def buildRectangUni(modSetting, pitch, diameter,boron,modT,fuelT,DyFrac,enrich):
uo2=getU(fuelT,DyFrac,enrich)
mod=getMod(modSetting,boron,modT) #loads the moderator
mats = openmc.Materials([uo2, mod])
mats.export_to_xml()
####################build the surfaces################################
fuel_or = openmc.ZCylinder(R=diameter/2)
box = openmc.get_rectangular_prism(width=pitch, height=pitch,boundary_type='reflective')
#################Build the Cells #######################################
fuel_region = -fuel_or #beautiful abuse of operator overloading
mod_region = box & +fuel_or
# c
# c Fuel
# c
# c throwback to MCNP
fuel = openmc.Cell(1, 'fuel')
fuel.fill = uo2
fuel.region = fuel_region
#
# Moderator
#
moderator = openmc.Cell(4, 'moderator')
moderator.fill = mod
moderator.region = mod_region
#I am groot!
groot = openmc.Universe(cells=(fuel, moderator))
geom = openmc.Geometry(groot)
geom.export_to_xml()
cell_filter = openmc.CellFilter([fuel, moderator])
# tallies
buildTallies(cell_filter)
return (fuel,moderator)
def _add_grid_pincells(self):
""" Adds BEAVRS pincellgrid and assembly gridsleeve pincells """
# Rectangular prisms for grid spacers
grid_surfs_tb = \
openmc.get_rectangular_prism(c.rodGridSide_tb, c.rodGridSide_tb)
grid_surfs_i = \
openmc.get_rectangular_prism(c.rodGridSide_i, c.rodGridSide_i)
# Rectangular prisms for lattice grid sleeves
grid_surfs_ass = \
openmc.get_rectangular_prism(c.gridstrapSide, c.gridstrapSide)
# Grids axial surfaces
self.s_grid1_bot = openmc.ZPlane(name='Bottom of grid 1',
z0=c.grid1_bot)
self.s_grid1_top = openmc.ZPlane(name='Top of grid 1', z0=c.grid1_top)
self.s_grid2_bot = openmc.ZPlane(name='Bottom of grid 2',
z0=c.grid2_bot)
self.s_grid2_top = openmc.ZPlane(name='Top of grid 2', z0=c.grid2_top)
self.s_grid3_bot = openmc.ZPlane(name='Bottom of grid 3',
z0=c.grid3_bot)
self.s_grid3_top = openmc.ZPlane(name='Top of grid 3', z0=c.grid3_top)
self.s_grid4_bot = openmc.ZPlane(name='Bottom of grid 4',
z0=c.grid4_bot)
self.s_grid4_top = openmc.ZPlane(name='Top of grid 4', z0=c.grid4_top)
self.s_grid5_bot = openmc.ZPlane(name='Bottom of grid 5',
z0=c.grid5_bot)
self.s_grid5_top = openmc.ZPlane(name='Top of grid 5', z0=c.grid5_top)
self.s_grid6_bot = openmc.ZPlane(name='Bottom of grid 6',
z0=c.grid6_bot)
self.s_grid6_top = openmc.ZPlane(name='Top of grid 6', z0=c.grid6_top)
self.s_grid7_bot = openmc.ZPlane(name='Bottom of grid 7',
z0=c.grid7_bot)
self.s_grid7_top = openmc.ZPlane(name='Top of grid 7', z0=c.grid7_top)
self.s_grid8_bot = openmc.ZPlane(name='Bottom of grid 8',
z0=c.grid8_bot)
self.s_grid8_top = openmc.ZPlane(name='Top of grid 8', z0=c.grid8_top)
# Grids pincell universes
self.u_grid_i = InfinitePinCell(name='Intermediate grid pincell')
self.u_grid_i.add_ring(self.mats['Borated Water'],
grid_surfs_i,
box=True)
self.u_grid_i.add_last_ring(self.mats['Zircaloy 4'])
self.u_grid_i.finalize()
self.u_grid_tb = InfinitePinCell(name='Top/Bottom grid pincell')
self.u_grid_tb.add_ring(self.mats['Borated Water'],
grid_surfs_tb,
box=True)
self.u_grid_tb.add_last_ring(self.mats['Inconel 718'])
self.u_grid_tb.finalize()
self.u_grid_sleeve_i = InfinitePinCell(
name='Intermediate grid sleeve pincell')
self.u_grid_sleeve_i.add_ring(self.mats['Zircaloy 4'],
grid_surfs_ass,
box=True)
self.u_grid_sleeve_i.add_last_ring(self.mats['Borated Water'])
self.u_grid_sleeve_i.finalize()
self.u_grid_sleeve_tb = InfinitePinCell(
name='Top/Bottom grid sleeve pincell')
self.u_grid_sleeve_tb.add_ring(self.mats['Inconel 718'],
grid_surfs_ass,
box=True)
self.u_grid_sleeve_tb.add_last_ring(self.mats['Borated Water'])
self.u_grid_sleeve_tb.finalize()
# Grids axial stack
self.u_grids = AxialPinCell(name='Grids axial universe')
self.u_grids.add_axial_section(self.s_struct_supportPlate_bot,
self.mats['Borated Water'])
self.u_grids.add_axial_section(self.s_struct_lowerNozzle_top,
self.mats['Water SPN'])
self.u_grids.add_axial_section(self.s_grid1_bot,
self.mats['Borated Water'])
self.u_grids.add_axial_section(self.s_grid1_top, self.u_grid_tb)
self.u_grids.add_axial_section(self.s_grid2_bot,
self.mats['Borated Water'])
self.u_grids.add_axial_section(self.s_grid2_top, self.u_grid_i)
self.u_grids.add_axial_section(self.s_grid3_bot,
self.mats['Borated Water'])
self.u_grids.add_axial_section(self.s_grid3_top, self.u_grid_i)
self.u_grids.add_axial_section(self.s_grid4_bot,
self.mats['Borated Water'])
self.u_grids.add_axial_section(self.s_grid4_top, self.u_grid_i)
self.u_grids.add_axial_section(self.s_grid5_bot,
self.mats['Borated Water'])
self.u_grids.add_axial_section(self.s_grid5_top, self.u_grid_i)
self.u_grids.add_axial_section(self.s_grid6_bot,
self.mats['Borated Water'])
self.u_grids.add_axial_section(self.s_grid6_top, self.u_grid_i)
self.u_grids.add_axial_section(self.s_grid7_bot,
self.mats['Borated Water'])
self.u_grids.add_axial_section(self.s_grid7_top, self.u_grid_i)
self.u_grids.add_axial_section(self.s_grid8_bot,
self.mats['Borated Water'])
self.u_grids.add_axial_section(self.s_grid8_top, self.u_grid_tb)
self.u_grids.add_axial_section(self.s_struct_upperNozzle_bot,
self.mats['Borated Water'])
self.u_grids.add_axial_section(self.s_struct_upperNozzle_top,
self.mats['Water SPN'])
self.u_grids.add_last_axial_section(self.mats['Borated Water'])
self.u_grids.finalize()
self.u_gridsleeve = AxialPinCell(name='Grid sleeve axial universe')
self.u_gridsleeve.add_axial_section(self.s_struct_supportPlate_bot,
self.mats['Borated Water'])
self.u_gridsleeve.add_axial_section(self.s_struct_lowerNozzle_top,
self.mats['Water SPN'])
self.u_gridsleeve.add_axial_section(self.s_grid1_bot,
self.mats['Borated Water'])
self.u_gridsleeve.add_axial_section(self.s_grid1_top,
self.u_grid_sleeve_tb)
self.u_gridsleeve.add_axial_section(self.s_grid2_bot,
self.mats['Borated Water'])
self.u_gridsleeve.add_axial_section(self.s_grid2_top,
self.u_grid_sleeve_i)
self.u_gridsleeve.add_axial_section(self.s_grid3_bot,
self.mats['Borated Water'])
self.u_gridsleeve.add_axial_section(self.s_grid3_top,
self.u_grid_sleeve_i)
self.u_gridsleeve.add_axial_section(self.s_grid4_bot,
self.mats['Borated Water'])
self.u_gridsleeve.add_axial_section(self.s_grid4_top,
self.u_grid_sleeve_i)
self.u_gridsleeve.add_axial_section(self.s_grid5_bot,
self.mats['Borated Water'])
self.u_gridsleeve.add_axial_section(self.s_grid5_top,
self.u_grid_sleeve_i)
self.u_gridsleeve.add_axial_section(self.s_grid6_bot,
self.mats['Borated Water'])
self.u_gridsleeve.add_axial_section(self.s_grid6_top,
self.u_grid_sleeve_i)
self.u_gridsleeve.add_axial_section(self.s_grid7_bot,
self.mats['Borated Water'])
self.u_gridsleeve.add_axial_section(self.s_grid7_top,
self.u_grid_sleeve_i)
self.u_gridsleeve.add_axial_section(self.s_grid8_bot,
self.mats['Borated Water'])
self.u_gridsleeve.add_axial_section(self.s_grid8_top,
self.u_grid_sleeve_tb)
self.u_gridsleeve.add_axial_section(self.s_struct_upperNozzle_bot,
self.mats['Borated Water'])
self.u_gridsleeve.add_axial_section(self.s_struct_upperNozzle_top,
self.mats['Water SPN'])
self.u_gridsleeve.add_last_axial_section(self.mats['Borated Water'])
self.u_gridsleeve.finalize()
def pincellfunction(pitch, enrichment):
settings = openmc.Settings()
# Set high tolerance to allow use of lower temperature xs
settings.temperature['tolerance'] = 10000
settings.temperature['method'] = 'nearest'
settings.temperature['multipole'] = True
settings.cutoff = {'energy': 1e-8} #energy cutoff in eV
#############################
### MATERIALS ###
#############################
uo2 = openmc.Material(1, "uo2")
uo2.add_element('U', 1.0, enrichment=enrichment)
uo2.add_element('O', 2.0)
uo2.set_density('g/cm3', 10.97)
uo2.temperature = 900 #kelvin
graphite = openmc.Material(2, "graphite")
graphite.set_density('g/cm3', 1.1995)
graphite.add_element('C', 1.0)
graphite.add_s_alpha_beta('c_Graphite')
graphite.temperature = 600 #kelvin
mats = openmc.Materials([uo2, graphite])
mats.export_to_xml()
#############################
### GEOMETRY ###
#############################
universe = openmc.Universe()
fuel_or = openmc.ZCylinder(R=0.5)
fuel_region = -fuel_or
fuel_cell = openmc.Cell(1, 'fuel')
fuel_cell.fill = uo2
fuel_cell.region = fuel_region
box = openmc.get_rectangular_prism(width=pitch,
height=pitch,
boundary_type='reflective')
water_region = box & +fuel_or
moderator = openmc.Cell(2, 'moderator')
moderator.fill = graphite
moderator.region = water_region
root = openmc.Universe(cells=(fuel_cell, moderator))
geom = openmc.Geometry(root)
geom.export_to_xml()
#####################################
### SOURCE/BATCHES ###
#####################################
point = openmc.stats.Point((0, 0, 0))
src = openmc.Source(space=point)
settings.source = src
settings.batches = 100
settings.inactive = 10
settings.particles = 1000
settings.export_to_xml()
#############################
### TALLIES ###
#############################
# Instantiate an empty Tallies object
tallies_file = openmc.Tallies()
# K-Eigenvalue (infinity) tallies
fiss_rate = openmc.Tally(name='fiss. rate')
fiss_rate.scores = ['nu-fission']
tallies_file.append(fiss_rate)
abs_rate = openmc.Tally(name='abs. rate')
abs_rate.scores = ['absorption']
tallies_file.append(abs_rate)
# Resonance Escape Probability tallies
therm_abs_rate = openmc.Tally(name='therm. abs. rate')
therm_abs_rate.scores = ['absorption']
therm_abs_rate.filters = [openmc.EnergyFilter([0., 0.625])]
tallies_file.append(therm_abs_rate)
# Thermal Flux Utilization tallies
fuel_therm_abs_rate = openmc.Tally(name='fuel therm. abs. rate')
fuel_therm_abs_rate.scores = ['absorption']
fuel_therm_abs_rate.filters = [
openmc.EnergyFilter([0., 0.625]),
openmc.CellFilter([fuel_cell])
]
tallies_file.append(fuel_therm_abs_rate)
# Fast Fission Factor tallies
therm_fiss_rate = openmc.Tally(name='therm. fiss. rate')
therm_fiss_rate.scores = ['nu-fission']
therm_fiss_rate.filters = [openmc.EnergyFilter([0., 0.625])]
tallies_file.append(therm_fiss_rate)
tallies_file.export_to_xml()
#############################
### PLOTTING ###
#############################
p = openmc.Plot()
p.filename = 'pinplot'
p.width = (pitch, pitch)
p.pixels = (200, 200)
p.color_by = 'material'
p.colors = {uo2: 'yellow', graphite: 'grey'}
plots = openmc.Plots([p])
plots.export_to_xml()
openmc.plot_geometry(output=False)
pngstring = 'pinplot{}.png'.format(str(pitch))
subprocess.call(['convert', 'pinplot.ppm', pngstring])
subprocess.call(['mv', pngstring, 'figures/' + pngstring])
#############################
### EXECUTION ###
#############################
openmc.run(output=False)
sp = openmc.StatePoint('statepoint.{}.h5'.format(settings.batches))
# Collect all the tallies
fiss_rate = sp.get_tally(name='fiss. rate')
fiss_rate_df = fiss_rate.get_pandas_dataframe()
abs_rate = sp.get_tally(name='abs. rate')
abs_rate_df = abs_rate.get_pandas_dataframe()
therm_abs_rate = sp.get_tally(name='therm. abs. rate')
therm_abs_rate_df = therm_abs_rate.get_pandas_dataframe()
fuel_therm_abs_rate = sp.get_tally(name='fuel therm. abs. rate')
fuel_therm_abs_rate_df = fuel_therm_abs_rate.get_pandas_dataframe()
therm_fiss_rate = sp.get_tally(name='therm. fiss. rate')
therm_fiss_rate_df = therm_fiss_rate.get_pandas_dataframe()
# Compute k-infinity
kinf = fiss_rate / abs_rate
kinf_df = kinf.get_pandas_dataframe()
# Compute resonance escape probability
res_esc = (therm_abs_rate) / (abs_rate)
res_esc_df = res_esc.get_pandas_dataframe()
# Compute fast fission factor
fast_fiss = fiss_rate / therm_fiss_rate
fast_fiss_df = fast_fiss.get_pandas_dataframe()
# Compute thermal flux utilization
therm_util = fuel_therm_abs_rate / therm_abs_rate
therm_util_df = therm_util.get_pandas_dataframe()
# Compute neutrons produced per absorption
eta = therm_fiss_rate / fuel_therm_abs_rate
eta_df = eta.get_pandas_dataframe()
columns = [
'pitch', 'enrichment', 'kinf mean', 'kinf sd', 'res_esc mean',
'res_esc sd', 'fast_fiss mean', 'fast_fiss sd', 'therm_util mean',
'therm_util sd', 'eta mean', 'eta sd'
]
data = [[
pitch, enrichment, kinf_df['mean'][0], kinf_df['std. dev.'][0],
res_esc_df['mean'][0], res_esc_df['std. dev.'][0],
fast_fiss_df['mean'][0], fast_fiss_df['std. dev.'][0],
therm_util_df['mean'][0], therm_util_df['std. dev.'][0],
eta_df['mean'][0], eta_df['std. dev.'][0]
]]
all_tallies = pd.DataFrame(data, columns=columns)
return all_tallies
fuel_outer_radius = openmc.ZCylinder(x0=0.0, y0=0.0, R=0.39218)
pin_cell_universe = openmc.Universe(name='Fuel Pin')
fuel_cell = openmc.Cell(name='Fuel')
fuel_cell.fill = fuel
fuel_cell.region = -fuel_outer_radius
pin_cell_universe.add_cell(fuel_cell)
moderator_cell = openmc.Cell(name='Moderator')
moderator_cell.fill = water
moderator_cell.region = +fuel_outer_radius
pin_cell_universe.add_cell(moderator_cell)
root_cell = openmc.Cell(name='root cell')
box = openmc.get_rectangular_prism(width=1.26, height=1.26,
boundary_type='reflective')
root_cell.region = box
root_cell.fill = pin_cell_universe
root_universe = openmc.Universe(universe_id=0, name='root universe')
root_universe.add_cell(root_cell)
openmc_geometry = openmc.Geometry(root_universe)
openmc_geometry.export_to_xml()
# ----------------------------------------------------------------------------
# Settings
# ----------------------------------------------------------------------------
fuel_or = openmc.ZCylinder(R=0.54)
clad_ir = openmc.ZCylinder(R=0.56)
clad_or = openmc.ZCylinder(R=0.60)
z1 = openmc.ZPlane(z0=0)
z2 = openmc.ZPlane(z0=60)
z3 = openmc.ZPlane(z0=150)
z4 = openmc.ZPlane(z0=165)
z5 = openmc.ZPlane(z0=-0.4)
z6 = openmc.ZPlane(z0=165.4)
z7 = openmc.ZPlane(z0=82.5)
z8 = openmc.ZPlane(z0=123.95)
z9 = openmc.ZPlane(z0=41.05)
top = openmc.ZPlane(z0=200, boundary_type='vacuum')
bottom = openmc.ZPlane(z0=-200, boundary_type='vacuum')
box = openmc.get_rectangular_prism(width=400,
height=400,
boundary_type='vacuum')
type(box)
#region
fuel_region = -fuel_or & +z2 & -z3
gap_region = +fuel_or & -clad_ir & +z2 & -z3
clad_region = +clad_ir & -clad_or & +z1 & -z4 | -clad_or & -z1 & +z5 | -clad_or & -z6 & +z4
gas_region = -clad_ir & +z1 & -z2 | -clad_ir & -z4 & +z3
pin_region = -clad_or & +z5 & -z6
coolant_region = ~pin_region & -top & +bottom & box
control_region = -clad_or & -z6 & +z5
steel_region = -z6 & +z5
controlvoid_region = ~control_region
#cell
def _add_assembly_surfs(self):
""" Adds BEAVRS assebly surfaces - these include the assembly pitch"""
# Rectangular prism around the edge of the pinlattice
self.assem_surfs = \
openmc.get_rectangular_prism(c.latticePitch, c.latticePitch)
def _add_lattice_surfs(self):
""" Adds BEAVRS lattice surfaces """
# Rectangular prism around the edge of the pinlattice
self.lattice_surfs = \
openmc.get_rectangular_prism(17*c.pinPitch, 17*c.pinPitch)
