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4 commits
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3 changed files with 30 additions and 26 deletions
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@ -15,6 +15,13 @@ from smr.surfaces import lattice_pitch, bottom_fuel_stack, top_active_core
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from smr.core import core_geometry
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def clone(mat):
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"""Make a shallow copy of a material (sharing compositions)."""
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mat_copy = copy.copy(mat)
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mat_copy.id = None
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return mat_copy
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# Define command-line options
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parser = argparse.ArgumentParser()
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parser.add_argument('-m', '--multipole', action='store_true',
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@ -53,7 +60,7 @@ if args.tallies == 'mat':
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for cell in geometry.get_all_cells().values():
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if cell.fill in fuel_mats:
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# Fill cell with list of "differentiated" materials
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cell.fill = [cell.fill.clone() for i in range(cell.num_instances)]
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cell.fill = [clone(cell.fill) for i in range(cell.num_instances)]
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#### Create OpenMC "materials.xml" file
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all_materials = geometry.get_all_materials()
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@ -7,7 +7,7 @@ import openmc
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from openmc.model import subdivide
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from .materials import mats
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from .surfaces import surfs, pellet_OR, bottom_fuel_rod, top_active_core
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from .surfaces import surfs, pellet_OR, bottom_fuel_stack, top_active_core
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def make_pin(name, surfaces, materials, grid=None):
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@ -700,12 +700,6 @@ def pin_universes(num_rings=10, num_axial=196, depleted=False):
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#### 1.6% ENRICHED FUEL PIN CELL
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if num_axial > 1:
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# Determine z position between each fuel pellet, omitting the surfaces
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# corresponding to the very bottom and top of the active fuel length
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axial_splits = np.linspace(bottom_fuel_rod, top_active_core, num_axial + 1)[1:-1]
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axial_surfs = [openmc.ZPlane(z0=z) for z in axial_splits]
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if num_rings > 1:
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# Get z-cylinder surfaces for each ring
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rings = []
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@ -715,25 +709,28 @@ def pin_universes(num_rings=10, num_axial=196, depleted=False):
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rings.append(cyl)
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def subdivided_fuel(fill):
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# Create universe for UO2 alone with axial/radial subdivision
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uo2_cells = []
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if num_axial > 1:
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for axial_region in subdivide(axial_surfs):
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if num_rings > 1:
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for ring_region in subdivide(rings):
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cell = openmc.Cell(fill=fill, region=axial_region & ring_region)
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uo2_cells.append(cell)
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else:
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uo2_cells.append(openmc.Cell(fill=fill, region=axial_region))
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"""Create universe for UO2 alone with axial/radial subdivision"""
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# Create universe with radial rings
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univ = openmc.Universe()
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if num_rings > 1:
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for ring_region in subdivide(rings):
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cell = openmc.Cell(fill=fill, region=ring_region)
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univ.add_cell(cell)
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else:
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if num_rings > 1:
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for ring_region in subdivide(rings):
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cell = openmc.Cell(fill=fill, region=ring_region)
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uo2_cells.append(cell)
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else:
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raise RuntimeError("Shouldn't call with 1 ring and 1 axial segment")
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univ.add_cell(openmc.Cell(fill=fill))
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return openmc.Universe(cells=uo2_cells)
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# If multiple axial segments are needed, use a lattice to avoid
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# performance cost of neighbor lookups
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if num_axial > 1:
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zlattice = openmc.RectLattice()
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zlattice.lower_left = (-100., -100., bottom_fuel_stack)
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zlattice.pitch = (200., 200., (top_active_core - bottom_fuel_stack)/num_axial)
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zlattice.dimension = (1, 1, num_axial)
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zlattice.universes = np.full((num_axial, 1, 1), univ)
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zlattice.outer = univ
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return zlattice
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else:
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return univ
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# If rings/axial segments are present, create a universe for the subdivided
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# fuel. Otherwise just use a plain material.
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@ -192,7 +192,7 @@ surfs['bot active core'] = openmc.ZPlane(
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surfs['top active core'] = openmc.ZPlane(
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z0=top_active_core, name='top active core')
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surfs['top lower thimble'] = copy.deepcopy(surfs['bot active core'])
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surfs['top lower thimble'] = surfs['bot active core']
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surfs['BA bot'] = openmc.ZPlane(
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z0=bot_burn_abs, name='bottom of BA')
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