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Improve z-lattice by using same universe in each level

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This commit is contained in:
Paul Romano 2018-04-10 15:04:38 -05:00
parent 38bcb13900
commit 7dbc5489d1
1 changed files with 14 additions and 28 deletions
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42
smr/smr/pins.py
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@ -700,12 +700,6 @@ def pin_universes(num_rings=10, num_axial=196, depleted=False):
#### 1.6% ENRICHED FUEL PIN CELL
if num_axial > 1:
# Determine z position between each fuel pellet, omitting the surfaces
# corresponding to the very bottom and top of the active fuel length
axial_splits = np.linspace(bottom_fuel_rod, top_active_core, num_axial + 1)[1:-1]
axial_surfs = [openmc.ZPlane(z0=z) for z in axial_splits]
if num_rings > 1:
# Get z-cylinder surfaces for each ring
rings = []
@ -715,35 +709,27 @@ def pin_universes(num_rings=10, num_axial=196, depleted=False):
rings.append(cyl)
def subdivided_fuel(fill):
# Create universe for UO2 alone with axial/radial subdivision
if num_axial > 1:
univs = np.empty((num_axial, 1, 1), dtype=openmc.Universe)
for i in range(num_axial):
univ_i = openmc.Universe()
if num_rings > 1:
for ring_region in subdivide(rings):
cell = openmc.Cell(fill=fill, region=ring_region)
univ_i.add_cell(cell)
else:
univ_i.add_cell(openmc.Cell(fill=fill))
univs[i, 0, 0] = univ_i
"""Create universe for UO2 alone with axial/radial subdivision"""
# Create universe with radial rings
univ = openmc.Universe()
if num_rings > 1:
for ring_region in subdivide(rings):
cell = openmc.Cell(fill=fill, region=ring_region)
univ.add_cell(cell)
else:
univ.add_cell(openmc.Cell(fill=fill))
# If multiple axial segments are needed, use a lattice to avoid
# performance cost of neighbor lookups
if num_axial > 1:
zlattice = openmc.RectLattice()
zlattice.lower_left = (-100., -100., bottom_fuel_rod)
zlattice.pitch = (200., 200., (top_active_core - bottom_fuel_rod)/num_axial)
zlattice.dimension = (1, 1, num_axial)
zlattice.universes = univs
zlattice.universes = np.full((num_axial, 1, 1), univ)
return zlattice
else:
uo2_cells = []
if num_rings > 1:
for ring_region in subdivide(rings):
cell = openmc.Cell(fill=fill, region=ring_region)
uo2_cells.append(cell)
else:
raise RuntimeError("Shouldn't call with 1 ring and 1 axial segment")
return openmc.Universe(cells=uo2_cells)
return univ
# If rings/axial segments are present, create a universe for the subdivided
# fuel. Otherwise just use a plain material.