
    cboot Input real 1.0

    bootstrap current fraction multiplier
    beam_current Output real -

    neutral beam current (A)
    diacf_hender Output real -

    diamagnetic current fraction, Hender fit
    diacf_scene Output real -

    diamagnetic current fraction, SCENE fit
    diamagnetic_current_fraction Output real -

    diamagnetic current fraction
    echpwr Output real -

    ECH power (MW)
    echwpow Output real -

    ECH wall plug power (MW)
    effcd Output real -

    current drive efficiency (A/W)
    harnum Input real 2.0

    cyclotron harmonic frequency number, used in cut-off function
    wave_mode Output integer -

    Switch for ECRH wave mode :

    • =0 O-mode
    • =1 X-mode
    beam_energy Input real 1000.0

    neutral beam energy (keV) (iteration variable 19)
    etacd Output real -

    auxiliary power wall plug to injector efficiency
    etacdfix Output real -

    secondary auxiliary power wall plug to injector efficiency
    etaech Input real 0.3

    ECH wall plug to injector efficiency
    etalh Input real 0.3

    lower hybrid wall plug to injector efficiency
    etanbi Input real 0.3

    neutral beam wall plug to injector efficiency
    fpion Input real 0.5

    fraction of beam energy to ions
    pnbitot Output real -

    neutral beam power entering vacuum vessel
    pscf_scene Output real -

    Pfirsch-Schlüter current fraction, SCENE fit
    nbshinemw Output real -

    neutral beam shine-through power
    feffcd Input real 1.0

    current drive efficiency fudge factor (iteration variable 47)
    forbitloss Output real -

    fraction of neutral beam power lost after ionisation but before thermalisation (orbit loss fraction)
    frbeam Input real 1.05

    R_tangential / R_major for neutral beam injection
    f_tritium_beam Input real 1e-06

    fraction of beam that is tritium
    gamcd Output real -

    normalised current drive efficiency (1.0e20 A/(W m^2))
    gamma_ecrh Input real 0.35

    User input ECRH gamma (1.0e20 A/(W m^2))
    xi_ebw Input real 0.8

    User scaling input for EBW plasma heating. Default 0.43
    iefrf Input integer 5

    Switch for current drive efficiency model:

    • =1 Fenstermacher Lower Hybrid
    • =2 Ion Cyclotron current drive
    • =3 Fenstermacher ECH
    • =4 Ehst Lower Hybrid
    • =5 ITER Neutral Beam
    • =6 new Culham Lower Hybrid model
    • =7 new Culham ECCD model
    • =8 new Culham Neutral Beam model
    • =9 RFP option removed in PROCESS (issue #508)
    • =10 ECRH user input gamma
    • =11 ECRH "HARE" model (E. Poli, Physics of Plasmas 2019). Removed in #1811.
    • =12 EBW user scaling input. Scaling (S. Freethy)
    iefrffix Output integer -

    Switch for 2nd current drive efficiency model:

    • =0 No fixed current drive
    • =1 Fenstermacher Lower Hybrid
    • =2 Ion Cyclotron current drive
    • =3 Fenstermacher ECH
    • =4 Ehst Lower Hybrid
    • =5 ITER Neutral Beam
    • =6 new Culham Lower Hybrid model
    • =7 new Culham ECCD model
    • =8 new Culham Neutral Beam model
    • =9 RFP option removed in PROCESS (issue #508)
    • =10 ECRH user input gamma
    • =11 ECRH "HARE" model (E. Poli, Physics of Plasmas 2019). Removed in #1811.
    • =12 EBW user scaling input. Scaling (S. Freethy)
    irfcd Input integer 1

    Switch for current drive calculation:

    • =0 turned off
    • =1 turned on
    nbshinef Output real -

    neutral beam shine-through fraction
    nbshield Input real 0.5

    neutral beam duct shielding thickness (m)
    pheat Output real -

    heating power not used for current drive (MW) (iteration variable 11)
    pheatfix Output real -

    secondary fixed heating power not used for current drive (MW)
    pinjalw Input real 150.0

    maximum allowable value for injected power (MW) (constraint equation 30)
    pinjemw Output real -

    auxiliary injected power to electrons (MW)
    pinjimw Output real -

    auxiliary injected power to ions (MW)
    pinjmw Output real -

    total auxiliary injected power (MW)
    pinjfixmw Output real -

    secondary total fixed auxiliary injected power (MW)
    plasma_current_internal_fraction Output real -

    plasma current fraction driven internally (Bootstrap + Diamagnetic + PS)
    plhybd Output real -

    lower hybrid injection power (MW)
    pnbeam Output real -

    neutral beam injection power (MW)
    porbitlossmw Output real -

    neutral beam power lost after ionisation but before thermalisation (orbit loss power) (MW)
    ps_current_fraction Output real -

    Pfirsch-Schlüter current fraction
    pwplh Output real -

    lower hybrid wall plug power (MW)
    pwpnb Output real -

    neutral beam wall plug power (MW)
    rtanbeam Output real -

    neutral beam centreline tangency radius (m)
    rtanmax Output real -

    maximum tangency radius for centreline of beam (m)
    taubeam Output real -

    neutral beam e-decay lengths to plasma centre
    tbeamin Input real 3.0

    permitted neutral beam e-decay lengths to plasma centre

    numerics

    Name Type Datatype Default Value Description
    ipnvars Parameter integer 175

    ipnvars FIX : total number of variables available for iteration
    ipeqns Parameter integer 91

    ipeqns FIX : number of constraint equations available
    ipnfoms Parameter integer 19

    ipnfoms FIX : number of available figures of merit
    ipvlam Parameter integer ipeqns+2*ipnvars+1
    iptnt Parameter integer (ipeqns*(3*ipeqns+13))/2
    ipvp1 Parameter integer ipnvars+1
    ioptimz Input integer 1

    ioptimz /1/ : code operation switch:

    • = -2 for no optimisation, no VMCOM or HYBRD;
    • = -1 for no optimisation, HYBRD only;
    • = 0 for HYBRD and VMCON (not recommended);
    • = 1 for optimisation, VMCON only

    minmax /7/ : switch for figure-of-merit (see lablmm for descriptions) negative => maximise, positive => minimise
    minmax Input integer 7
    lablmm Input character [b'major radius ' b'not used ' b'neutron wall load ' b'P_tf + P_pf ' b'fusion gain ' b'cost of electricity ' b'capital cost ' b'aspect ratio ' b'divertor heat load ' b'toroidal field ' b'total injected power ' b'H plant capital cost ' b'H production rate ' b'pulse length ' b'plant availability ' b'min R0, max tau_burn ' b'net electrical output ' b'Null figure of merit ' b'max Q, max t_burn ']

    lablmm(ipnfoms) : labels describing figures of merit:


    • ( 1) major radius
    • ( 2) not used
    • ( 3) neutron wall load
    • ( 4) P_tf + P_pf
    • ( 5) fusion gain Q
    • ( 6) cost of electricity
    • ( 7) capital cost (direct cost if ireactor=0, constructed cost otherwise)
    • ( 8) aspect ratio
    • ( 9) divertor heat load
    • (10) toroidal field
    • (11) total injected power
    • (12) hydrogen plant capital cost OBSOLETE
    • (13) hydrogen production rate OBSOLETE
    • (14) pulse length
    • (15) plant availability factor (N.B. requires iavail=1 to be set)
    • (16) linear combination of major radius (minimised) and pulse length (maximised) note: FoM should be minimised only!
    • (17) net electrical output
    • (18) Null Figure of Merit
    • (19) linear combination of big Q and pulse length (maximised) note: FoM should be minimised only!
    ncalls Output integer -

    ncalls : number of function calls during solution
    neqns Output integer -

    neqns /0/ : number of equality constraints to be satisfied
    nfev1 Output integer -

    nfev1 : number of calls to FCNHYB (HYBRD function caller) made
    nfev2 Output integer -

    nfev2 : number of calls to FCNVMC1 (VMCON function caller) made
    nineqns Output integer -

    nineqns /0/ : number of inequality constraints VMCON must satisfy (leave at zero for now)
    nvar Input integer 16

    nvar /16/ : number of iteration variables to use
    nviter Output integer -

    nviter : number of VMCON iterations performed

    icc(ipeqns) /0/ : array defining which constraint equations to activate (see lablcc for descriptions)
    icc Output integer -
    active_constraints Output logical -

    active_constraints(ipeqns) : Logical array showing which constraints are active
    lablcc Input character [b'Beta consistency ' b'Global power balance consistency ' b'Ion power balance ' b'Electron power balance ' b'Density upper limit ' b'(Epsilon x beta-pol) upper limit ' b'Beam ion density consistency ' b'Neutron wall load upper limit ' b'Fusion power upper limit ' b'Toroidal field 1/R consistency ' b'Radial build consistency ' b'Volt second lower limit ' b'Burn time lower limit ' b'NBI decay lengths consistency ' b'L-H power threshold limit ' b'Net electric power lower limit ' b'Radiation fraction upper limit ' b'Divertor heat load upper limit ' b'MVA upper limit ' b'Beam tangency radius upper limit ' b'Plasma minor radius lower limit ' b'Divertor collisionality upper lim' b'Conducting shell radius upper lim' b'Beta upper limit ' b'Peak toroidal field upper limit ' b'CS coil EOF current density limit' b'CS coil BOP current density limit' b'Fusion gain Q lower limit ' b'Inboard radial build consistency ' b'Injection power upper limit ' b'TF coil case stress upper limit ' b'TF coil conduit stress upper lim ' b'I_op / I_critical (TF coil) ' b'Dump voltage upper limit ' b'J_winding pack/J_protection limit' b'TF coil temp. margin lower limit ' b'Current drive gamma limit ' b'1st wall coolant temp rise limit ' b'First wall peak temperature limit' b'Start-up inj. power lower limit ' b'Plasma curr. ramp time lower lim ' b'Cycle time lower limit ' b'Average centrepost temperature ' b'Peak centrepost temp. upper limit' b'Edge safety factor lower limit ' b'Ip/Irod upper limit ' b'TF coil tor. thickness upper lim ' b'Poloidal beta upper limit ' b'RFP reversal parameter < 0 ' b'IFE repetition rate upper limit ' b'Startup volt-seconds consistency ' b'Tritium breeding ratio lower lim ' b'Neutron fluence on TF coil limit ' b'Peak TF coil nucl. heating limit ' b'Vessel helium concentration limit' b'Psep / R upper limit ' b'TF coil leg rad width lower limit' b'TF coil leg rad width lower limit' b'NB shine-through frac upper limit' b'CS temperature margin lower limit' b'Minimum availability value ' b'taup/taueff ' b'number of ITER-like vacuum pumps ' b'Zeff limit ' b'Dump time set by VV stress ' b'Rate of change of energy in field' b'Upper Lim. on Radiation Wall load' b'Upper Lim. on Psep * Bt / q A R ' b'pdivt < psep_kallenbach divertor ' b'Separatrix temp consistency ' b'Separatrix density consistency ' b'CS Tresca yield criterion ' b'Psep >= Plh + Paux ' b'TFC quench < tmax_croco ' b'TFC current/copper area < Max ' b'Eich critical separatrix density ' b'TFC current per turn upper limit ' b'Reinke criterion fZ lower limit ' b'Peak CS field upper limit ' b'pdivt lower limit ' b'ne0 > neped ' b'toroidalgap > tftort ' b'available_space > required_space ' b'beta > betalim_lower ' b'CP lifetime ' b'TFC turn dimension ' b'Cryogenic plant power ' b'TF coil strain absolute value ' b'CS current/copper area < Max ' b'CS stress load cycles ' b'ECRH ignitability ']

    lablcc(ipeqns) : labels describing constraint equations (corresponding itvs)


    • ( 1) Beta (consistency equation) (itv 5)
    • ( 2) Global power balance (consistency equation) (itv 10,1,2,3,4,6,11)
    • ( 3) Ion power balance DEPRECATED (itv 10,1,2,3,4,6,11)
    • ( 4) Electron power balance DEPRECATED (itv 10,1,2,3,4,6,11)
    • ( 5) Density upper limit (itv 9,1,2,3,4,5,6)
    • ( 6) (Epsilon x beta poloidal) upper limit (itv 8,1,2,3,4,6)
    • ( 7) Beam ion density (NBI) (consistency equation) (itv 7)
    • ( 8) Neutron wall load upper limit (itv 14,1,2,3,4,6)
    • ( 9) Fusion power upper limit (itv 26,1,2,3,4,6)
    • (10) Toroidal field 1/R (consistency equation) (itv 12,1,2,3,13 )
    • (11) Radial build (consistency equation) (itv 3,1,13,16,29,42,61)
    • (12) Volt second lower limit (STEADY STATE) (itv 15,1,2,3)
    • (13) Burn time lower limit (PULSE) (itv 21,1,16,17,29,42,44,61) (itv 19,1,2,3,6)
    • (14) Neutral beam decay lengths to plasma centre (NBI) (consistency equation)
    • (15) LH power threshold limit (itv 103)
    • (16) Net electric power lower limit (itv 25,1,2,3)
    • (17) Radiation fraction upper limit (itv 28)
    • (18) Divertor heat load upper limit (itv 27)
    • (19) MVA upper limit (itv 30)
    • (20) Neutral beam tangency radius upper limit (NBI) (itv 33,31,3,13)
    • (21) Plasma minor radius lower limit (itv 32)
    • (22) Divertor collisionality upper limit (itv 34,43)
    • (23) Conducting shell to plasma minor radius ratio upper limit (itv 104,1,74)
    • (24) Beta upper limit (itv 36,1,2,3,4,6,18)
    • (25) Peak toroidal field upper limit (itv 35,3,13,29)
    • (26) Central solenoid EOF current density upper limit (ipfres=0) (itv 38,37,41,12)
    • (27) Central solenoid BOP current density upper limit (ipfres=0) (itv 39,37,41,12)
    • (28) Fusion gain Q lower limit (itv 45,47,40)
    • (29) Inboard radial build consistency (itv 3,1,13,16,29,42,61)
    • (30) Injection power upper limit (itv 46,47,11)
    • (31) TF coil case stress upper limit (SCTF) (itv 48,56,57,58,59,60,24)
    • (32) TF coil conduit stress upper limit (SCTF) (itv 49,56,57,58,59,60,24)
    • (33) I_op / I_critical (TF coil) (SCTF) (itv 50,56,57,58,59,60,24)
    • (34) Dump voltage upper limit (SCTF) (itv 51,52,56,57,58,59,60,24)
    • (35) J_winding pack/J_protection upper limit (SCTF) (itv 53,56,57,58,59,60,24)
    • (36) TF coil temperature margin lower limit (SCTF) (itv 54,55,56,57,58,59,60,24)
    • (37) Current drive gamma upper limit (itv 40,47)
    • (38) First wall coolant temperature rise upper limit (itv 62)
    • (39) First wall peak temperature upper limit (itv 63)
    • (40) Start-up injection power lower limit (PULSE) (itv 64)
    • (41) Plasma current ramp-up time lower limit (PULSE) (itv 66,65)
    • (42) Cycle time lower limit (PULSE) (itv 17,67,65)
    • (43) Average centrepost temperature (TART) (consistency equation) (itv 13,20,69,70)
    • (44) Peak centrepost temperature upper limit (TART) (itv 68,69,70)
    • (45) Edge safety factor lower limit (TART) (itv 71,1,2,3)
    • (46) Equation for Ip/Irod upper limit (TART) (itv 72,2,60)
    • (47) NOT USED
    • (48) Poloidal beta upper limit (itv 79,2,3,18)
    • (49) NOT USED
    • (50) IFE repetition rate upper limit (IFE)
    • (51) Startup volt-seconds consistency (PULSE) (itv 16,29,3,1)
    • (52) Tritium breeding ratio lower limit (itv 89,90,91)
    • (53) Neutron fluence on TF coil upper limit (itv 92,93,94)
    • (54) Peak TF coil nuclear heating upper limit (itv 95,93,94)
    • (55) Vacuum vessel helium concentration upper limit iblanket =2 (itv 96,93,94)
    • (56) Pseparatrix/Rmajor upper limit (itv 97,1,3)
    • (57) NOT USED
    • (58) NOT USED
    • (59) Neutral beam shine-through fraction upper limit (NBI) (itv 105,6,19,4 )
    • (60) Central solenoid temperature margin lower limit (SCTF) (itv 106)
    • (61) Minimum availability value (itv 107)
    • (62) taup/taueff the ratio of particle to energy confinement times (itv 110)
    • (63) The number of ITER-like vacuum pumps niterpump < tfno (itv 111)
    • (64) Zeff less than or equal to zeffmax (itv 112)
    • (65) Dump time set by VV loads (itv 56, 113)
    • (66) Limit on rate of change of energy in poloidal field (Use iteration variable 65(tohs), 115)
    • (67) Simple Radiation Wall load limit (itv 116, 4,6)
    • (68) Psep * Bt / qAR upper limit (itv 117)
    • (69) ensure separatrix power = the value from Kallenbach divertor (itv 118)
    • (70) ensure that teomp = separatrix temperature in the pedestal profile, (itv 119 (tesep))
    • (71) ensure that neomp = separatrix density (nesep) x neratio
    • (72) central solenoid shear stress limit (Tresca yield criterion) (itv 123 foh_stress)
    • (73) Psep >= Plh + Paux (itv 137 (fplhsep))
    • (74) TFC quench < tmax_croco (itv 141 (fcqt))
    • (75) TFC current/copper area < Maximum (itv 143 f_coppera_m2)
    • (76) Eich critical separatrix density
    • (77) TF coil current per turn upper limit
    • (78) Reinke criterion impurity fraction lower limit (itv 147 freinke)
    • (79) Peak CS field upper limit (itv 149 fbmaxcs)
    • (80) Divertor power lower limit pdivt (itv 153 fpdivlim)
    • (81) Ne(0) > ne(ped) constraint (itv 154 fne0)
    • (82) toroidalgap > tftort constraint (itv 171 ftoroidalgap)
    • (83) Radial build consistency for stellarators (itv 172 f_avspace)
    • (84) Lower limit for beta (itv 173 fbetatry_lower)
    • (85) Constraint for CP lifetime
    • (86) Constraint for TF coil turn dimension
    • (87) Constraint for cryogenic power
    • (88) Constraint for TF coil strain absolute value
    • (89) Constraint for CS coil quench protection
    • (90) Lower Limit on number of stress load cycles for CS (itr 167 fncycle)
    • (91) Checking if the design point is ECRH ignitable (itv 168 fecrh_ignition)

    ixc Output integer -

    ixc(ipnvars) /0/ : array defining which iteration variables to activate (see lablxc for descriptions)
    lablxc Input character [b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ']

    lablxc(ipnvars) : labels describing iteration variables


    • ( 1) aspect
    • ( 2) bt
    • ( 3) rmajor
    • ( 4) te
    • ( 5) beta
    • ( 6) dene
    • ( 7) rnbeam
    • ( 8) fbeta (f-value for equation 6)
    • ( 9) fdene (f-value for equation 5)
    • (10) hfact
    • (11) pheat
    • (12) oacdcp
    • (13) tfcth (NOT RECOMMENDED)
    • (14) fwalld (f-value for equation 8)
    • (15) fvs (f-value for equation 12)
    • (16) ohcth
    • (17) tdwell
    • (18) q
    • (19) beam_energy
    • (20) tcpav
    • (21) ftburn (f-value for equation 13)
    • (22) NOT USED
    • (23) fcoolcp
    • (24) NOT USED
    • (25) fpnetel (f-value for equation 16)
    • (26) ffuspow (f-value for equation 9)
    • (27) fhldiv (f-value for equation 18)
    • (28) fradpwr (f-value for equation 17), total radiation fraction
    • (29) bore
    • (30) fmva (f-value for equation 19)
    • (31) gapomin
    • (32) frminor (f-value for equation 21)
    • (33) fportsz (f-value for equation 20)
    • (34) fdivcol (f-value for equation 22)
    • (35) fpeakb (f-value for equation 25)
    • (36) fbetatry (f-value for equation 24)
    • (37) coheof
    • (38) fjohc (f-value for equation 26)
    • (39) fjohc0 (f-value for equation 27)
    • (40) fgamcd (f-value for equation 37)
    • (41) fcohbop
    • (42) gapoh
    • (43) NOT USED
    • (44) fvsbrnni
    • (45) fqval (f-value for equation 28)
    • (46) fpinj (f-value for equation 30)
    • (47) feffcd
    • (48) fstrcase (f-value for equation 31)
    • (49) fstrcond (f-value for equation 32)
    • (50) fiooic (f-value for equation 33)
    • (51) fvdump (f-value for equation 34)
    • (52) NOT USED
    • (53) fjprot (f-value for equation 35)
    • (54) ftmargtf (f-value for equation 36)
    • (55) NOT USED
    • (56) tdmptf
    • (57) thkcas
    • (58) thwcndut
    • (59) fcutfsu
    • (60) cpttf
    • (61) gapds
    • (62) fdtmp (f-value for equation 38)
    • (63) ftpeak (f-value for equation 39)
    • (64) fauxmn (f-value for equation 40)
    • (65) tohs
    • (66) ftohs (f-value for equation 41)
    • (67) ftcycl (f-value for equation 42)
    • (68) fptemp (f-value for equation 44)
    • (69) rcool
    • (70) vcool
    • (71) fq (f-value for equation 45)
    • (72) fipir (f-value for equation 46)
    • (73) scrapli
    • (74) scraplo
    • (75) tfootfi
    • (76) NOT USED
    • (77) NOT USED
    • (78) NOT USED
    • (79) fbetap (f-value for equation 48)
    • (80) NOT USED
    • (81) edrive
    • (82) drveff
    • (83) tgain
    • (84) chrad
    • (85) pdrive
    • (86) frrmax (f-value for equation 50)
    • (87) NOT USED
    • (88) NOT USED
    • (89) ftbr (f-value for equation 52)
    • (90) blbuith
    • (91) blbuoth
    • (92) fflutf (f-value for equation 53)
    • (93) shldith
    • (94) shldoth
    • (95) fptfnuc (f-value for equation 54)
    • (96) fvvhe (f-value for equation 55)
    • (97) fpsepr (f-value for equation 56)
    • (98) li6enrich
    • (99) NOT USED
    • (100) NOT USED
    • (101) NOT USED
    • (102) fimpvar # OBSOLETE
    • (103) flhthresh (f-value for equation 15)
    • (104) fcwr (f-value for equation 23)
    • (105) fnbshinef (f-value for equation 59)
    • (106) ftmargoh (f-value for equation 60)
    • (107) favail (f-value for equation 61)
    • (108) breeder_f: Volume of Li4SiO4 / (Volume of Be12Ti + Li4SiO4)
    • (109) ralpne: thermal alpha density / electron density
    • (110) ftaulimit: Lower limit on taup/taueff the ratio of alpha
    • (111) fniterpump: f-value for constraint that number
    • (112) fzeffmax: f-value for max Zeff (f-value for equation 64)
    • (113) ftaucq: f-value for minimum quench time (f-value for equation 65)
    • (114) fw_channel_length: Length of a single first wall channel
    • (115) fpoloidalpower: f-value for max rate of change of
    • (116) fradwall: f-value for radiation wall load limit (eq. 67)
    • (117) fpsepbqar: f-value for Psep*Bt/qar upper limit (eq. 68)
    • (118) fpsep: f-value to ensure separatrix power is less than
    • (119) tesep: separatrix temperature calculated by the Kallenbach divertor model
    • (120) ttarget: Plasma temperature adjacent to divertor sheath [eV]
    • (121) neratio: ratio of mean SOL density at OMP to separatrix density at OMP
    • (122) oh_steel_frac : streel fraction of Central Solenoid
    • (123) foh_stress : f-value for CS coil Tresca yield criterion (f-value for eq. 72)
    • (124) qtargettotal : Power density on target including surface recombination [W/m2]
    • (125) fimp(3) : Beryllium density fraction relative to electron density
    • (126) fimp(4) : Carbon density fraction relative to electron density
    • (127) fimp(5) : Nitrogen fraction relative to electron density
    • (128) fimp(6) : Oxygen density fraction relative to electron density
    • (129) fimp(7) : Neon density fraction relative to electron density
    • (130) fimp(8) : Silicon density fraction relative to electron density
    • (131) fimp(9) : Argon density fraction relative to electron density
    • (132) fimp(10) : Iron density fraction relative to electron density
    • (133) fimp(11) : Nickel density fraction relative to electron density
    • (134) fimp(12) : Krypton density fraction relative to electron density
    • (135) fimp(13) : Xenon density fraction relative to electron density
    • (136) fimp(14) : Tungsten density fraction relative to electron density
    • (137) fplhsep (f-value for equation 73)
    • (138) rebco_thickness : thickness of REBCO layer in tape (m)
    • (139) copper_thick : thickness of copper layer in tape (m)
    • (140) dr_tf_wp : radial thickness of TFC winding pack (m)
    • (141) fcqt : TF coil quench temperature < tmax_croco (f-value for equation 74)
    • (142) nesep : electron density at separatrix [m-3]
    • (143) f_copperA_m2 : TF coil current / copper area < Maximum value
    • (144) fnesep : Eich critical electron density at separatrix
    • (145) fgwped : fraction of Greenwald density to set as pedestal-top density
    • (146) fcpttf : F-value for TF coil current per turn limit (constraint equation 77)
    • (147) freinke : F-value for Reinke detachment criterion (constraint equation 78)
    • (148) fzactual : fraction of impurity at SOL with Reinke detachment criterion
    • (149) fbmaxcs : F-value for max peak CS field (con. 79, itvar 149)
    • (150) REMOVED
    • (151) REMOVED
    • (152) fgwsep : Ratio of separatrix density to Greenwald density
    • (153) fpdivlim : F-value for minimum pdivt (con. 80)
    • (154) fne0 : F-value for ne(0) > ne(ped) (con. 81)
    • (155) pfusife : IFE input fusion power (MW) (ifedrv=3 only)
    • (156) rrin : Input IFE repetition rate (Hz) (ifedrv=3 only)
    • (157) fvssu : F-value for available to required start up flux (con. 51)
    • (158) croco_thick : Thickness of CroCo copper tube (m)
    • (159) ftoroidalgap : F-value for toroidalgap > tftort constraint (con. 82)
    • (160) f_avspace (f-value for equation 83)
    • (161) fbetatry_lower (f-value for equation 84)
    • (162) r_cp_top : Top outer radius of the centropost (ST only) (m)
    • (163) f_t_turn_tf : f-value for TF coils WP trurn squared dimension constraint
    • (164) f_crypmw : f-value for cryogenic plant power
    • (165) fstr_wp : f-value for TF coil strain absolute value
    • (166) f_copperaoh_m2 : CS coil current /copper area < Maximum value
    • (167) fncycle : f-value for minimum CS coil stress load cycles
    • (168) fecrh_ignition: f-value for equation 91
    • (169) te0_ecrh_achievable: Max. achievable electron temperature at ignition point
    • (170) beta_div : field line angle wrt divertor target plate (degrees)
    • (171) casths_fraction : TF side case thickness as fraction of toridal case thickness
    • (172) casths : TF side case thickness [m]
    • (173) EMPTY : Description
    • (174) EMPTY : Description
    • (175) EMPTY : Description

    name_xc Variable character -
    sqsumsq Output real -

    sqsumsq : sqrt of the sum of the square of the constraint residuals
    objf_name Input character b' '

    Description of the objective function
    norm_objf Output real -

    Normalised objective function (figure of merit)
    epsfcn Input real 0.001

    epsfcn /1.0e-3/ : finite difference step length for HYBRD/VMCON derivatives
    epsvmc Input real 1e-06

    epsvmc /1.0e-6/ : error tolerance for VMCON
    factor Input real 0.1

    factor /0.1/ : used in HYBRD for first step size
    ftol Input real 0.0001

    ftol /1.0e-4/ : error tolerance for HYBRD
    boundl Input real [9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99 9.e-99]

    boundl(ipnvars) /../ : lower bounds used on ixc variables during VMCON optimisation runs
    boundu Input real [9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99 9.e+99]
    bondl Output real -
    bondu Output real -
    rcm Output real -
    resdl Output real -
    scafc Output real -
    scale Output real -
    xcm Output real -
    xcs Output real -
    vlam Output real -

    pulse_variables

    Name Type Datatype Default Value Description
    bctmp Input real 320.0

    first wall bulk coolant temperature (C)
    dtstor Input real 300.0

    maximum allowable temperature change in stainless steel thermal storage block (K) (istore=3)
    istore Input integer 1

    Switch for thermal storage method:

    • =1 option 1 of Electrowatt report, AEA FUS 205
    • =2 option 2 of Electrowatt report, AEA FUS 205
    • =3 stainless steel block
    itcycl Input integer 1

    Switch for first wall axial stress model:

    • =1 total axial constraint, no bending
    • =2 no axial constraint, no bending
    • =3 no axial constraint, bending
    lpulse Output integer -

    Switch for reactor model:

    • =0 continuous operation
    • =1 pulsed operation

    impurity_radiation_module

    Name Type Datatype Default Value Description
    nimp Parameter integer 14

    nimp /14/ FIX : number of ion species in impurity radiation model
    coreradius Input real 0.6

    coreradius /0.6/ : normalised radius defining the 'core' region
    coreradiationfraction Input real 1.0

    coreradiationfraction /1.0/ : fraction of radiation from 'core' region that is subtracted from the loss power

    fimp(nimp) /1.0,0.1,0.02,0.0,0.0,0.0,0.0,0.0,0.0016,0.0,0.0,0.0,0.0,0.0/ : impurity number density fractions relative to electron density
    fimp Input real [1. 0.1 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. ]
    imp_label Input character [b'H_' b'He' b'Be' b'C_' b'N_' b'O_' b'Ne' b'Si' b'Ar' b'Fe' b'Ni' b'Kr' b'Xe' b'W_']

    imp_label(nimp) : impurity ion species names:

    • ( 1) Hydrogen (fraction calculated by code)
    • ( 2) Helium
    • ( 3) Beryllium
    • ( 4) Carbon
    • ( 5) Nitrogen
    • ( 6) Oxygen
    • ( 7) Neon
    • ( 8) Silicon
    • ( 9) Argon
    • (10) Iron
    • (11) Nickel
    • (12) Krypton
    • (13) Xenon
    • (14) Tungsten
    all_array_hotfix_len* Parameter integer 200
    impurity_arr_label Input character [b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ' b' ']
    impurity_arr_z Output integer -
    impurity_arr_amass Output real -
    impurity_arr_frac Output real -
    impurity_arr_len_tab Output integer -
    impurity_arr_temp_kev Output real -
    impurity_arr_lz_wm3 Output real -
    impurity_arr_zav Output real -
    toolow Output logical -

    Used for reporting error in function pimpden

    ccfe_hcpb_module

    Name Type Datatype Default Value Description
    ip Output integer -
    ofile Output integer -
    armour_density Output real -

    FW armour density [kg/m3]
    fw_density Output real -

    FW density [kg/m3]
    blanket_density Output real -

    Blanket density [kg/m3]
    shield_density Output real -

    Shield density [kg/m3]
    vv_density Output real -

    Vacuum vessel density [kg/m3]
    x_blanket Output real -

    Blanket exponent (tonne/m2)
    x_shield Output real -

    Shield exponent (tonne/m2)
    tfc_nuc_heating Output real -

    Unit nuclear heating in TF coil (W per W of fusion power)
    fw_armour_u_nuc_heating Output real -

    Unit heating of FW and armour in FW armour (W/kg per W of fusion power)
    shld_u_nuc_heating Output real -

    Unit nuclear heating in shield (W per W of fusion power)
    pnuc_tot_blk_sector Output real -

    Total nuclear power deposited in blanket covered sector (FW, BLKT, SHLD, TF) (MW)
    exp_blanket Output real -

    Exponential factors in nuclear heating calcs
    exp_shield1 Output real -

    Exponential factors in nuclear heating calcs
    exp_shield2 Output real -

    Exponential factors in nuclear heating calcs

    fson_string_m

    Name Type Datatype Default Value Description
    block_size* Parameter integer 32

    fson_value_m

    Name Type Datatype Default Value Description
    type_unknown Parameter integer -1
    type_null Parameter integer 0
    type_object Parameter integer 1
    type_array Parameter integer 2
    type_string Parameter integer 3
    type_integer Parameter integer 4
    type_real Parameter integer 5
    type_logical Parameter integer 6

    fson_library

    Name Type Datatype Default Value Description
    end_of_file* Parameter integer -1
    end_of_record* Parameter integer -2
    state_looking_for_value* Parameter integer 1
    state_in_object* Parameter integer 2
    state_in_pair_name* Parameter integer 3
    state_in_pair_value* Parameter integer 4
    pushed_index* Variable integer -
    pushed_char* Variable character -