Add new plasma shaping option

documentation/source/physics-models/plasma_geometry.md

@@ -252,6 +252,21 @@ $$
   $$
 
 ---------------------------------------------------------------------
+- `i_plasma_geometry = 12` -- The elongation is calculated directly from the aspect ratio based on a scaling for the maximum contrallable elongation in a spherical tokamak[^5] and asssuming a constant $li(3)$. 
+    $$
+    \kappa = 2.93 \left(\frac{1.8}{A}\right)^{1.4}
+    $$
+
+  The elongation and triangularity of the 95% flux surface are calculated as follows, based on the 1989 ITER guidelines [^1]:
+
+  $$
+  \kappa_{95} = \kappa / 1.12
+  $$
+  $$
+  \delta_{95} = \delta / 1.5 
+  $$
+
+---------------------------------------------------------------------
 
 
 ### Plasma-Wall Gap
@@ -785,6 +800,7 @@ Unpublished internal Oak Ridge document.
 [^3]: H. Zohm et al, *'On the Physics Guidelines for a Tokamak DEMO'*,
 FTP/3-3, Proc. IAEA Fusion Energy Conference, October 2012, San Diego
 [^4]: Menard, J.E. & Brown, T. & El-Guebaly, L. & Boyer, M. & Canik, J. & Colling, Bethany & Raman, Roger & Wang, Z. & Zhai, Yunbo & Buxton, Peter & Covele, B. & D’Angelo, C. & Davis, Andrew & Gerhardt, S. & Gryaznevich, M. & Harb, Moataz & Hender, T.C. & Kaye, S. & Kingham, David & Woolley, R.. (2016). *Fusion nuclear science facilities and pilot plants based on the spherical tokamak.* Nuclear Fusion. 56. 106023. 10.1088/0029-5515/56/10/106023. 
+[^5] J.E. Menard, S.C. Jardin, S.M. Kaye, C.E. Kessel and J. Manickam (1997) *Ideal MHD stability limits of low aspect ratio tokamak plasmas.* Nuclear Fusion. 37. 595. 10.1088/0029-5515/37/5/I03
 [^6]: J D Galambos, *STAR Code : Spherical Tokamak Analysis and Reactor Code*,
 unpublished internal Oak Ridge document
 [^7]: O. Sauter, “Geometric formulas for system codes including the effect of negative triangularity,” Fusion Engineering and Design, vol. 112, pp. 633–645, Nov. 2016, doi: https://doi.org/10.1016/j.fusengdes.2016.04.033.

helias/FELIX.IN.DAT.txt

@@ -0,0 +1,250 @@
+*************************************************************************
+*****                                                               *****
+*****                        HELIAS-5B                              *****
+*****               Stuart Muldrew (17/01/2019)                     *****
+*****            Based on Felix Warmer Run (27/05/2015)             *****
+*****   Warmer et al. (2016), IEEE Trans. Plasma Sci. 44, 1576      *****
+*****                                                               *****
+*************************************************************************
+
+*---------------Constraint Equations---------------*
+
+neqns = 3               *number of equalities
+
+
+*--------------- equaltities
+icc = 2                 *Global power balance (consistency equation)
+icc = 11                *Radial build (consistency equation)
+icc = 16                *Net electric power lower limit
+
+
+*-------------- inequaltities
+icc = 84                *Lower beta limit
+icc = 24                *Upper beta limit
+
+
+
+*---------------Iteration Variables----------------*
+
+ixc = 4                 *te
+boundl(4) = 4.
+boundu(4) = 25.
+
+ixc = 6                 *dene
+dene = 2.0914E20        *Electron density (/m3)
+boundl(6) = 3.005E19
+boundu(6) = 5.005E20
+
+ixc = 10                *hfact
+hfact = 1.2187          *H-factor on energy confinement times
+boundu(10) = 2.0
+
+ixc = 25                *fpnetel
+* Replaced 'fpnetel' with 'fp_plant_electric_net_required_mw'
+fp_plant_electric_net_required_mw = 1.0000        *f-value for net electric power
+boundl(25) = 0.98
+boundu(25) = 1.0
+
+ixc = 50                * itv_fiooic
+boundu(50) = 0.9
+boundl(50) = 0.001
+
+
+*----------------Physics Variables-----------------*
+
+alphan   = 0.35         *Density profile index
+alphat   = 1.20         *Temperature profile index
+aspect   = 12.22        *Aspect ratio
+bt       = 5.5          *Toroidal field on axis (T)
+* Replaced 'ignite' with 'i_plasma_ignited'
+i_plasma_ignited   = 1            *Switch for ignition assumption (1: Ignited)
+* Obsolete: iinvqd   = 1            *Switch for inverse quadrature in L-mode scaling laws 5 and 9 (1: Inverse quadrature with Neo-Alcator tau-E used)
+ipedestal = 0           *Switch for pedestal profiles (0: Parabolic Profiles)
+* Replaced 'iradloss' with 'i_rad_loss'
+i_rad_loss = 1            *Switch for radiation loss term usage in power balance (1: Total power lost is scaling power plus core radiation only)
+* Replaced 'isc' with 'i_confinement_time'
+i_confinement_time      = 38           *Switch for energy confinement time scaling law (38: ISS04)
+kappa    = 1.001        *Plasma separatrix elongation
+rmajor   = 22.0         *Plasma major radius (m)
+* Replaced 'ssync' with 'f_sync_reflect'
+f_sync_reflect    = 0.6          *Synchrotron wall reflectivity factor
+te       = 7.0          *Volume averaged electron temperature (keV)
+tratio   = 0.95         *Ion temperature / electron temperature
+*zfear    = 0            *High-Z impurity switch (0: Iron)
+
+*--------------Stellarator Variables---------------*
+
+istell   = 1            *Switch for stellarator option
+bmn      = 0.001        *Relative radial field perturbation
+f_asym   = 1.1          *Divertor heat load peaking factor
+f_rad    = 0.85         *Radiated power fraction in sol
+f_w      = 0.6          *Island size fraction factor
+flpitch  = 0.001        *Field line pitch (rad)
+iotabar  = 0.9          *Rotational transform (reciprocal of tokamak q)
+isthtr   = 1            *Switch for stellarator auxiliary heating method (1: Electron cyclotron resonance heating)
+shear    = 0.5          *Magnetic shear, derivative of iotabar
+
+*-----------------Build Variables------------------*
+
+* Replaced 'blnkith' with 'dr_blkt_inboard'
+dr_blkt_inboard  = 0.7          *Inboard blanket thickness (m)
+* Replaced 'blnkoth' with 'dr_blkt_outboard'
+dr_blkt_outboard  = 0.8          *Outboard blanket thickness (m)
+* Replaced 'ddwex' with 'dr_cryostat'
+dr_cryostat    = 0.15         *Cryostat thickness (m)
+* Replaced 'd_vv_in' with 'dr_vv_inboard'
+dr_vv_inboard  = 0.35         *Inboard vacuum vessel thickness (tf coil / shield) (m)
+* Replaced 'd_vv_out' with 'dr_vv_outboard'
+dr_vv_outboard = 0.35         *Outboard vacuum vessel thickness (tf coil / shield) (m)
+* Replaced 'd_vv_top' with 'dz_vv_upper'
+dz_vv_upper = 0.35         *Topside vacuum vessel thickness (tf coil / shield) (m)
+* Replaced 'd_vv_bot' with 'dz_vv_lower'
+dz_vv_lower = 0.35         *Underside vacuum vessel thickness (tf coil / shield) (m)
+* Replaced 'gapds' with 'dr_shld_vv_gap_inboard'
+dr_shld_vv_gap_inboard    = 0.025        *Gap between inboard vacuum vessel and tf coil (m)
+gapomin  = 0.025        *Minimum gap between outboard vacuum vessel and TF coil (m)
+* Replaced 'scrapli' with 'dr_fw_plasma_gap_inboard'
+dr_fw_plasma_gap_inboard  = 0.15         *Gap between plasma and first wall; inboard side (m)
+* Replaced 'scraplo' with 'dr_fw_plasma_gap_outboard'
+dr_fw_plasma_gap_outboard  = 0.3          *Gap between plasma and first wall; outboard side (m)
+* Replaced 'shldith' with 'dr_shld_inboard'
+dr_shld_inboard  = 0.4          *Inboard shield thickness (m)
+* Replaced 'shldoth' with 'dr_shld_outboard'
+dr_shld_outboard  = 0.7          *Outboard shield thickness (m)
+* Replaced 'shldtth' with 'dz_shld_upper'
+dz_shld_upper  = 0.7          *Upper/lower shield thickness (m)
+* Replaced 'vgap' with 'dz_xpoint_divertor'
+dz_xpoint_divertor     = 0.0          *Vertical gap between x-point and divertor (m)
+
+*---------------Constraint Variables---------------*
+
+* Replaced 'pnetelin' with 'p_plant_electric_net_required_mw'
+p_plant_electric_net_required_mw = 1000         *Required net electric power (MW)
+* Replaced 'betalim' with 'beta_max'
+beta_max = 0.05          *upper beta limit
+* Replaced 'betalim_lower' with 'beta_min'
+beta_min = 0.01    *lower beta limit
+
+*-------------Current Drive Variables--------------*
+
+* Replaced 'etaech' with 'eta_ecrh_injector_wall_plug'
+eta_ecrh_injector_wall_plug   = 0.7          *ECH wall plug to injector efficiency
+* Replaced 'pheat' with 'p_hcd_primary_extra_heat_mw'
+p_hcd_primary_extra_heat_mw    = 0.0          *Heating power not used for current drive (MW)
+
+*----------------Divertor Variables----------------*
+
+anginc   = 0.035        *Angle of incidence of field line on plate (rad)
+* Obsolete: divdum   = 1            *Switch for divertor zeff model (1: input)
+tdiv     = 3.0          *Temperature at divertor (eV)
+xpertin  = 1.5          *Perpendicular heat transport coefficient (m2/s)
+* Obsolete: zeffdiv  = 3.0          *Zeff in the divertor region (if divdum /= 0)
+
+*------------------FWBs Variables------------------*
+
+denstl   = 7800.0       *Density of steel (kg/m3)
+* Replaced 'emult' with 'f_p_blkt_multiplication'
+f_p_blkt_multiplication    = 1.18         *Energy multiplication in blanket and shield
+* Replaced 'etahtp' with 'eta_coolant_pump_electric'
+eta_coolant_pump_electric   = 1.0          *Electrical efficiency of primary coolant pumps
+fblbe    = 0.47         *Beryllium fraction of blanket by volume
+fblli2o  = 0.07         *Lithium oxide fraction of blanket by volume
+fbllipb  = 0.00         *Lithium lead fraction of blanket by volume
+fblss    = 0.13         *Stainless steel fraction of blanket by volume
+fblvd    = 0.00         *Vanadium fraction of blanket by volume
+fhole    = 0.0          *Area fraction taken up by other holes (not used)
+fwclfr   = 0.1          *First wall coolant fraction
+* Replaced 'htpmw_blkt' with 'p_blkt_coolant_pump_mw'
+p_blkt_coolant_pump_mw = 120.0      *Blanket coolant mechanical pumping power (MW)
+* Replaced 'htpmw_fw' with 'p_fw_coolant_pump_mw'
+p_fw_coolant_pump_mw = 56.0         *First wall coolant mechanical pumping power (MW)
+* Replaced 'htpmw_div' with 'p_div_coolant_pump_mw'
+p_div_coolant_pump_mw = 24.0        *Divertor coolant mechanical pumping power (MW)
+* Replaced 'primary_pumping' with 'i_coolant_pumping'
+i_coolant_pumping = 0     *Switch for pumping power (0: User sets pump power directly)
+* Replaced 'secondary_cycle' with 'i_thermal_electric_conversion'
+i_thermal_electric_conversion = 2     *Switch for power conversion cycle (2: user input thermal-electric efficiency)
+vfblkt   = 0.10         *Coolant void fraction in blanket (blktmodel=0)
+vfshld   = 0.60         *Coolant void fraction in shield
+
+*-------------Heat Transport Variables-------------*
+
+* Replaced 'etath' with 'eta_turbine'
+eta_turbine    = 0.4          *Thermal to electric conversion efficiency; if seconday_cycle=2
+
+*------------Impurity Radiation Module-------------*
+
+*imprad_model = 1        *Switch for impurity radiation model
+* Replaced 'coreradius' with 'radius_plasma_core_norm'
+radius_plasma_core_norm = 0.6        *Normalised radius defining the 'core' region
+
+fimp(1)  = 1.0          *Hydrogen (fraction calculated by code)
+fimp(2)  = 0.1          *Helium (fraction calculated by code)
+fimp(3)  = 0.0          *Beryllium
+fimp(4)  = 0.0          *Carbon
+fimp(5)  = 0.0          *Nitrogen
+fimp(6)  = 0.0          *Oxygen
+fimp(7)  = 0.0          *Neon
+fimp(8)  = 0.0          *Silicon
+fimp(9)  = 0.0          *Argon
+fimp(10) = 0.0          *Iron
+fimp(11) = 0.0          *Nickel
+fimp(12) = 0.0          *Krypton
+fimp(13) = 0.0          *Xenon
+fimp(14) = 1.0E-5       *Tungsten
+
+*---------------------Numerics---------------------*
+
+ioptimz  = 1            *Code operation switch (1: Optimisation, VMCON only)
+maxcal   = 100          *Maximum number of VMCON iterations
+minmax   = 7            *Switch for figure-of-merit (7: Min Capital Cost)
+runtitle = HELIAS-5B
+
+*-----------------Tfcoil Variables-----------------*
+
+fcutfsu  = 0.69         *Copper fraction of cable conductor (TF coils)
+i_tf_sc_mat = 1         *Switch for superconductor material in tf coils (1: ITER Nb3Sn)
+tftmp     = 4.2         *Peak helium coolant temperature in TF coils and PF coils (k)
+* Replaced 'tmpcry' with 'temp_tf_cryo'
+temp_tf_cryo    = 4.2         *Coil temperature for cryogenic plant power calculation (K)
+t_turn_tf = 0.056       *Dimension conductor area including steel and insulation.
+* Replaced 'thicndut' with 'dx_tf_turn_insulation'
+dx_tf_turn_insulation  = 0.002       *Conduit insulation thickness (m)
+* Replaced 'thwcndut' with 'dx_tf_turn_steel'
+dx_tf_turn_steel  = 0.0012      *TF coil conduit case thickness (m)
+* Replaced 'vftf' with 'f_a_tf_turn_cable_space_extra_void'
+f_a_tf_turn_cable_space_extra_void      = 0.3         *Coolant fraction of TF coil leg (i_tf_sup=0)
+* Replaced 'thkcas' with 'dr_tf_nose_case'
+dr_tf_nose_case    = 0.06        * Case thickness
+*-----------------Pfcoil Variables-----------------*
+
+*PF coil vertical positioning adjuster
+zref(1)  = 3.6
+zref(2)  = 1.2
+zref(3)  = 2.5
+zref(4)  = 1.0
+zref(5)  = 1.0
+zref(6)  = 1.0
+zref(7)  = 1.0
+zref(8)  = 1.0
+
+*------------------Cost Variables------------------*
+cost_model = 0          *0: 1990 cost module, the 2015 does not work yet for stellarators
+abktflnc = 15.0         *Allowable first wall/blanket neutron (MW-yr/m2)
+adivflnc = 25.0         *Allowable divertor heat fluence (MW-yr/m2)
+cfactr   = 0.75         *Total plant capacity fraction
+dintrt   = 0.00         *Diff between borrowing and saving interest rates
+fcap0    = 1.15         *Average cost of money for construction of plant
+fcap0cp  = 1.06         *Average cost of money for replaceable components
+fcontng  = 0.15         *Project contingency factor
+fcr0     = 0.065        *Fixed charge rate during construction
+fkind    = 1.0          *Multiplier for nth of a kind costs
+iavail   = 0            *Switch for plant availability model (0: Use input value for cfactr)
+ifueltyp = 0            *Switch (0: treat blanket divertor first wall and fraction fcdfuel of CD equipment as capital cost)
+ireactor = 1            *Switch for net electric power calculations (1: Calculate MW electric and c-o-e)
+lsa      = 2            *Level of safety assurance switch (2: In-between)
+discount_rate = 0.06    *Effective cost of money in constant dollars
+tlife    = 40.0         *Plant life (years)
+ucblvd   = 280.0        *Unit cost for blanket vanadium ($/kg)
+ucdiv    = 5.0E5        *Cost of divertor blade ($)
+ucme     = 3.0E8        *Unit cost of maintenance equipment ($)

process/core/input.py

@@ -1817,7 +1817,7 @@ def __post_init__(self):
         data_structure.physics_variables, int, range=(1, 9)
     ),
     "i_plasma_geometry": InputVariable(
-        data_structure.physics_variables, int, range=(0, 11)
+        data_structure.physics_variables, int, range=(0, 12)
     ),
     "i_plasma_shape": InputVariable(
         data_structure.physics_variables, int, choices=[0, 1]

process/core/io/plot/scans.py

@@ -85,6 +85,7 @@ def plot_scan(
         5: "oacdcp",
         6: "pflux_fw_neutron_max_mw",
         7: "beamfus0",
+        8: "Obsolete",  # OBSOLETE
         9: "temp_plasma_electron_vol_avg_kev",
         10: "boundu(15)",
         11: "beta_norm_max",
@@ -118,7 +119,7 @@ def plot_scan(
         40: "boundu(135)",
         41: "dr_blkt_outboard",
         42: "f_nd_impurity_electrons(9)",
-        43: "Obsolete",  # Removed
+        43: "Obsolete",  # OBSOLETE
         44: "alstrtf",
         45: "temp_tf_superconductor_margin_min",
         46: "boundu(152)",
@@ -128,6 +129,7 @@ def plot_scan(
         50: "f_nd_impurity_electrons(13)",
         51: "f_p_div_lower",
         52: "rad_fraction_sol",
+        53: "Obsolete",  # OBSOLETE
         54: "b_crit_upper_nbti",
         55: "dr_shld_inboard",
         56: "p_cryo_plant_electric_max_mw",
@@ -156,6 +158,7 @@ def plot_scan(
         79: "eta_ecrh_injector_wall_plug",
         80: "fcoolcp",
         81: "n_tf_coil_turns",
+        82: "f_p_plasma_separatrix_rad",
     }
     # -------------------
 

process/data_structure/physics_variables.py

@@ -690,6 +690,7 @@
 - =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)
+- =12 set kappa Menard 1997 aspect-ratio-dependent scaling, triang input
 """