forked from crp/ecp-benchmarks
Add axial subdivision of fuel pins
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Paul Romano
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7 changed files with 6888 additions and 770 deletions
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@ -76,4 +76,17 @@
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<color id="11" rgb="255 215 0" />
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<color id="12" rgb="0 0 128" />
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</plot>
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<!--assembly no spacer cell-->
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<plot basis="xy" color_by="cell" filename="assm_no_spacer_cell" id="5" type="slice">
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<origin>0.0 0.0 90.0</origin>
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<width>32.25546 32.25546</width>
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<pixels>2000 2000</pixels>
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<background>255 255 255</background>
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</plot>
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<!--z slice-->
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<plot basis="xz" color_by="cell" filename="assm_xz" id="6" type="slice">
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<origin>0.0 0.0 141.61599999999999</origin>
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<width>32.25546 283.23199999999997</width>
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<pixels>455 4000</pixels>
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</plot>
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</plots>
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@ -1,9 +1,9 @@
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<?xml version='1.0' encoding='utf-8'?>
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<settings>
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<run_mode>eigenvalue</run_mode>
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<particles>10000</particles>
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<batches>200</batches>
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<inactive>100</inactive>
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<particles>1000</particles>
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<batches>20</batches>
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<inactive>10</inactive>
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<source strength="1.0">
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<space type="fission">
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<parameters>-75.26274 -75.26274 36.007 75.26274 75.26274 236.0066</parameters>
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@ -1,31 +1,31 @@
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<?xml version='1.0' encoding='utf-8'?>
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<bins>763</bins>
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<bins>6613</bins>
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</filter>
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<tally id="1" name="depletion tally">
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<filters>1</filters>
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@ -1,9 +1,31 @@
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"""Instantiate pin cell Cells and Universes for core model."""
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import numpy as np
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import openmc
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from .materials import mats
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from .surfaces import surfs, n_rings
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from .surfaces import surfs, n_rings, bottom_fuel_rod, top_active_core
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def subdivide(surfaces):
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"""Create regions separate by a series of surfaces.
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Parameters
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----------
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surfaces : iterable of openmc.Surface
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Surfaces separating regions
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Returns
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-------
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list of openmc.Region
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Regions formed by the given surfaces
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"""
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regions = [-surfaces[0]]
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for s0, s1 in zip(surfaces[:-1], surfaces[1:]):
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regions.append(+s0 & -s1)
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regions.append(+surfaces[-1])
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return regions
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def make_pin(name, surfaces, materials, grid=None):
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@ -579,30 +601,6 @@ stack_surfs_BA = [
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surfs['bot upper nozzle'],
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surfs['top upper nozzle']]
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stack_surfs = [
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surfs['bot support plate'],
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surfs['top support plate'],
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surfs['top lower nozzle'],
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surfs['top lower thimble'],
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surfs['grid1bot'],
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surfs['grid1top'],
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surfs['dashpot top'],
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surfs['grid2bot'],
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surfs['grid2top'],
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surfs['grid3bot'],
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surfs['grid3top'],
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surfs['grid4bot'],
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surfs['grid4top'],
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surfs['top active core'],
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surfs['grid5bot'],
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surfs['grid5top'],
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surfs['top pin plenum'],
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surfs['top FR'],
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surfs['bot upper nozzle'],
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surfs['top upper nozzle']
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]
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# Stack all axial pieces of control rod tubes together for each bank
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univs['BA stack'] = make_stack(
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@ -669,10 +667,26 @@ univs['pin plenum grid (intermediate)'] = make_pin(
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#### 1.6% ENRICHED FUEL PIN CELL
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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, 196)[1:-1]
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axial_surfs = [openmc.ZPlane(z0=z) for z in axial_splits]
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# Get z-cylinder surfaces for each ring
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rings = [surfs['fuel ring {}'.format(i)] for i in range(1, n_rings)]
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fuel_surfaces = rings + [surfs['pellet OR'], surfs['clad IR'],
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surfs['clad OR']]
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fuel_mats = [mats['UO2 1.6']]*10 + [mats['He'], mats['Zr'], mats['H2O']]
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# Create universe for UO2 alone with axial/radial subdivision
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uo2_cells = []
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for axial_region in subdivide(axial_surfs):
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for ring_region in subdivide(rings):
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uo2_cells.append(openmc.Cell(
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fill=mats['UO2 1.6'],
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region=axial_region & ring_region
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))
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univs['Subdivided Fuel (1.6%)'] = openmc.Universe(cells=uo2_cells)
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fuel_surfaces = [surfs['pellet OR'], surfs['clad IR'], surfs['clad OR']]
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fuel_mats = [univs['Subdivided Fuel (1.6%)'], mats['He'], mats['Zr'], mats['H2O']]
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univs['Fuel (1.6%)'] = make_pin(
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'Fuel (1.6%)',
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@ -721,7 +735,17 @@ univs['Fuel (1.6%) stack'] = make_stack(
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#### 2.4% ENRICHED FUEL PIN CELL
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fuel_mats = [mats['UO2 2.4']]*10 + [mats['He'], mats['Zr'], mats['H2O']]
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# Create universe for UO2 alone with axial/radial subdivision
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uo2_cells = []
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for axial_region in subdivide(axial_surfs):
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for ring_region in subdivide(rings):
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uo2_cells.append(openmc.Cell(
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fill=mats['UO2 2.4'],
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region=axial_region & ring_region
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))
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univs['Subdivided Fuel (2.4%)'] = openmc.Universe(cells=uo2_cells)
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fuel_mats = [univs['Subdivided Fuel (2.4%)'], mats['He'], mats['Zr'], mats['H2O']]
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univs['Fuel (2.4%)'] = make_pin(
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'Fuel (2.4%)',
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@ -770,7 +794,17 @@ univs['Fuel (2.4%) stack'] = make_stack(
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#### 3.1% ENRICHED FUEL PIN CELL
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fuel_mats = [mats['UO2 3.1']]*10 + [mats['He'], mats['Zr'], mats['H2O']]
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# Create universe for UO2 alone with axial/radial subdivision
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uo2_cells = []
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for axial_region in subdivide(axial_surfs):
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for ring_region in subdivide(rings):
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uo2_cells.append(openmc.Cell(
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fill=mats['UO2 3.1'],
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region=axial_region & ring_region
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))
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univs['Subdivided Fuel (3.1%)'] = openmc.Universe(cells=uo2_cells)
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fuel_mats = [univs['Subdivided Fuel (3.1%)'], mats['He'], mats['Zr'], mats['H2O']]
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univs['Fuel (3.1%)'] = make_pin(
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'Fuel (3.1%)',
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@ -33,7 +33,7 @@ plot.filename = 'radial_xy_slice'
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plot.colors = colors
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plot.background = [255, 255, 255]
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plot.pixels = [1000, 1000]
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plots += [plot]
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plots.append(plot)
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plot = openmc.Plot(name='axial slice')
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plot.basis = 'xz'
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@ -44,7 +44,7 @@ plot.filename = 'axial_xz_slice'
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plot.colors = colors
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plot.background = [255, 255, 255]
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plot.pixels = [1000, 1000]
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plots += [plot]
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plots.append(plot)
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plot = openmc.Plot(name='assembly grid spacer')
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plot.basis = 'xy'
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@ -55,7 +55,7 @@ plot.filename = 'assm_grid_spacer'
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plot.colors = colors
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plot.background = [255, 255, 255]
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plot.pixels = [2000, 2000]
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plots += [plot]
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plots.append(plot)
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plot = openmc.Plot(name='assembly no spacer')
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plot.basis = 'xy'
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@ -66,4 +66,23 @@ plot.filename = 'assm_no_spacer'
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plot.colors = colors
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plot.background = [255, 255, 255]
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plot.pixels = [2000, 2000]
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plots += [plot]
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plots.append(plot)
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plot = openmc.Plot(name='assembly no spacer cell')
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plot.basis = 'xy'
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plot.color_by = 'cell'
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plot.origin = [0., 0., 90.]
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plot.width = [lattice_pitch*1.5, lattice_pitch*1.5]
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plot.filename = 'assm_no_spacer_cell'
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plot.background = [255, 255, 255]
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plot.pixels = [2000, 2000]
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plots.append(plot)
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plot = openmc.Plot(name='z slice')
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plot.basis = 'xz'
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plot.color_by = 'cell'
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plot.filename = 'assm_xz'
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plot.origin = (0., 0., lowest_extent + (highest_extent - lowest_extent)/2)
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plot.width = (lattice_pitch*1.5, highest_extent - lowest_extent)
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plot.pixels = (int(plot.width[0]/plot.width[1]*4000), 4000)
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plots.append(plot)
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@ -34,6 +34,7 @@ INCHES = 2.54
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# fuel rod parameters
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pellet_OR = 0.3195*INCHES/2 # ML17013A274, Table 4.1-2
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pellet_length = 0.4*INCHES # ML17013A274, Table 4.1-2
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clad_IR = 0.326*INCHES/2 # ML17013A274, Table 4.1-2
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clad_OR = 0.374*INCHES/2 # ML17013A274, Table 4.1-2
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active_fuel_length = 78.74*INCHES # ML17013A274, Figure 4.2-10
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@ -128,10 +129,8 @@ surfs = {}
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# Create radii for rings in fuel
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n_rings = 10
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ring_radii = []
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for i in range(1, n_rings):
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R = sqrt(i*pellet_OR**2/n_rings)
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ring_radii.append(R)
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name = 'fuel ring {}'.format(i)
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surfs[name] = openmc.ZCylinder(R=R, name=name)
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