151 lines
5.4 KiB
Python
151 lines
5.4 KiB
Python
import openmc
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from beavrs.builder import BEAVRS
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def find_assembly(assembly_name, wrap_geometry=True):
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"""Find a fuel assembly with some string name in the BEAVRS OpenMC model.
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This method extracts the fuel assembly and wraps it in an OpenMC Geometry.
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The returned geometry has reflective boundary conditions along all
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boundaries. The z-axis is bounded between z=200 and z=210 cm.
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Parameters
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----------
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assembly_name : str
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The name of the fuel assembly lattice
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wrap_geometry : bool
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If false, the fuel assembly Lattice is returned. If true, the fuel
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assembly Lattice is wrapped in an OpenMC Geometry and returned (default).
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Returns
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-------
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fuel_assembly
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The OpenMC Lattice or Geometry for the assembly or None if not found
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"""
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# Get OpenMC Lattices for the fuel assembly
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fuel_assembly = \
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beavrs.openmc_geometry.get_lattices_by_name(assembly_name)[0]
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# Wrap lattice in a Geometry if requested by the user
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if wrap_geometry:
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# Create a root Cell
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root_cell = openmc.Cell(name='root cell')
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root_cell.fill = fuel_assembly
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# Make mixed reflective / vacuum boundaries
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min_x = openmc.XPlane(x0=-10.70864, boundary_type='reflective')
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max_x = openmc.XPlane(x0=+-10.70864, boundary_type='reflective')
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min_y = openmc.YPlane(y0=-10.70864, boundary_type='reflective')
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max_y = openmc.YPlane(y0=+-10.70864, boundary_type='reflective')
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max_z = openmc.ZPlane(z0=197.5, boundary_type='reflective')
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min_z = openmc.ZPlane(z0=192.5, boundary_type='reflective')
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# Add boundaries to the root Cell
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root_cell.region = \
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+min_x & -max_x & +min_y & -max_y & +min_z & -max_z
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# Create a root Universe
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root_univ = openmc.Universe(universe_id=0, name='root universe')
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root_univ.add_cell(root_cell)
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# Create a Geometry
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fuel_assembly = openmc.Geometry(root_univ)
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return fuel_assembly
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def build_reflector(assembly1_name, assembly2_name):
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"""Build a 2x2 fuel assembly geometry with a water reflector on the
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bottom and right.
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This routine puts reflective boundary conditions along min x, max y and z
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and vacuum boundary conditions along the max x and min y boundaries.
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Parameters
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----------
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assembly1_name : str
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The BEAVRS fuel assembly to place in the bottom right and top left
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assembly2_name : str
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The BEAVRS fuel assembly to place in the bottom left and top right
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Returns
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-------
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openmc.Geometry
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A 2x2 fuel assembly and reflector OpenMC Geometry
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"""
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fuel_assembly1 = find_assembly(assembly1_name, wrap_geometry=False)
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fuel_assembly2 = find_assembly(assembly2_name, wrap_geometry=False)
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# Find the water material
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all_cells = beavrs.main_universe.get_all_cells()
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for cell_uuid, cell in all_cells.items():
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if cell.fill_type == 'material' and cell.fill.name == 'Borated Water':
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water = cell.fill
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# Create a Cell/Universe around the first fuel assembly
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fuel_cell1 = openmc.Cell(name='assm1 cell')
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fuel_cell1.fill = fuel_assembly1
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fuel_univ1 = openmc.Universe(name='assm1 universe')
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fuel_univ1.add_cell(fuel_cell1)
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# Create a Cell/Universe around the second fuel assembly
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fuel_cell2 = openmc.Cell(name='assm2 cell')
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fuel_cell2.fill = fuel_assembly2
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fuel_univ2 = openmc.Universe(name='assm2 universe')
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fuel_univ2.add_cell(fuel_cell2)
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# Create a Cell/Universe with water
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water_cell = openmc.Cell(name='water cell', fill=water)
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water_univ = openmc.Universe(name='water universe')
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water_univ.add_cell(water_cell)
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# Create a 3x3 lattice two fuel assemblies surrounded by a water reflector
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reflector_lattice = openmc.RectLattice(name='reflector')
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reflector_lattice.lower_left = [-32.12592, -32.12592, -500.]
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reflector_lattice.pitch = [21.41728, 21.41728, 1000.]
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reflector_lattice.universes = [[[fuel_univ1, fuel_univ2, water_univ],
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[fuel_univ2, fuel_univ1, water_univ],
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[water_univ, water_univ, water_univ]]]
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# Create a Geometry around the reflected lattice
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root_cell = openmc.Cell(name='root cell')
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root_cell.fill = reflector_lattice
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# Make mixed reflective / vacuum boundaries
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min_x = openmc.XPlane(x0=-32.12592, boundary_type='reflective')
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max_x = openmc.XPlane(x0=+32.12592, boundary_type='vacuum')
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min_y = openmc.YPlane(y0=-32.12592, boundary_type='vacuum')
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max_y = openmc.YPlane(y0=+32.12592, boundary_type='reflective')
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min_z = openmc.ZPlane(z0=192.5, boundary_type='reflective')
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max_z = openmc.ZPlane(z0=197.5, boundary_type='reflective')
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# Add boundaries to the root Cell
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root_cell.region = +min_x & -max_x & +min_y & -max_y & +min_z & -max_z
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# Create a root Universe for this fuel assembly
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root_univ = openmc.Universe(universe_id=0, name='root universe')
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root_univ.add_cell(root_cell)
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# Create an OpenMC Geometry for this fuel assembly
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reflector = openmc.Geometry()
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reflector.root_universe = root_univ
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return reflector
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#### Create OpenMC "materials.xml" and "geometry.xml" files
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# Instantiate a BEAVRS object
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beavrs = BEAVRS()
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# Write all BEAVRS materials to materials.xml file
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beavrs.write_openmc_materials()
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# Extract fuel assemblies of interest from BEAVRS model
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openmc_geometry = build_reflector('Fuel 1.6% enr instr no BAs',
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'Fuel 3.1% enr instr 20')
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