forked from crp/ecp-benchmarks
Make differentiation of materials optional for assembly-long and core-fresh
This commit is contained in:
Paul Romano
parent
2b8e9e9f5d
commit
1718798735
2 changed files with 81 additions and 25 deletions
|
|
@ -20,14 +20,18 @@ from smr.pins import pin_universes, make_stack
|
|||
parser = argparse.ArgumentParser()
|
||||
parser.add_argument('--multipole', action='store_true',
|
||||
help='Use multipole cross sections')
|
||||
parser.add_argument('--no-multipole', action='store_false',
|
||||
parser.add_argument('--no-multipole', dest='multipole', action='store_false',
|
||||
help='Do not use multipole cross sections')
|
||||
parser.add_argument('--clone', action='store_true',
|
||||
help='Clone materials for each cell instance')
|
||||
parser.add_argument('--no-clone', dest='clone', action='store_false',
|
||||
help='Do not clone materials for each cell instance')
|
||||
parser.add_argument('-a', '--axial', type=int, default=100,
|
||||
help='Number of axial subdivisions in fuel')
|
||||
parser.add_argument('-d', '--depleted', action='store_true',
|
||||
help='Whether UO2 compositions should represent depleted fuel')
|
||||
parser.add_argument('-o', '--output-dir', type=Path, default=None)
|
||||
parser.set_defaults(multipole=True)
|
||||
parser.set_defaults(clone=False, multipole=True)
|
||||
args = parser.parse_args()
|
||||
|
||||
# Make directory for inputs
|
||||
|
|
@ -97,15 +101,33 @@ for halfspace in surfs['lat grid box inner']:
|
|||
# Define geometry with a single assembly
|
||||
geometry = openmc.Geometry(root_universe)
|
||||
|
||||
|
||||
def clone(material):
|
||||
"""Perform copy of material but share nuclide densities"""
|
||||
shared_mat = copy.copy(material)
|
||||
shared_mat.id = None
|
||||
return shared_mat
|
||||
|
||||
h = active_fuel_length / args.axial
|
||||
|
||||
fuel_mats = {}
|
||||
|
||||
# Count the number of instances for each cell and material
|
||||
if args.clone:
|
||||
geometry.determine_paths(instances_only=True)
|
||||
|
||||
for cell in tqdm(geometry.get_all_material_cells().values(),
|
||||
desc='Assigning volume'):
|
||||
desc='Differentiating materials / assigning volume'):
|
||||
if cell.fill in materials:
|
||||
# Determine if this material is fuel
|
||||
is_fuel = 'UO2 Fuel' in cell.fill.name
|
||||
|
||||
# Fill cell with list of "differentiated" materials if requested
|
||||
if args.clone:
|
||||
cell.fill = [clone(cell.fill) for i in range(cell.num_instances)]
|
||||
|
||||
# Determine volume of each fuel material
|
||||
if 'UO2 Fuel' in cell.fill.name:
|
||||
if is_fuel:
|
||||
upper_right = cell.region.bounding_box[1]
|
||||
if isclose(upper_right[0], rings[0]):
|
||||
ri, ro = 0.0, rings[0]
|
||||
|
|
@ -113,14 +135,25 @@ for cell in tqdm(geometry.get_all_material_cells().values(),
|
|||
ri, ro = rings[0], rings[1]
|
||||
else:
|
||||
ri, ro = rings[1], pellet_OR
|
||||
if ri not in fuel_mats:
|
||||
cell.fill = cell.fill.clone()
|
||||
cell.fill.volume = pi * (ro*ro - ri*ri) * h
|
||||
fuel_mats[ri] = cell.fill
|
||||
|
||||
if args.clone:
|
||||
for mat in cell.fill:
|
||||
mat.volume = pi * (ro*ro - ri*ri) * h
|
||||
else:
|
||||
cell.fill = fuel_mats[ri]
|
||||
# In non-clone mode, we still need to create a copy of the
|
||||
# material for each ring since they get different volumes
|
||||
if ri not in fuel_mats:
|
||||
cell.fill = cell.fill.clone()
|
||||
cell.fill.volume = pi * (ro*ro - ri*ri) * h
|
||||
fuel_mats[ri] = cell.fill
|
||||
else:
|
||||
cell.fill = fuel_mats[ri]
|
||||
else:
|
||||
cell.fill.volume = 1.0
|
||||
if args.clone:
|
||||
for mat in cell.fill:
|
||||
mat.volume = 1.0
|
||||
else:
|
||||
cell.fill.volume = 1.0
|
||||
|
||||
#### Create OpenMC "materials.xml" file
|
||||
print('Getting materials...')
|
||||
|
|
|
|||
|
|
@ -1,29 +1,38 @@
|
|||
#!/usr/bin/env python3
|
||||
|
||||
import os
|
||||
import shutil
|
||||
import copy
|
||||
import argparse
|
||||
from math import pi
|
||||
from pathlib import Path
|
||||
|
||||
import numpy as np
|
||||
|
||||
import openmc
|
||||
from tqdm import tqdm
|
||||
|
||||
from smr.materials import materials
|
||||
from smr.plots import core_plots
|
||||
from smr.surfaces import lattice_pitch, bottom_fuel_stack, top_active_core, \
|
||||
pellet_OR, active_fuel_length
|
||||
from smr.core import core_geometry
|
||||
from smr import inlet_temperature
|
||||
|
||||
|
||||
def clone(material):
|
||||
"""Perform copy of material but share nuclide densities"""
|
||||
shared_mat = copy.copy(material)
|
||||
shared_mat.id = None
|
||||
return shared_mat
|
||||
|
||||
|
||||
# Define command-line options
|
||||
parser = argparse.ArgumentParser()
|
||||
parser.add_argument('--multipole', action='store_true',
|
||||
help='Use multipole cross sections')
|
||||
parser.add_argument('--no-multipole', action='store_false',
|
||||
parser.add_argument('--no-multipole', dest='multipole', action='store_false',
|
||||
help='Do not use multipole cross sections')
|
||||
parser.add_argument('--clone', action='store_true',
|
||||
help='Clone materials for each cell instance')
|
||||
parser.add_argument('--no-clone', dest='clone', action='store_false',
|
||||
help='Do not clone materials for each cell instance')
|
||||
parser.add_argument('-r', '--rings', type=int, default=10,
|
||||
help='Number of annular regions in fuel')
|
||||
parser.add_argument('-a', '--axial', type=int, default=196,
|
||||
|
|
@ -31,7 +40,7 @@ parser.add_argument('-a', '--axial', type=int, default=196,
|
|||
parser.add_argument('-d', '--depleted', action='store_true',
|
||||
help='Whether UO2 compositions should represent depleted fuel')
|
||||
parser.add_argument('-o', '--output-dir', type=Path, default=None)
|
||||
parser.set_defaults(multipole=True)
|
||||
parser.set_defaults(clone=False, multipole=True)
|
||||
args = parser.parse_args()
|
||||
|
||||
# Make directory for inputs
|
||||
|
|
@ -53,22 +62,36 @@ geometry = core_geometry(ring_radii, args.axial, args.depleted)
|
|||
h = active_fuel_length / args.axial
|
||||
fuel_mats = {}
|
||||
|
||||
# Count the number of instances for each cell and material
|
||||
if args.clone:
|
||||
geometry.determine_paths(instances_only=True)
|
||||
|
||||
fuel_volume = pi * pellet_OR**2 * h / args.rings
|
||||
for cell in geometry.get_all_cells().values():
|
||||
for cell in tqdm(geometry.get_all_cells().values(),
|
||||
desc='Differentiating materials / assigning volume'):
|
||||
if cell.fill in materials:
|
||||
# Determine if this material is fuel
|
||||
name = cell.fill.name
|
||||
is_fuel = 'UO2 Fuel' in name
|
||||
|
||||
# Determine volume of each fuel material
|
||||
if 'UO2 Fuel' in cell.fill.name:
|
||||
r_o = cell.region.bounding_box[1][0]
|
||||
if r_o not in fuel_mats:
|
||||
cell.fill = cell.fill.clone()
|
||||
cell.fill.volume = fuel_volume
|
||||
fuel_mats[r_o] = cell.fill
|
||||
if is_fuel:
|
||||
if args.clone:
|
||||
# Fill cell with list of "differentiated" materials if requested
|
||||
cell.fill = [clone(cell.fill) for i in range(cell.num_instances)]
|
||||
for mat in cell.fill:
|
||||
mat.volume = fuel_volume
|
||||
else:
|
||||
cell.fill = fuel_mats[r_o]
|
||||
r_o = cell.region.bounding_box[1][0]
|
||||
if (name, r_o) not in fuel_mats:
|
||||
cell.fill = cell.fill.clone()
|
||||
cell.fill.volume = fuel_volume
|
||||
fuel_mats[name, r_o] = cell.fill
|
||||
else:
|
||||
cell.fill = fuel_mats[name, r_o]
|
||||
else:
|
||||
cell.fill.volume = 1.0
|
||||
|
||||
|
||||
#### Create OpenMC "materials.xml" file
|
||||
all_materials = geometry.get_all_materials()
|
||||
materials = openmc.Materials(all_materials.values())
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue