.. glossary::
:sorted:
alpha_t
Turbulence characterization parameter used by the separatrix operational space.
areal_elongation
Elongation of the confined region computed using the poloidal area inside the last-closed-flux-surface :math:`\kappa_A = S_{pol} / (\pi a^2)`.
atomic_data
Dictionary mapping :class:`~cfspopcon.named_options.AtomicSpecies` to datasets giving coronal and non-coronal :math:`L_z` radiated power factors and :math:`\langle Z \rangle` mean charge state curves from `radas <https://github.com/cfs-energy/radas>`_.
average_electron_density
Volume-averaged electron density in the confined region :math:`\bar n_e`.
average_electron_temp
Volume-averaged electron temperature in the confined region :math:`\bar T_e`.
average_ion_density
Volume-averaged ion density in the confined region :math:`\bar n_i`.
average_ion_mass
Average mass of fuel ions, with the average weighted by the relative concentration of each species.
average_ion_temp
Volume-averaged ion temperature in the confined region :math:`\bar T_i`.
average_total_pressure
Sum of electron and ion pressures.
B_pol_out_mid
Poloidal magnetic field at outboard midplane separatrix
B_t_out_mid
Toroidal magnetic field at outboard midplane separatrix
beta_poloidal
Ratio of plasma pressure to magnetic pressure provided by the poloidal magnetic field.
beta_toroidal
Ratio of plasma pressure to magnetic pressure provided by the toroidal magnetic field.
beta_total
Ratio of plasma pressure to magnetic pressure provided by the total magnetic field.
bootstrap_fraction
Fraction of the plasma current due to the bootstrap current.
breakdown_flux_consumption
From a point model estimate given by :cite:`Sugihara`, this expression gives the required flux for ionization.
change_in_dilution
Change in the fuel-ion dilution, resolved per impurity species.
change_in_zeff
Change in the effective charge, resolved per impurity species.
confinement_power_scaling
A :class:`~cfspopcon.named_options.ConfinementPowerScaling` indicating which confinement mode power-threshold scaling to use.
confinement_threshold_scalar
Scalar value applied to the confinement threshold (:math:`P_{LH}` or :math:`P_{LI}`), used to study the effect of increasing or decreasing the threshold.
confinement_time_scalar
Usually denoted :math:`H`, scalar applied to the energy confinement time calculated from a scaling such that :math:`\tau_e = H \tau_{e,scaling}`.
core_impurity_species
A :class:`~cfspopcon.named_options.AtomicSpecies` indicating which species should be used as the core radiator
core_radiated_power_fraction
Fraction of input power radiated from the confined region before it reaches the separatrix.
critical_alpha_MHD
Critical value of :math:`\alpha_{MHD}` used in the separatrix operational space.
current_relaxation_time
Time constant for the radial current diffusion.
cylindrical_safety_factor
Analytical approximation of safety factor at :math:`\rho=0.95` (confusingly, still has some shaping corrections despite being called the 'cylindrical' safety factor).
density_profile_form
A :class:`~cfspopcon.named_options.ProfileForm` indicating which sort of assumed profile shape we should use for the density profiles.
dilution
Fuel-species concentration as a fraction of the electron density :math:`n_{DT}/n_e`.
edge_collisionality
Collisionality at the separatrix.
edge_impurity_concentration
Concentration of the edge radiator (impurity density relative to the electron density) in the edge.
edge_impurity_concentration_in_core
Concentration of the edge-radiator impurity in the core, after applying a compression/enrichment factor.
edge_impurity_enrichment
Ratio of concentration of the edge radiator in the core to in the edge, :math:`f_e = n_{edge}/n_{core}`.
edge_impurity_species
A :class:`~cfspopcon.named_options.AtomicSpecies` indicating which species should be injected into the plasma to increase the power radiated from the confined region.
effective_collisionality
Estimate of collisionality used for computing the expected density peaking.
ejima_coefficient
Empirical linear scaling factor of the product of major radius and plasma current at flattop correlated with resistive flux at start of flattop :math:`C_E`.
electron_density_peaking
Ratio of the peak ion density to the volume-averaged electron density.
electron_density_peaking_offset
Scalar offset of the electron density peaking relative to the density peaking scaling.
electron_density_profile
A 1D profile of the electron density as a function of :math:`\rho_{pol}`.
electron_temp_profile
A 1D profile of the electron temperature as a function of :math:`\rho_{pol}`.
elongation_psi95
Usually denoted :math:`\kappa_{95}`, the elongation at the :math:`\psi_N=0.95` surface.
elongation_ratio_areal_to_psi95
Ratio of areal elongation to elongation at the :math:`\psi_N=0.95` surface, :math:`\kappa_{A}/\kappa_{95}`.
elongation_ratio_sep_to_areal
Ratio of separatrix elongation to areal elongation :math:`\kappa_{sep}/\kappa_A`.
energy_confinement_scaling
Which :math:`\tau_e` energy confinement scaling should be used. Should match a confinement scaling in `cfspopcon.formulas.energy_confinement::energy_confinement_scalings.yaml`.
energy_confinement_scaling_for_L_mode
Which :math:`\tau_e` energy confinement scaling should be used if :math:`P_{SOL} < P_{LH}`. Should match an L-mode confinement scaling in `cfspopcon.formulas.energy_confinement::energy_confinement_scalings.yaml`.
energy_confinement_time
A characteristic time which gives the rate at which the plasma loses energy. In steady-state, :math:`\tau_e=W_p / P_in`.
external_flux
The flux from the time integration of the voltage due to the external inductance of the plasma. The general formula is the time integration of :math:`- L_e\frac{dI_p}{dt} - Ip\frac{dL_e}{dt}`
Note, time-independent POPCON makes the simplification that :math:`L_e` is constant over the ramp-up.
external_inductance
The self-inductance associated with the LCFS of the plasma.
f_shaping
Shaping factor used to compute :math:`q_*`.
fieldline_pitch_at_omp
The magnetic field pitch :math:`B_{tot} / B_{pol}` at the 'upstream' end of a flux tube in the scrape-off-layer, used to convert from poloidal to parallel heat flux density.
flux_needed_from_CS_over_rampup
The amount of flux needed from the CS over ramp up.
fraction_of_external_power_coupled
Fraction of supplied external heating absorbed by the plasma: :math:`f_{coupled}=P_{external} / P_{launched}`.
fraction_of_P_SOL_to_divertor
fraction of the total power going towards the most-loaded divertor target.
fuel_ion_density_profile
A 1D profile of the fuel ion density as a function of :math:`\rho_{pol}`.
fusion_reaction
A `str` indicating which fusion reaction should be used, should match a class name in `cfspopcon.formulas.fusion_reaction.fusion_data`
fusion_triple_product
The product of the energy confinement time, the core ion temperature and core ion density, used as a metric for fusion performance.
greenwald_density_limit
The highest volume-averaged density which can be achieved before a density-limit disruption is triggered.
greenwald_fraction
Ratio of the average electron density to the Greenwald density limit :math:`f_{G}=\bar n_e / n_G`.
heavier_fuel_species_fraction
Fraction of fuel ions which are the heavier species. i.e. for DT fusion, this is :math:`f_T = n_T/(n_T+n_D)`.
impurity_charge_state
The mean charge state of a non-fuel species.
impurity_concentration
Concentration of each impurity species, relative to the electron density.
impurity_residence_time
The average time an impurity ion stays in the scrape-off-layer before it recycles on the wall.
impurity_species
A :class:`~cfspopcon.named_options.AtomicSpecies` indicating which impurity to use for a calculation.
inductive_plasma_current
Plasma current driven by the central solenoid (i.e. excluding the contribution of the bootstrap current).
internal_flux
The flux from the time integration of the voltage due to the internal inductance of the plasma. The general formula is the time integration of :math:`- L_i\frac{dI_p}{dt} - \frac{Ip}{2}\frac{dL_i}{dt}`
Note, time-independent POPCON makes the simplification that :math:`L_i` is constant over the ramp-up.
internal_inductance
The self-inductance of the plasma from the center to the plasma edge.
internal_inductivity
Also known as normalized internal inductance, for a general geometry, is :math:`\frac{\langle B^2_{\theta} \rangle _V}{\langle B_{\theta}(r=LCFS) \rangle}` but is approximated in POPCON for a cylindrical plasma.
intrinsic_impurity_concentration
Concentration of each intrinsic impurity species, relative to the electron density.
inverse_aspect_ratio
Ratio of minor to major radius :math:`\epsilon= a / R_0`.
invmu_0_dLedR
:math:`\frac{1}{\mu_0}\frac{\partial L_e}{\partial R}` (eq.21 in :cite:`Barr_2018`) which is a part of the hoop force and therefore appears in the :term:`vertical_magnetic_field_equation` which counteracts the outward toroidal forces.
ion_density_peaking
Ratio of the peak ion density to the volume-averaged ion density.
ion_density_peaking_offset
Scalar offset of the ion density peaking relative to the density peaking scaling.
ion_heat_diffusivity
A heat diffusion constant which gives a heat flux corresponding to an ion temperature gradient.
ion_temp_profile
A 1D profile of the ion temperature as a function of :math:`\rho_{pol}`.
ion_to_electron_temp_ratio
Ratio of electron and ion temperatures, :math:`T_i/T_e`.
ionization_volume
Volume available above the target for ionization
ionization_volume_density_factor
factor that relates the target density to an averaged density across the ionization volume
kappa_e0
Electron heat conductivity constant, such that :math:`q_{e,\parallel,cond}=\kappa_{e0}T_{e}^{5/2}\nabla_\parallel T_e`.
kappa_ez
finite z correction factor to the electron heat conductivity. per :cite:`Goldston_2017`
lambda_q
The near-scrape-off-layer heat-flux-density decay length.
lambda_q_factor
A scaling factor :math:`C` which can be used to increase or decrease :math:`\lambda_q=C \lambda_{q,scaling}`.
lambda_q_scaling
A :class:`~cfspopcon.named_options.LambdaQScaling` indicating which scaling to use for calculating :term:`lambda_q`.
lengyel_overestimation_factor
A constant calibration factor applied to the impurity concentration calculated by the Lengyel model such that its value approximately matches the value calculated by higher fidelity modelling such as SOLPS.
loop_voltage
inductive loop voltage
magnetic_field_on_axis
Magnetic field at the geometric magnetic axis :math:`B_0 = BR / R0`.
major_radius
The major radius of the geometric magnetic axis.
max_flattop_duration
Given the loop voltage at flattop, and how much flux from the CS has been consumed over the ramp-up, this defines how long your flattop can be.
maximum_P_LH_factor_for_P_SOL
If P_SOL is larger than this factor times the P_LH threshold, core impurities will be seeded to reduce P_SOL to th
mean_ion_charge_state
Mean charge state of the ions (:math:`n_e / \sum_j n_j`)
min_P_radiation
The minimum amount of power which must be radiated from the confined region. If power radiated by the intrinsic impurities
is less than this, a core radiator will be injected until this level is reached.
minimum_core_radiated_fraction
Minimum fraction of :math:`P_{in}` which should be radiated from the confined region, below which we will inject an additional core radiator to increase the radiated power up to this value.
minor_radius
Horizontal minor radius of the plasma :math:`(R_{max,LCFS}-R_{min,LCFS})/2`
n_points_for_confined_region_profiles
The number of points to use for the confined region profiles.
neoclassical_loop_resistivity
Plasma loop neoclassical resistivity.
nesep_over_nebar
Ratio of the separatrix electron density to the volume-averaged electron density :math:`n_{e,sep} / \bar n_e`.
neutral_flux_density_factor
Conversion factor from neutral pressure at duct to neutral recycling flux at the target. From :cite:`Kallenbach_2018`
neutron_power_flux_to_walls
Neutron power per unit area to the wall.
neutron_rate
Number of neutrons produced per second.
normalized_beta
Ratio of plasma pressure to magnetic pressure provided by the total magnetic field, normalized to :math:`\beta_{max} = I_MA / a B_0` (Troyon limit).
normalized_inverse_temp_scale_length
Inverse normalized electron temperature gradient scale length :math:`a / ( T_e / \nabla T_e )`, which defines the shape of the :class:`~cfspopcon.named_options.ProfileForm.prf` profiles.
nu_star
The normalized collisionality.
P_alpha
Fusion power released as alpha particles integrated over the plasma volume.
P_auxiliary_absorbed
auxiliary heating absorbed by the plasma integrated over the plasma volume.
P_auxiliary_launched
External heating supplied to the plasma (entering the volume, but not necessarily absorbed by the plasma) integrated over the plasma volume.
P_external
External heating absorbed by the plasma (ohmic plus auxiliary) integrated over the plasma volume.
P_fusion
Total power generated by fusion integrated over the plasma volume. For DT fusion, this is the sum of the power going to the alpha particles and to the neutrons.
P_in
Total input power to the plasma. Sum of ohmic, auxiliary and alpha power.
P_LH_thresh
Power required to cross the L-H transition.
P_LI_thresh
Power required to cross the L-I transition.
P_neutron
Fusion power released as neutrons integrated over the plasma volume.
P_ohmic
Power deposited in the plasma due to resistive ohmic heating.
P_rad_bremsstrahlung
Power radiated due to Bremmsstrahlung from all species.
P_rad_hydrogen_bremsstrahlung
Power radiated due to Bremmsstrahlung from hydrogen.
P_rad_impurity
Power radiated by impurities in the plasma.
P_rad_synchrotron
Power radiated due to synchrotron radiation.
P_radiation
Power radiated from the confined region due to Bremmsstrahlung, synchrotron and impurity excitation-relaxation processes.
P_radiation_from_core_seeded_impurity
The power radiated by the core radiator.
parallel_connection_length
Parallel length (along a field-line) of a scrape-off-layer flux tube, from an 'upstream' position (usually the outboard midplane) to the divertor target.
PB_over_R
:math:`P_{SOL}B_0/R`, a metric used to estimate how challenging heat exhaust will be.
PBpRnSq
:math:`P_{SOL}B_{pol}/(R n_{sep}^2)`, a metric used to estimate how challenging heat exhaust will be. This metric is approximately :math:`q_\parallel/n_{e,sep}^2`, which in the Lengyel model gives the impurity concentration required for detachment.
peak_electron_density
Peak electron density
peak_electron_temp
Peak electron temperature
peak_fuel_ion_density
Peak fuel ion density (i.e. product of fuel dilution, ion peaking factor and average electron density).
peak_ion_temp
Peak ion temperature
peak_pressure
Peak total pressure in the core.
plasma_current
Current carried by the plasma :math:`I_p`.
plasma_stored_energy
Thermal energy in the plasma.
plasma_volume
Plasma volume inside the last-closed-flux-surface.
poloidal_circumference
Plasma poloidal circumference of the LCFS.
poloidal_field_flux
The surface flux contribution from the vertical magnetic field required for radial force balance (which arises from the poloidal field coils).
poloidal_sound_larmor_radius
The sound Larmor radius using the poloidal magnetic field.
power_crossing_separatrix
Power crossing the separatrix and entering the scrape-off-layer.
pumping_duct_neutral_pressure
Neutral pressure at the baratron position in pumping duct.
Q
Fusion power thermal gain factor.
q_parallel
The parallel heat flux density entering a scrape-off-layer flux tube.
q_perp
The poloidal heat flux density entering a scrape-off-layer flux tube.
q_star
Analytical approximation of safety factor at :math:`\rho=0.95`.
radas_dir
A path to the `radas <https://github.com/cfs-energy/radas>`_ working directory.
radas_version
Version of radas used to construct the atomic data files.
radiated_power_method
A :class:`~cfspopcon.named_options.RadiationMethod` indicating how we should calculate the power radiated from the confined region.
radiated_power_scalar
An enhancement factor :math:`C` to modify the radiated power :math:`P_{rad} = C P_{rad,calculated}`.
ratio_of_divertor_to_duct_pressure
ratio between divertor neutral pressure and pressure at pumping duct
ratio_of_molecular_to_ion_mass
Ratio between neutral molecule mass and ion mass
ratio_of_P_SOL_to_P_LH
The ratio of the power crossing the separatrix to the LH transition threshold power.
ratio_of_P_SOL_to_P_LI
The ratio of the power crossing the separatrix to the LI transition threshold power.
reattachment_time
Time duration for detachment front to reach the target in response to a transient. Per :cite:`Henderson_2023`
reference_electron_density
A constant upstream electron density used when evaluating the :math:`L_Z` impurity radiation curve (due to the reasonably weak dependence of :math:`L_Z` on :math:`n_e`, this approximation shouldn't be too harmful).
reference_ne_tau
A constant :math:`n_e\tau` (upstream electron density times impurity residence time) used when evaluating the :math:`L_Z` impurity radiation curve.
resistive_flux
Usually this is the magnetic flux induced by the resistance of the plasma. However, given that POPCON calculates this with the empirical :math:`C_E`, it may also hold information about flux induced coupling with the wall. :math:`\psi_{res} = C_E\mu_0R_0I_p`.
resistivity_trapped_enhancement_method
A flag to indicate which method should be used when calculating the enhancement of resistivity due to trapped particles.
rho
The square-root of the normalized poloidal flux :math:`\rho_{pol}=\sqrt{\psi_N}`, used as a flux surface label.
rho_star
The ratio of the sound Larmor radius to the major radius for the average ion temperature.
safety_factor_on_axis
On-axis safety factor
separatrix_electron_density
The electron density at the 'upstream' end of a scrape-off-layer flux-tube (usually at the outboard midplane).
separatrix_electron_temp
The electron temperature at the 'upstream' end of a scrape-off-layer flux-tube (usually at the outboard midplane).
separatrix_elongation
Elongation of the last-closed-flux-surface :math:`(Z_{max,LCFS} - Z_{min,LCFS}) / (R_{max,LCFS} - R_{min,LCFS})`.
separatrix_power_transient
Transient increase to power crossing the separatrix. Per :cite:`Henderson_2023`
separatrix_triangularity
Separatrix triangularity (average of upper and lower triangularity).
SepOS_density_limit
Less than 1 if an L-mode is below the density limit, according to the separatrix operational space.
SepOS_LH_transition
Less than 1 if in L-mode and greater than 1 if in H-mode, according to the separatrix operational space.
SepOS_MHD_limit
Less than 1 if below the ideal MHD limit, according to the separatrix operational space.
sheath_heat_transmission_factor
Sheath heat transmission coefficient per equation 2.89 in :cite:`Stangeby_2000`
SOC_LOC_ratio
Ratio of the energy confinement time from the chosen saturated ohmic confinement (SOC) scaling and the chosen linear ohmic confinement (LOC) scaling.
SOL_conduction_fraction
Fraction of power carried by heat conduction in the scrape-off-layer.
SOL_momentum_loss_function
Fraction of momentum entering a scrape-off-layer flux tube which is lost before reaching the divertor target.
SOL_power_loss_fraction
Fraction of power entering a scrape-off-layer flux tube which is lost (radiated or cross-field transported) before reaching the divertor target.
spitzer_resistivity
Plasma loop collisional resistivity.
summed_impurity_density
Density of non-fuel ions.
surface_area
Area of the last-closed-flux-surface, i.e. the surface defined by toroidally revolving the poloidal last-closed-flux-surface.
surface_inductance_coefficients
The set of coefficients from Hirshman :cite:`hirshman` or Barr's :cite:`Barr_2018` paper on external flux which are used to fit analytic expressions, dependent on plasma geometry, to the external inductance and vertical field mutual inductance of the plasma.
sustainment_power_in_electron_channel
The power in the electron channel required to maintain the electron temperature at the separatrix.
sustainment_power_in_ion_channel
The power in the ion channel required to maintain the ion temperature gradient at the separatrix.
target_angle_of_incidence
Angle of incidence between magnetic field vector and surface normal vector at divertor target.
target_electron_density
The electron density at the divertor target.
target_electron_flux
The rate of electrons per unit area reaching the divertor target.
target_electron_temp
The electron temperature at the divertor target.
target_gaussian_spreading
Gaussian spreading coefficient, S, representing diffusive transport between x-point and divertor target
target_neutral_pressure
Neutral pressure at the divertor target.
target_q_parallel
The parallel heat flux density at the divertor target.
temp_profile_form
A :class:`~cfspopcon.named_options.ProfileForm` indicating which sort of assumed profile shape we should use for the temperature profiles.
temp_scale_length_ratio
The ratio of the electron and ion temperature scale lengths at the separatrix :math:`T_i / T_e * \lambda_{T_e} / \lambda_{T_i} = L_{T_e} / L_{T_i}`.
temperature_peaking
Ratio of the peak (electron or ion) temperature to the volume-averaged temperature.
toroidal_flux_expansion
Ratio of the divertor target major radius to the 'upstream' (usually outboard midplane) major radius for the two point model :math:`R_{target} / R_{upstream}`.
total_flux_available_from_CS
The amount of flux available from the central solenoid over the entire pulse.
trapped_particle_fraction
Global average of the fraction of trapped electrons used in the calculation of global plasma resistivity.
triangularity_psi95
Usually denoted :math:`\delta_{95}`, average of upper and lower triangularity at the :math:`\psi_N=0.95` surface.
triangularity_ratio_sep_to_psi95
Ratio of separatrix triangularity to triangularity at the :math:`psi_N=0.95` surface :math:`\delta_{sep}/\delta_{95}.`
troyon_max_beta
The Troyon beta limit.
two_point_model_error_nonconverged_error
Indicates whether the two-point-model should raise an error or return NaN if its iterative solver does not converge.
vertical_field_mutual_inductance
This unitless mutual-inductance quantity provides the coupling between the plasma surface and the vertical magnetic field.
vertical_magnetic_field
Vertical magnetic field derived from the necessary force to balance the hoop force :math:`B_V`
vertical_magnetic_field_equation
Which vertical magnetic field equation to select from :cite:`mit&taka`, :cite:`Barr_2018`, :cite:`Jean`, :cite:`MFEF`
vertical_minor_radius
Vertical minor radius of the plasma :math:`(Z_{max,LCFS}-Z_{min,LCFS})/2`
wall_temperature
Temperature of neutral gas at the wall
z_effective
The "effective charge" of the ions, defined as :math:`\sum_j Z_j^2 n_j / n_e`.