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Merged
chris-ashe merged 7 commits into from
Dec 17, 2025
Merged

♻️ Create outboard blanket class #3997

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18257cf
Add Outboard and Inboard Blanket classes with basic geometry calculat…
chris-ashe Dec 3, 2025
3cd5afe
Refactor set_pumping_powers_as_fractions to accept parameters and ret…
chris-ashe Dec 3, 2025
ddf2762
Add set_blanket_module_geometry calls in Outboard and Inboard Blanket…
chris-ashe Dec 3, 2025
388e96b
Refactor DCLL and CCFE_HCPB classes to inherit from InboardBlanket an…
chris-ashe Dec 3, 2025
d785fa8
Add geometry calculation methods for inboard and outboard blanket seg…
chris-ashe Dec 3, 2025
4f0caf0
Reviewer changes
chris-ashe Dec 5, 2025
95da307
Rename geometry methods in blanket classes for consistency
chris-ashe Dec 5, 2025
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189 changes: 138 additions & 51 deletions process/blanket_library.py
View file
Open in desktop
Original file line number Diff line number Diff line change
Expand Up @@ -630,30 +630,6 @@ def set_blanket_module_geometry(self):
fwbs_variables.n_blkt_inboard_modules_poloidal = 1
fwbs_variables.n_blkt_outboard_modules_poloidal = 1

# Calculate mid-plane toroidal circumference and segment
# of inboard blanket
blanket_library.len_blkt_inboard_segment_toroidal = (
2.0e0
* np.pi
* (
physics_variables.rmajor
- physics_variables.rminor
- build_variables.dr_fw_plasma_gap_inboard
)
) / fwbs_variables.n_blkt_inboard_modules_toroidal

# Calculate mid-plane toroidal circumference and segment
# of outboard blanke
blanket_library.len_blkt_outboard_segment_toroidal = (
2.0e0
* np.pi
* (
physics_variables.rmajor
+ physics_variables.rminor
+ build_variables.dr_fw_plasma_gap_outboard
)
) / fwbs_variables.n_blkt_outboard_modules_toroidal

# Calculate poloidal height of blanket modules
self.blanket_module_poloidal_height()

Expand Down Expand Up @@ -1921,7 +1897,6 @@ def thermo_hydraulic_model(self, output: bool):

# load in pressures if primary pumping == 2
if fwbs_variables.i_p_coolant_pumping == 2:
self.set_blanket_module_geometry()
deltap = self.thermo_hydraulic_model_pressure_drop_calculations(
output=output
)
Expand Down Expand Up @@ -2978,35 +2953,71 @@ def coolant_pumping_power(
return pumppower


def set_pumping_powers_as_fractions():
# User sets mechanical pumping power as a fraction of thermal power in component

heat_transport_variables.p_fw_coolant_pump_mw = (
heat_transport_variables.f_p_fw_coolant_pump_total_heat
* (
fwbs_variables.p_fw_nuclear_heat_total_mw
+ fwbs_variables.psurffwi
+ fwbs_variables.psurffwo
)
def set_pumping_powers_as_fractions(
f_p_fw_coolant_pump_total_heat: float,
f_p_blkt_coolant_pump_total_heat: float,
f_p_shld_coolant_pump_total_heat: float,
f_p_div_coolant_pump_total_heat: float,
p_fw_nuclear_heat_total_mw: float,
psurffwi: float,
psurffwo: float,
p_blkt_nuclear_heat_total_mw: float,
p_shld_nuclear_heat_mw: float,
p_cp_shield_nuclear_heat_mw: float,
p_plasma_separatrix_mw: float,
p_div_nuclear_heat_total_mw: float,
p_div_rad_total_mw: float,
) -> tuple[float, float, float, float]:
"""
Calculate mechanical pumping powers as fractions of thermal power in each component.

:param f_p_fw_coolant_pump_total_heat: Fraction for FW coolant pump.
:type f_p_fw_coolant_pump_total_heat: float
:param f_p_blkt_coolant_pump_total_heat: Fraction for blanket coolant pump.
:type f_p_blkt_coolant_pump_total_heat: float
:param f_p_shld_coolant_pump_total_heat: Fraction for shield coolant pump.
:type f_p_shld_coolant_pump_total_heat: float
:param f_p_div_coolant_pump_total_heat: Fraction for divertor coolant pump.
:type f_p_div_coolant_pump_total_heat: float
:param p_fw_nuclear_heat_total_mw: Total FW nuclear heating (MW).
:type p_fw_nuclear_heat_total_mw: float
:param psurffwi: Inboard FW surface heating (MW).
:type psurffwi: float
:param psurffwo: Outboard FW surface heating (MW).
:type psurffwo: float
:param p_blkt_nuclear_heat_total_mw: Total blanket nuclear heating (MW).
:type p_blkt_nuclear_heat_total_mw: float
:param p_shld_nuclear_heat_mw: Shield nuclear heating (MW).
:type p_shld_nuclear_heat_mw: float
:param p_cp_shield_nuclear_heat_mw: CP shield nuclear heating (MW).
:type p_cp_shield_nuclear_heat_mw: float
:param p_plasma_separatrix_mw: Plasma separatrix power (MW).
:type p_plasma_separatrix_mw: float
:param p_div_nuclear_heat_total_mw: Divertor nuclear heating (MW).
:type p_div_nuclear_heat_total_mw: float
:param p_div_rad_total_mw: Divertor radiative power (MW).
:type p_div_rad_total_mw: float

:return: Tuple of pumping powers (MW) for FW, blanket, shield, and divertor.
:rtype: tuple[float, float, float, float]
"""
p_fw_coolant_pump_mw = f_p_fw_coolant_pump_total_heat * (
p_fw_nuclear_heat_total_mw + psurffwi + psurffwo
)
heat_transport_variables.p_blkt_coolant_pump_mw = (
heat_transport_variables.f_p_blkt_coolant_pump_total_heat
* fwbs_variables.p_blkt_nuclear_heat_total_mw
p_blkt_coolant_pump_mw = (
f_p_blkt_coolant_pump_total_heat * p_blkt_nuclear_heat_total_mw
)
heat_transport_variables.p_shld_coolant_pump_mw = (
heat_transport_variables.f_p_shld_coolant_pump_total_heat
* (
fwbs_variables.p_shld_nuclear_heat_mw
+ fwbs_variables.p_cp_shield_nuclear_heat_mw
)
p_shld_coolant_pump_mw = f_p_shld_coolant_pump_total_heat * (
p_shld_nuclear_heat_mw + p_cp_shield_nuclear_heat_mw
)
heat_transport_variables.p_div_coolant_pump_mw = (
heat_transport_variables.f_p_div_coolant_pump_total_heat
* (
physics_variables.p_plasma_separatrix_mw
+ fwbs_variables.p_div_nuclear_heat_total_mw
+ fwbs_variables.p_div_rad_total_mw
)
p_div_coolant_pump_mw = f_p_div_coolant_pump_total_heat * (
p_plasma_separatrix_mw + p_div_nuclear_heat_total_mw + p_div_rad_total_mw
)
return (
p_fw_coolant_pump_mw,
p_blkt_coolant_pump_mw,
p_shld_coolant_pump_mw,
p_div_coolant_pump_mw,
)


Expand Down Expand Up @@ -3177,3 +3188,79 @@ def dshellvol(rmajor, rminor, zminor, drin, drout, dz):
vout = v2 - v1

return vin, vout, vin + vout


class OutboardBlanket(BlanketLibrary):
def calculate_basic_geometry(self):
self.component_volumes()

dia_blkt_channel = self.pipe_hydraulic_diameter(i_channel_shape=1)
fwbs_variables.radius_blkt_channel = dia_blkt_channel / 2
(
fwbs_variables.radius_blkt_channel_90_bend,
fwbs_variables.radius_blkt_channel_180_bend,
) = self.calculate_pipe_bend_radius(i_ps=1)

def calculate_blanket_outboard_module_geometry(
self,
n_blkt_outboard_modules_toroidal: int,
rmajor: float,
rminor: float,
dr_fw_plasma_gap_outboard: float,
) -> float:
"""
Calculate the mid-plane toroidal circumference and segment length of the outboard blanket.

:param n_blkt_outboard_modules_toroidal: Number of outboard blanket modules in the toroidal direction.
:type n_blkt_outboard_modules_toroidal: int
:param rmajor: Major radius (m).
:type rmajor: float
:param rminor: Minor radius (m).
:type rminor: float
:param dr_fw_plasma_gap_outboard: Outboard first wall to plasma gap (m).
:type dr_fw_plasma_gap_outboard: float
:return: Length of outboard blanket segment in the toroidal direction (m).
:rtype: float
"""
return (
2.0 * np.pi * (rmajor + rminor + dr_fw_plasma_gap_outboard)
) / n_blkt_outboard_modules_toroidal


class InboardBlanket(BlanketLibrary):
def calculate_basic_geometry(self):
self.component_volumes()

dia_blkt_channel = self.pipe_hydraulic_diameter(i_channel_shape=1)
fwbs_variables.radius_blkt_channel = dia_blkt_channel / 2
(
fwbs_variables.radius_blkt_channel_90_bend,
fwbs_variables.radius_blkt_channel_180_bend,
) = self.calculate_pipe_bend_radius(i_ps=1)

self.set_blanket_module_geometry()

def calculate_blanket_inboard_module_geometry(
self,
n_blkt_inboard_modules_toroidal: int,
rmajor: float,
rminor: float,
dr_fw_plasma_gap_inboard: float,
) -> float:
"""
Calculate the mid-plane toroidal circumference and segment length of the inboard blanket.

:param n_blkt_inboard_modules_toroidal: Number of inboard blanket modules in the toroidal direction.
:type n_blkt_inboard_modules_toroidal: int
:param rmajor: Major radius (m).
:type rmajor: float
:param rminor: Minor radius (m).
:type rminor: float
:param dr_fw_plasma_gap_inboard: Inboard first wall to plasma gap (m).
:type dr_fw_plasma_gap_inboard: float
:return: Length of inboard blanket segment in the toroidal direction (m).
:rtype: float
"""
return (
2.0 * np.pi * (rmajor + rminor + dr_fw_plasma_gap_inboard)
) / n_blkt_inboard_modules_toroidal
40 changes: 37 additions & 3 deletions process/dcll.py
View file
Open in desktop
Original file line number Diff line number Diff line change
Expand Up @@ -3,7 +3,7 @@
from process import (
process_output as po,
)
from process.blanket_library import BlanketLibrary
from process.blanket_library import InboardBlanket, OutboardBlanket
from process.data_structure import (
build_variables,
current_drive_variables,
Expand All @@ -15,7 +15,7 @@
)


class DCLL(BlanketLibrary):
class DCLL(InboardBlanket, OutboardBlanket):
"""This module contains the Dual Coolant Lead Lithium (DCLL) specific submods of PROCESSS.

author: G. Graham, CCFE
Expand Down Expand Up @@ -96,6 +96,21 @@ def run(self, output: bool):
fwbs_variables.radius_blkt_channel_180_bend,
) = self.calculate_pipe_bend_radius(i_ps=1)

self.set_blanket_module_geometry()

blanket_library.len_blkt_inboard_segment_toroidal = self.calculate_blanket_inboard_module_geometry(
n_blkt_inboard_modules_toroidal=fwbs_variables.n_blkt_inboard_modules_toroidal,
rmajor=physics_variables.rmajor,
rminor=physics_variables.rminor,
dr_fw_plasma_gap_inboard=build_variables.dr_fw_plasma_gap_inboard,
)
blanket_library.len_blkt_outboard_segment_toroidal = self.calculate_blanket_outboard_module_geometry(
n_blkt_outboard_modules_toroidal=fwbs_variables.n_blkt_outboard_modules_toroidal,
rmajor=physics_variables.rmajor,
rminor=physics_variables.rminor,
dr_fw_plasma_gap_outboard=build_variables.dr_fw_plasma_gap_outboard,
)

self.primary_coolant_properties(output=output)
self.liquid_breeder_properties(output=output)
self.dcll_neutronics_and_power(output=output)
Expand Down Expand Up @@ -309,7 +324,26 @@ def dcll_power_and_heating(self, output: bool):

if fwbs_variables.i_p_coolant_pumping == 1:
# User sets mechanical pumping power directly
blanket_library.set_pumping_powers_as_fractions()
(
heat_transport_variables.p_fw_coolant_pump_mw,
heat_transport_variables.p_blkt_coolant_pump_mw,
heat_transport_variables.p_shld_coolant_pump_mw,
heat_transport_variables.p_div_coolant_pump_mw,
) = blanket_library.set_pumping_powers_as_fractions(
f_p_fw_coolant_pump_total_heat=heat_transport_variables.f_p_fw_coolant_pump_total_heat,
f_p_blkt_coolant_pump_total_heat=heat_transport_variables.f_p_blkt_coolant_pump_total_heat,
f_p_shld_coolant_pump_total_heat=heat_transport_variables.f_p_shld_coolant_pump_total_heat,
f_p_div_coolant_pump_total_heat=heat_transport_variables.f_p_div_coolant_pump_total_heat,
p_fw_nuclear_heat_total_mw=fwbs_variables.p_fw_nuclear_heat_total_mw,
psurffwi=fwbs_variables.psurffwi,
psurffwo=fwbs_variables.psurffwo,
p_blkt_nuclear_heat_total_mw=fwbs_variables.p_blkt_nuclear_heat_total_mw,
p_shld_nuclear_heat_mw=fwbs_variables.p_shld_nuclear_heat_mw,
p_cp_shield_nuclear_heat_mw=fwbs_variables.p_cp_shield_nuclear_heat_mw,
p_plasma_separatrix_mw=physics_variables.p_plasma_separatrix_mw,
p_div_nuclear_heat_total_mw=fwbs_variables.p_div_nuclear_heat_total_mw,
p_div_rad_total_mw=fwbs_variables.p_div_rad_total_mw,
)

elif fwbs_variables.i_p_coolant_pumping in [2, 3]:
# Mechanical pumping power is calculated for first wall and blanket
Expand Down
40 changes: 37 additions & 3 deletions process/hcpb.py
View file
Open in desktop
Original file line number Diff line number Diff line change
Expand Up @@ -8,7 +8,7 @@
from process import (
process_output as po,
)
from process.blanket_library import BlanketLibrary
from process.blanket_library import InboardBlanket, OutboardBlanket
from process.coolprop_interface import FluidProperties
from process.data_structure import (
build_variables,
Expand All @@ -27,7 +27,7 @@
logger = logging.getLogger(__name__)


class CCFE_HCPB(BlanketLibrary):
class CCFE_HCPB(OutboardBlanket, InboardBlanket):
"""This module contains the PROCESS CCFE HCPB blanket model
based on CCFE HCPB model from the PROCESS engineering paper
PROCESS Engineering paper (M. Kovari et al.)
Expand All @@ -53,6 +53,21 @@ def run(self, output: bool):
fwbs_variables.radius_blkt_channel_180_bend,
) = self.calculate_pipe_bend_radius(i_ps=1)

self.set_blanket_module_geometry()

blanket_library.len_blkt_inboard_segment_toroidal = self.calculate_blanket_inboard_module_geometry(
n_blkt_inboard_modules_toroidal=fwbs_variables.n_blkt_inboard_modules_toroidal,
rmajor=physics_variables.rmajor,
rminor=physics_variables.rminor,
dr_fw_plasma_gap_inboard=build_variables.dr_fw_plasma_gap_inboard,
)
blanket_library.len_blkt_outboard_segment_toroidal = self.calculate_blanket_outboard_module_geometry(
n_blkt_outboard_modules_toroidal=fwbs_variables.n_blkt_outboard_modules_toroidal,
rmajor=physics_variables.rmajor,
rminor=physics_variables.rminor,
dr_fw_plasma_gap_outboard=build_variables.dr_fw_plasma_gap_outboard,
)

# Centrepost neutronics
if physics_variables.itart == 1:
# CP radius at the point of maximum sield radius [m]
Expand Down Expand Up @@ -813,7 +828,26 @@ def powerflow_calc(self, output: bool):

if fwbs_variables.i_p_coolant_pumping == 1:
# User sets mechanical pumping power directly
blanket_library.set_pumping_powers_as_fractions()
(
heat_transport_variables.p_fw_coolant_pump_mw,
heat_transport_variables.p_blkt_coolant_pump_mw,
heat_transport_variables.p_shld_coolant_pump_mw,
heat_transport_variables.p_div_coolant_pump_mw,
) = blanket_library.set_pumping_powers_as_fractions(
f_p_fw_coolant_pump_total_heat=heat_transport_variables.f_p_fw_coolant_pump_total_heat,
f_p_blkt_coolant_pump_total_heat=heat_transport_variables.f_p_blkt_coolant_pump_total_heat,
f_p_shld_coolant_pump_total_heat=heat_transport_variables.f_p_shld_coolant_pump_total_heat,
f_p_div_coolant_pump_total_heat=heat_transport_variables.f_p_div_coolant_pump_total_heat,
p_fw_nuclear_heat_total_mw=fwbs_variables.p_fw_nuclear_heat_total_mw,
psurffwi=fwbs_variables.psurffwi,
psurffwo=fwbs_variables.psurffwo,
p_blkt_nuclear_heat_total_mw=fwbs_variables.p_blkt_nuclear_heat_total_mw,
p_shld_nuclear_heat_mw=heat_transport_variables.p_shld_nuclear_heat_mw,
p_cp_shield_nuclear_heat_mw=fwbs_variables.p_cp_shield_nuclear_heat_mw,
p_plasma_separatrix_mw=physics_variables.p_plasma_separatrix_mw,
p_div_nuclear_heat_total_mw=fwbs_variables.p_div_nuclear_heat_total_mw,
p_div_rad_total_mw=fwbs_variables.p_div_rad_total_mw,
)

elif fwbs_variables.i_p_coolant_pumping == 2:
# Calculate the required material properties of the FW and BB coolant.
Expand Down