crp/ecp-benchmarks
1
0
Fork 1
Code Issues Pull requests Projects Releases Packages Wiki Activity Actions

Special treatment for a single radial/axial region in fuel pins

Browse source
This commit is contained in:
Paul Romano 2018-01-17 12:18:11 -06:00
parent dac1af47ad
commit a957d442a8
1 changed files with 58 additions and 44 deletions
Download patch file Download diff file Expand all files Collapse all files

102
smr/smr/pins.py
View file

@ -101,7 +101,7 @@ def make_stack(name, surfaces, universes):
return universe
def make_pin_stack(name, zsurfaces, universes, boundary, pin_universe):
def make_pin_stack(name, zsurfaces, universes, boundary, fuel_fill):
"""Construct a Universe of axially stacked universes with a single inner fuel
pin universe.
@ -118,8 +118,8 @@ def make_pin_stack(name, zsurfaces, universes, boundary, pin_universe):
boundary : openmc.Surface
Boundary between the fuel pin itself and everything outside (gap, clad,
moderator)
pin_universe : openmc.Universe
Universe containing (subdivided) fuel pin
fuel_fill : openmc.Universe or openmc.Material
Universe or material for (possibly subdivided) fuel
Returns
-------
@ -136,7 +136,7 @@ def make_pin_stack(name, zsurfaces, universes, boundary, pin_universe):
universe.add_cell(cell)
cell_name = '{} (i)'.format(name)
cell = openmc.Cell(name=cell_name, fill=pin_universe, region=-boundary)
cell = openmc.Cell(name=cell_name, fill=fuel_fill, region=-boundary)
universe.add_cell(cell)
return universe
@ -681,27 +681,47 @@ def pin_universes(num_rings=10, num_axial=196):
#### 1.6% ENRICHED FUEL PIN CELL
# 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_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]
# Get z-cylinder surfaces for each ring
rings = []
for i in range(num_rings):
R = sqrt(i*pellet_OR**2/num_rings)
cyl = openmc.ZCylinder(R=R, name='fuel ring {}'.format(i))
rings.append(cyl)
if num_rings > 1:
# Get z-cylinder surfaces for each ring
rings = []
for i in range(num_rings):
R = sqrt(i*pellet_OR**2/num_rings)
cyl = openmc.ZCylinder(R=R, name='fuel ring {}'.format(i))
rings.append(cyl)
# Create universe for UO2 alone with axial/radial subdivision
uo2_cells = []
for axial_region in subdivide(axial_surfs):
for ring_region in subdivide(rings):
uo2_cells.append(openmc.Cell(
fill=mats['UO2 1.6'],
region=axial_region & ring_region
))
univs['Subdivided Fuel (1.6%)'] = openmc.Universe(cells=uo2_cells)
def subdivided_fuel(fill):
# Create universe for UO2 alone with axial/radial subdivision
uo2_cells = []
if num_axial > 1:
for axial_region in subdivide(axial_surfs):
if num_rings > 1:
for ring_region in subdivide(rings):
cell = openmc.Cell(fill=fill, region=axial_region & ring_region)
uo2_cells.append(cell)
else:
uo2_cells.append(openmc.Cell(fill=fill, region=axial_region))
else:
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)
# If rings/axial segments are present, create a universe for the subdivided
# fuel. Otherwise just use a plain material.
if num_rings > 1 or num_axial > 1:
fuel_fill = subdivided_fuel(mats['UO2 1.6'])
else:
fuel_fill = mats['UO2 1.6']
outside_pin_surfaces = [surfs['clad IR'], surfs['clad OR']]
outside_pin_mats = [mats['He'], mats['Zr'], mats['H2O']]
@ -753,7 +773,7 @@ def pin_universes(num_rings=10, num_axial=196):
univs['Outside pin']
],
boundary=surfs['pellet OR'],
pin_universe=univs['Subdivided Fuel (1.6%)'])
fuel_fill=fuel_fill)
fuel_stack_surfs = [
surfs['bot support plate'],
@ -788,15 +808,12 @@ def pin_universes(num_rings=10, num_axial=196):
#### 2.4% ENRICHED FUEL PIN CELL
# Create universe for UO2 alone with axial/radial subdivision
uo2_cells = []
for axial_region in subdivide(axial_surfs):
for ring_region in subdivide(rings):
uo2_cells.append(openmc.Cell(
fill=mats['UO2 2.4'],
region=axial_region & ring_region
))
univs['Subdivided Fuel (2.4%)'] = openmc.Universe(cells=uo2_cells)
# If rings/axial segments are present, create a universe for the subdivided
# fuel. Otherwise just use a plain material.
if num_rings > 1 or num_axial > 1:
fuel_fill = subdivided_fuel(mats['UO2 2.4'])
else:
fuel_fill = mats['UO2 2.4']
# Stack all axial pieces of 2.4% enriched fuel pin cell
@ -816,7 +833,7 @@ def pin_universes(num_rings=10, num_axial=196):
univs['Outside pin']
],
boundary=surfs['pellet OR'],
pin_universe=univs['Subdivided Fuel (2.4%)'])
fuel_fill=fuel_fill)
univs['Fuel (2.4%) stack'] = make_stack(
'Fuel (2.4%) stack',
@ -837,15 +854,12 @@ def pin_universes(num_rings=10, num_axial=196):
#### 3.1% ENRICHED FUEL PIN CELL
# Create universe for UO2 alone with axial/radial subdivision
uo2_cells = []
for axial_region in subdivide(axial_surfs):
for ring_region in subdivide(rings):
uo2_cells.append(openmc.Cell(
fill=mats['UO2 3.1'],
region=axial_region & ring_region
))
univs['Subdivided Fuel (3.1%)'] = openmc.Universe(cells=uo2_cells)
# If rings/axial segments are present, create a universe for the subdivided
# fuel. Otherwise just use a plain material.
if num_rings > 1 or num_axial > 1:
fuel_fill = subdivided_fuel(mats['UO2 3.1'])
else:
fuel_fill = mats['UO2 3.1']
# Stack all axial pieces of 3.1% enriched fuel pin cell
@ -865,7 +879,7 @@ def pin_universes(num_rings=10, num_axial=196):
univs['Outside pin']
],
boundary=surfs['pellet OR'],
pin_universe=univs['Subdivided Fuel (3.1%)'])
fuel_fill=fuel_fill)
univs['Fuel (3.1%) stack'] = make_stack(
'Fuel (3.1%) stack',