In [ ]:

remove-cell

# SPDX-FileCopyrightText: 2024-present Tokamak Neutron Source Maintainers
#
# SPDX-License-Identifier: LGPL-2.1-or-later

"""Example reading from eqdsk file"""

# SPDX-FileCopyrightText: 2024-present Tokamak Neutron Source Maintainers # # SPDX-License-Identifier: LGPL-2.1-or-later """Example reading from eqdsk file"""

In [ ]:

import numpy as np

from tokamak_neutron_source import (
    FluxMap,
    FractionalFuelComposition,
    TokamakNeutronSource,
    TransportInformation,
)
from tokamak_neutron_source.profile import ParabolicPedestalProfile

import numpy as np from tokamak_neutron_source import ( FluxMap, FractionalFuelComposition, TokamakNeutronSource, TransportInformation, ) from tokamak_neutron_source.profile import ParabolicPedestalProfile

Creation from an EQDSK file.¶

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temperature_profile = ParabolicPedestalProfile(25.0, 5.0, 0.1, 1.45, 2.0, 0.95)  # [keV]
density_profile = ParabolicPedestalProfile(0.8e20, 0.5e19, 0.5e17, 1.0, 2.0, 0.95)
rho_profile = np.linspace(0, 1, 30)

source = TokamakNeutronSource(
    transport=TransportInformation.from_parameterisations(
        ion_temperature_profile=temperature_profile,
        fuel_density_profile=density_profile,
        rho_profile=rho_profile,
        fuel_composition=FractionalFuelComposition(D=0.5, T=0.5),
    ),
    flux_map=FluxMap.from_eqdsk("tests/test_data/eqref_OOB.json"),
    cell_side_length=0.05,
)
f, ax = source.plot()

temperature_profile = ParabolicPedestalProfile(25.0, 5.0, 0.1, 1.45, 2.0, 0.95) # [keV] density_profile = ParabolicPedestalProfile(0.8e20, 0.5e19, 0.5e17, 1.0, 2.0, 0.95) rho_profile = np.linspace(0, 1, 30) source = TokamakNeutronSource( transport=TransportInformation.from_parameterisations( ion_temperature_profile=temperature_profile, fuel_density_profile=density_profile, rho_profile=rho_profile, fuel_composition=FractionalFuelComposition(D=0.5, T=0.5), ), flux_map=FluxMap.from_eqdsk("tests/test_data/eqref_OOB.json"), cell_side_length=0.05, ) f, ax = source.plot()

Normalising fusion power¶

We can calculate the total fusion power from the reactions specified.

However, this may not correspond to some reference value we obtain from another code. There are many reasons why this may be the case:

• Different reactivity parameterisations or XS data
• Different interpolation of poloidal magnetic flux
• Limitations of cell-based discretisation (vs flux surface integrals)

We can correct for this:

In [ ]:

print(f"Total fusion power: {source.calculate_total_fusion_power() / 1e9} GW")
source.normalise_fusion_power(2.2e9)
print(f"Total fusion power: {source.calculate_total_fusion_power() / 1e9} GW")

print(f"Total fusion power: {source.calculate_total_fusion_power() / 1e9} GW") source.normalise_fusion_power(2.2e9) print(f"Total fusion power: {source.calculate_total_fusion_power() / 1e9} GW")