Source code for openmc.examples

from numbers import Integral

import numpy as np

import openmc
import openmc.model


[docs]def pwr_pin_cell(): """Create a PWR pin-cell model. This model is a single fuel pin with 2.4 w/o enriched UO2 corresponding to a beginning-of-cycle condition and borated water. The specifications are from the `BEAVRS <http://crpg.mit.edu/research/beavrs>`_ benchmark. Note that the number of particles/batches is initially set very low for testing purposes. Returns ------- model : openmc.model.Model A PWR pin-cell model """ model = openmc.model.Model() # Define materials. fuel = openmc.Material(name='UO2 (2.4%)') fuel.set_density('g/cm3', 10.29769) fuel.add_nuclide("U234", 4.4843e-6) fuel.add_nuclide("U235", 5.5815e-4) fuel.add_nuclide("U238", 2.2408e-2) fuel.add_nuclide("O16", 4.5829e-2) clad = openmc.Material(name='Zircaloy') clad.set_density('g/cm3', 6.55) clad.add_nuclide("Zr90", 2.1827e-2) clad.add_nuclide("Zr91", 4.7600e-3) clad.add_nuclide("Zr92", 7.2758e-3) clad.add_nuclide("Zr94", 7.3734e-3) clad.add_nuclide("Zr96", 1.1879e-3) hot_water = openmc.Material(name='Hot borated water') hot_water.set_density('g/cm3', 0.740582) hot_water.add_nuclide("H1", 4.9457e-2) hot_water.add_nuclide("O16", 2.4672e-2) hot_water.add_nuclide("B10", 8.0042e-6) hot_water.add_nuclide("B11", 3.2218e-5) hot_water.add_s_alpha_beta('c_H_in_H2O') # Define the materials file. model.materials = (fuel, clad, hot_water) # Instantiate ZCylinder surfaces pitch = 1.26 fuel_or = openmc.ZCylinder(x0=0, y0=0, r=0.39218, name='Fuel OR') clad_or = openmc.ZCylinder(x0=0, y0=0, r=0.45720, name='Clad OR') left = openmc.XPlane(x0=-pitch/2, name='left', boundary_type='reflective') right = openmc.XPlane(x0=pitch/2, name='right', boundary_type='reflective') bottom = openmc.YPlane(y0=-pitch/2, name='bottom', boundary_type='reflective') top = openmc.YPlane(y0=pitch/2, name='top', boundary_type='reflective') # Instantiate Cells fuel_pin = openmc.Cell(name='Fuel', fill=fuel) cladding = openmc.Cell(name='Cladding', fill=clad) water = openmc.Cell(name='Water', fill=hot_water) # Use surface half-spaces to define regions fuel_pin.region = -fuel_or cladding.region = +fuel_or & -clad_or water.region = +clad_or & +left & -right & +bottom & -top # Create root universe model.geometry.root_universe = openmc.Universe(0, name='root universe') model.geometry.root_universe.add_cells([fuel_pin, cladding, water]) model.settings.batches = 10 model.settings.inactive = 5 model.settings.particles = 100 model.settings.source = openmc.Source(space=openmc.stats.Box( [-pitch/2, -pitch/2, -1], [pitch/2, pitch/2, 1], only_fissionable=True)) plot = openmc.Plot.from_geometry(model.geometry) plot.pixels = (300, 300) plot.color_by = 'material' model.plots.append(plot) return model
[docs]def pwr_core(): """Create a PWR full-core model. This model is the OECD/NEA Monte Carlo Performance benchmark which is a grossly simplified pressurized water reactor (PWR) with 241 fuel assemblies. Note that the number of particles/batches is initially set very low for testing purposes. Returns ------- model : openmc.model.Model Full-core PWR model """ model = openmc.model.Model() # Define materials. fuel = openmc.Material(1, name='UOX fuel') fuel.set_density('g/cm3', 10.062) fuel.add_nuclide("U234", 4.9476e-6) fuel.add_nuclide("U235", 4.8218e-4) fuel.add_nuclide("U238", 2.1504e-2) fuel.add_nuclide("Xe135", 1.0801e-8) fuel.add_nuclide("O16", 4.5737e-2) clad = openmc.Material(2, name='Zircaloy') clad.set_density('g/cm3', 5.77) clad.add_nuclide("Zr90", 0.5145) clad.add_nuclide("Zr91", 0.1122) clad.add_nuclide("Zr92", 0.1715) clad.add_nuclide("Zr94", 0.1738) clad.add_nuclide("Zr96", 0.0280) cold_water = openmc.Material(3, name='Cold borated water') cold_water.set_density('atom/b-cm', 0.07416) cold_water.add_nuclide("H1", 2.0) cold_water.add_nuclide("O16", 1.0) cold_water.add_nuclide("B10", 6.490e-4) cold_water.add_nuclide("B11", 2.689e-3) cold_water.add_s_alpha_beta('c_H_in_H2O') hot_water = openmc.Material(4, name='Hot borated water') hot_water.set_density('atom/b-cm', 0.06614) hot_water.add_nuclide("H1", 2.0) hot_water.add_nuclide("O16", 1.0) hot_water.add_nuclide("B10", 6.490e-4) hot_water.add_nuclide("B11", 2.689e-3) hot_water.add_s_alpha_beta('c_H_in_H2O') rpv_steel = openmc.Material(5, name='Reactor pressure vessel steel') rpv_steel.set_density('g/cm3', 7.9) rpv_steel.add_nuclide("Fe54", 0.05437098, 'wo') rpv_steel.add_nuclide("Fe56", 0.88500663, 'wo') rpv_steel.add_nuclide("Fe57", 0.0208008, 'wo') rpv_steel.add_nuclide("Fe58", 0.00282159, 'wo') rpv_steel.add_nuclide("Ni58", 0.0067198, 'wo') rpv_steel.add_nuclide("Ni60", 0.0026776, 'wo') rpv_steel.add_nuclide("Mn55", 0.01, 'wo') rpv_steel.add_nuclide("Cr52", 0.002092475, 'wo') rpv_steel.add_nuclide("C0", 0.0025, 'wo') rpv_steel.add_nuclide("Cu63", 0.0013696, 'wo') lower_rad_ref = openmc.Material(6, name='Lower radial reflector') lower_rad_ref.set_density('g/cm3', 4.32) lower_rad_ref.add_nuclide("H1", 0.0095661, 'wo') lower_rad_ref.add_nuclide("O16", 0.0759107, 'wo') lower_rad_ref.add_nuclide("B10", 3.08409e-5, 'wo') lower_rad_ref.add_nuclide("B11", 1.40499e-4, 'wo') lower_rad_ref.add_nuclide("Fe54", 0.035620772088, 'wo') lower_rad_ref.add_nuclide("Fe56", 0.579805982228, 'wo') lower_rad_ref.add_nuclide("Fe57", 0.01362750048, 'wo') lower_rad_ref.add_nuclide("Fe58", 0.001848545204, 'wo') lower_rad_ref.add_nuclide("Ni58", 0.055298376566, 'wo') lower_rad_ref.add_nuclide("Mn55", 0.0182870, 'wo') lower_rad_ref.add_nuclide("Cr52", 0.145407678031, 'wo') lower_rad_ref.add_s_alpha_beta('c_H_in_H2O') upper_rad_ref = openmc.Material(7, name='Upper radial reflector / Top plate region') upper_rad_ref.set_density('g/cm3', 4.28) upper_rad_ref.add_nuclide("H1", 0.0086117, 'wo') upper_rad_ref.add_nuclide("O16", 0.0683369, 'wo') upper_rad_ref.add_nuclide("B10", 2.77638e-5, 'wo') upper_rad_ref.add_nuclide("B11", 1.26481e-4, 'wo') upper_rad_ref.add_nuclide("Fe54", 0.035953677186, 'wo') upper_rad_ref.add_nuclide("Fe56", 0.585224740891, 'wo') upper_rad_ref.add_nuclide("Fe57", 0.01375486056, 'wo') upper_rad_ref.add_nuclide("Fe58", 0.001865821363, 'wo') upper_rad_ref.add_nuclide("Ni58", 0.055815129186, 'wo') upper_rad_ref.add_nuclide("Mn55", 0.0184579, 'wo') upper_rad_ref.add_nuclide("Cr52", 0.146766614995, 'wo') upper_rad_ref.add_s_alpha_beta('c_H_in_H2O') bot_plate = openmc.Material(8, name='Bottom plate region') bot_plate.set_density('g/cm3', 7.184) bot_plate.add_nuclide("H1", 0.0011505, 'wo') bot_plate.add_nuclide("O16", 0.0091296, 'wo') bot_plate.add_nuclide("B10", 3.70915e-6, 'wo') bot_plate.add_nuclide("B11", 1.68974e-5, 'wo') bot_plate.add_nuclide("Fe54", 0.03855611055, 'wo') bot_plate.add_nuclide("Fe56", 0.627585036425, 'wo') bot_plate.add_nuclide("Fe57", 0.014750478, 'wo') bot_plate.add_nuclide("Fe58", 0.002000875025, 'wo') bot_plate.add_nuclide("Ni58", 0.059855207342, 'wo') bot_plate.add_nuclide("Mn55", 0.0197940, 'wo') bot_plate.add_nuclide("Cr52", 0.157390026871, 'wo') bot_plate.add_s_alpha_beta('c_H_in_H2O') bot_nozzle = openmc.Material(9, name='Bottom nozzle region') bot_nozzle.set_density('g/cm3', 2.53) bot_nozzle.add_nuclide("H1", 0.0245014, 'wo') bot_nozzle.add_nuclide("O16", 0.1944274, 'wo') bot_nozzle.add_nuclide("B10", 7.89917e-5, 'wo') bot_nozzle.add_nuclide("B11", 3.59854e-4, 'wo') bot_nozzle.add_nuclide("Fe54", 0.030411411144, 'wo') bot_nozzle.add_nuclide("Fe56", 0.495012237964, 'wo') bot_nozzle.add_nuclide("Fe57", 0.01163454624, 'wo') bot_nozzle.add_nuclide("Fe58", 0.001578204652, 'wo') bot_nozzle.add_nuclide("Ni58", 0.047211231662, 'wo') bot_nozzle.add_nuclide("Mn55", 0.0156126, 'wo') bot_nozzle.add_nuclide("Cr52", 0.124142524198, 'wo') bot_nozzle.add_s_alpha_beta('c_H_in_H2O') top_nozzle = openmc.Material(10, name='Top nozzle region') top_nozzle.set_density('g/cm3', 1.746) top_nozzle.add_nuclide("H1", 0.0358870, 'wo') top_nozzle.add_nuclide("O16", 0.2847761, 'wo') top_nozzle.add_nuclide("B10", 1.15699e-4, 'wo') top_nozzle.add_nuclide("B11", 5.27075e-4, 'wo') top_nozzle.add_nuclide("Fe54", 0.02644016154, 'wo') top_nozzle.add_nuclide("Fe56", 0.43037146399, 'wo') top_nozzle.add_nuclide("Fe57", 0.0101152584, 'wo') top_nozzle.add_nuclide("Fe58", 0.00137211607, 'wo') top_nozzle.add_nuclide("Ni58", 0.04104621835, 'wo') top_nozzle.add_nuclide("Mn55", 0.0135739, 'wo') top_nozzle.add_nuclide("Cr52", 0.107931450781, 'wo') top_nozzle.add_s_alpha_beta('c_H_in_H2O') top_fa = openmc.Material(11, name='Top of fuel assemblies') top_fa.set_density('g/cm3', 3.044) top_fa.add_nuclide("H1", 0.0162913, 'wo') top_fa.add_nuclide("O16", 0.1292776, 'wo') top_fa.add_nuclide("B10", 5.25228e-5, 'wo') top_fa.add_nuclide("B11", 2.39272e-4, 'wo') top_fa.add_nuclide("Zr90", 0.43313403903, 'wo') top_fa.add_nuclide("Zr91", 0.09549277374, 'wo') top_fa.add_nuclide("Zr92", 0.14759527104, 'wo') top_fa.add_nuclide("Zr94", 0.15280552077, 'wo') top_fa.add_nuclide("Zr96", 0.02511169542, 'wo') top_fa.add_s_alpha_beta('c_H_in_H2O') bot_fa = openmc.Material(12, name='Bottom of fuel assemblies') bot_fa.set_density('g/cm3', 1.762) bot_fa.add_nuclide("H1", 0.0292856, 'wo') bot_fa.add_nuclide("O16", 0.2323919, 'wo') bot_fa.add_nuclide("B10", 9.44159e-5, 'wo') bot_fa.add_nuclide("B11", 4.30120e-4, 'wo') bot_fa.add_nuclide("Zr90", 0.3741373658, 'wo') bot_fa.add_nuclide("Zr91", 0.0824858164, 'wo') bot_fa.add_nuclide("Zr92", 0.1274914944, 'wo') bot_fa.add_nuclide("Zr94", 0.1319920622, 'wo') bot_fa.add_nuclide("Zr96", 0.0216912612, 'wo') bot_fa.add_s_alpha_beta('c_H_in_H2O') # Define the materials file. model.materials = (fuel, clad, cold_water, hot_water, rpv_steel, lower_rad_ref, upper_rad_ref, bot_plate, bot_nozzle, top_nozzle, top_fa, bot_fa) # Define surfaces. s1 = openmc.ZCylinder(r=0.41, surface_id=1) s2 = openmc.ZCylinder(r=0.475, surface_id=2) s3 = openmc.ZCylinder(r=0.56, surface_id=3) s4 = openmc.ZCylinder(r=0.62, surface_id=4) s5 = openmc.ZCylinder(r=187.6, surface_id=5) s6 = openmc.ZCylinder(r=209.0, surface_id=6) s7 = openmc.ZCylinder(r=229.0, surface_id=7) s8 = openmc.ZCylinder(r=249.0, surface_id=8, boundary_type='vacuum') s31 = openmc.ZPlane(z0=-229.0, surface_id=31, boundary_type='vacuum') s32 = openmc.ZPlane(z0=-199.0, surface_id=32) s33 = openmc.ZPlane(z0=-193.0, surface_id=33) s34 = openmc.ZPlane(z0=-183.0, surface_id=34) s35 = openmc.ZPlane(z0=0.0, surface_id=35) s36 = openmc.ZPlane(z0=183.0, surface_id=36) s37 = openmc.ZPlane(z0=203.0, surface_id=37) s38 = openmc.ZPlane(z0=215.0, surface_id=38) s39 = openmc.ZPlane(z0=223.0, surface_id=39, boundary_type='vacuum') # Define pin cells. fuel_cold = openmc.Universe(name='Fuel pin, cladding, cold water', universe_id=1) c21 = openmc.Cell(cell_id=21, fill=fuel, region=-s1) c22 = openmc.Cell(cell_id=22, fill=clad, region=+s1 & -s2) c23 = openmc.Cell(cell_id=23, fill=cold_water, region=+s2) fuel_cold.add_cells((c21, c22, c23)) tube_cold = openmc.Universe(name='Instrumentation guide tube, ' 'cold water', universe_id=2) c24 = openmc.Cell(cell_id=24, fill=cold_water, region=-s3) c25 = openmc.Cell(cell_id=25, fill=clad, region=+s3 & -s4) c26 = openmc.Cell(cell_id=26, fill=cold_water, region=+s4) tube_cold.add_cells((c24, c25, c26)) fuel_hot = openmc.Universe(name='Fuel pin, cladding, hot water', universe_id=3) c27 = openmc.Cell(cell_id=27, fill=fuel, region=-s1) c28 = openmc.Cell(cell_id=28, fill=clad, region=+s1 & -s2) c29 = openmc.Cell(cell_id=29, fill=hot_water, region=+s2) fuel_hot.add_cells((c27, c28, c29)) tube_hot = openmc.Universe(name='Instrumentation guide tube, hot water', universe_id=4) c30 = openmc.Cell(cell_id=30, fill=hot_water, region=-s3) c31 = openmc.Cell(cell_id=31, fill=clad, region=+s3 & -s4) c32 = openmc.Cell(cell_id=32, fill=hot_water, region=+s4) tube_hot.add_cells((c30, c31, c32)) # Set positions occupied by guide tubes tube_x = np.array([5, 8, 11, 3, 13, 2, 5, 8, 11, 14, 2, 5, 8, 11, 14, 2, 5, 8, 11, 14, 3, 13, 5, 8, 11]) tube_y = np.array([2, 2, 2, 3, 3, 5, 5, 5, 5, 5, 8, 8, 8, 8, 8, 11, 11, 11, 11, 11, 13, 13, 14, 14, 14]) # Define fuel lattices. l100 = openmc.RectLattice(name='Fuel assembly (lower half)', lattice_id=100) l100.lower_left = (-10.71, -10.71) l100.pitch = (1.26, 1.26) l100.universes = np.tile(fuel_cold, (17, 17)) l100.universes[tube_x, tube_y] = tube_cold l101 = openmc.RectLattice(name='Fuel assembly (upper half)', lattice_id=101) l101.lower_left = (-10.71, -10.71) l101.pitch = (1.26, 1.26) l101.universes = np.tile(fuel_hot, (17, 17)) l101.universes[tube_x, tube_y] = tube_hot # Define assemblies. fa_cw = openmc.Universe(name='Water assembly (cold)', universe_id=5) c50 = openmc.Cell(cell_id=50, fill=cold_water, region=+s34 & -s35) fa_cw.add_cell(c50) fa_hw = openmc.Universe(name='Water assembly (hot)', universe_id=7) c70 = openmc.Cell(cell_id=70, fill=hot_water, region=+s35 & -s36) fa_hw.add_cell(c70) fa_cold = openmc.Universe(name='Fuel assembly (cold)', universe_id=6) c60 = openmc.Cell(cell_id=60, fill=l100, region=+s34 & -s35) fa_cold.add_cell(c60) fa_hot = openmc.Universe(name='Fuel assembly (hot)', universe_id=8) c80 = openmc.Cell(cell_id=80, fill=l101, region=+s35 & -s36) fa_hot.add_cell(c80) # Define core lattices l200 = openmc.RectLattice(name='Core lattice (lower half)', lattice_id=200) l200.lower_left = (-224.91, -224.91) l200.pitch = (21.42, 21.42) l200.universes = [ [fa_cw]*21, [fa_cw]*21, [fa_cw]*7 + [fa_cold]*7 + [fa_cw]*7, [fa_cw]*5 + [fa_cold]*11 + [fa_cw]*5, [fa_cw]*4 + [fa_cold]*13 + [fa_cw]*4, [fa_cw]*3 + [fa_cold]*15 + [fa_cw]*3, [fa_cw]*3 + [fa_cold]*15 + [fa_cw]*3, [fa_cw]*2 + [fa_cold]*17 + [fa_cw]*2, [fa_cw]*2 + [fa_cold]*17 + [fa_cw]*2, [fa_cw]*2 + [fa_cold]*17 + [fa_cw]*2, [fa_cw]*2 + [fa_cold]*17 + [fa_cw]*2, [fa_cw]*2 + [fa_cold]*17 + [fa_cw]*2, [fa_cw]*2 + [fa_cold]*17 + [fa_cw]*2, [fa_cw]*2 + [fa_cold]*17 + [fa_cw]*2, [fa_cw]*3 + [fa_cold]*15 + [fa_cw]*3, [fa_cw]*3 + [fa_cold]*15 + [fa_cw]*3, [fa_cw]*4 + [fa_cold]*13 + [fa_cw]*4, [fa_cw]*5 + [fa_cold]*11 + [fa_cw]*5, [fa_cw]*7 + [fa_cold]*7 + [fa_cw]*7, [fa_cw]*21, [fa_cw]*21] l201 = openmc.RectLattice(name='Core lattice (lower half)', lattice_id=201) l201.lower_left = (-224.91, -224.91) l201.pitch = (21.42, 21.42) l201.universes = [ [fa_hw]*21, [fa_hw]*21, [fa_hw]*7 + [fa_hot]*7 + [fa_hw]*7, [fa_hw]*5 + [fa_hot]*11 + [fa_hw]*5, [fa_hw]*4 + [fa_hot]*13 + [fa_hw]*4, [fa_hw]*3 + [fa_hot]*15 + [fa_hw]*3, [fa_hw]*3 + [fa_hot]*15 + [fa_hw]*3, [fa_hw]*2 + [fa_hot]*17 + [fa_hw]*2, [fa_hw]*2 + [fa_hot]*17 + [fa_hw]*2, [fa_hw]*2 + [fa_hot]*17 + [fa_hw]*2, [fa_hw]*2 + [fa_hot]*17 + [fa_hw]*2, [fa_hw]*2 + [fa_hot]*17 + [fa_hw]*2, [fa_hw]*2 + [fa_hot]*17 + [fa_hw]*2, [fa_hw]*2 + [fa_hot]*17 + [fa_hw]*2, [fa_hw]*3 + [fa_hot]*15 + [fa_hw]*3, [fa_hw]*3 + [fa_hot]*15 + [fa_hw]*3, [fa_hw]*4 + [fa_hot]*13 + [fa_hw]*4, [fa_hw]*5 + [fa_hot]*11 + [fa_hw]*5, [fa_hw]*7 + [fa_hot]*7 + [fa_hw]*7, [fa_hw]*21, [fa_hw]*21] # Define root universe. root = openmc.Universe(universe_id=0, name='root universe') c1 = openmc.Cell(cell_id=1, fill=l200, region=-s6 & +s34 & -s35) c2 = openmc.Cell(cell_id=2, fill=l201, region=-s6 & +s35 & -s36) c3 = openmc.Cell(cell_id=3, fill=bot_plate, region=-s7 & +s31 & -s32) c4 = openmc.Cell(cell_id=4, fill=bot_nozzle, region=-s5 & +s32 & -s33) c5 = openmc.Cell(cell_id=5, fill=bot_fa, region=-s5 & +s33 & -s34) c6 = openmc.Cell(cell_id=6, fill=top_fa, region=-s5 & +s36 & -s37) c7 = openmc.Cell(cell_id=7, fill=top_nozzle, region=-s5 & +s37 & -s38) c8 = openmc.Cell(cell_id=8, fill=upper_rad_ref, region=-s7 & +s38 & -s39) c9 = openmc.Cell(cell_id=9, fill=bot_nozzle, region=+s6 & -s7 & +s32 & -s38) c10 = openmc.Cell(cell_id=10, fill=rpv_steel, region=+s7 & -s8 & +s31 & -s39) c11 = openmc.Cell(cell_id=11, fill=lower_rad_ref, region=+s5 & -s6 & +s32 & -s34) c12 = openmc.Cell(cell_id=12, fill=upper_rad_ref, region=+s5 & -s6 & +s36 & -s38) root.add_cells((c1, c2, c3, c4, c5, c6, c7, c8, c9, c10, c11, c12)) # Assign root universe to geometry model.geometry.root_universe = root model.settings.batches = 10 model.settings.inactive = 5 model.settings.particles = 100 model.settings.source = openmc.Source(space=openmc.stats.Box( [-160, -160, -183], [160, 160, 183])) plot = openmc.Plot() plot.origin = (125, 125, 0) plot.width = (250, 250) plot.pixels = (3000, 3000) plot.color_by = 'material' model.plots.append(plot) return model
[docs]def pwr_assembly(): """Create a PWR assembly model. This model is a reflected 17x17 fuel assembly from the the `BEAVRS <http://crpg.mit.edu/research/beavrs>`_ benchmark. The fuel is 2.4 w/o enriched UO2 corresponding to a beginning-of-cycle condition. Note that the number of particles/batches is initially set very low for testing purposes. Returns ------- model : openmc.model.Model A PWR assembly model """ model = openmc.model.Model() # Define materials. fuel = openmc.Material(name='Fuel') fuel.set_density('g/cm3', 10.29769) fuel.add_nuclide("U234", 4.4843e-6) fuel.add_nuclide("U235", 5.5815e-4) fuel.add_nuclide("U238", 2.2408e-2) fuel.add_nuclide("O16", 4.5829e-2) clad = openmc.Material(name='Cladding') clad.set_density('g/cm3', 6.55) clad.add_nuclide("Zr90", 2.1827e-2) clad.add_nuclide("Zr91", 4.7600e-3) clad.add_nuclide("Zr92", 7.2758e-3) clad.add_nuclide("Zr94", 7.3734e-3) clad.add_nuclide("Zr96", 1.1879e-3) hot_water = openmc.Material(name='Hot borated water') hot_water.set_density('g/cm3', 0.740582) hot_water.add_nuclide("H1", 4.9457e-2) hot_water.add_nuclide("O16", 2.4672e-2) hot_water.add_nuclide("B10", 8.0042e-6) hot_water.add_nuclide("B11", 3.2218e-5) hot_water.add_s_alpha_beta('c_H_in_H2O') # Define the materials file. model.materials = (fuel, clad, hot_water) # Instantiate ZCylinder surfaces fuel_or = openmc.ZCylinder(x0=0, y0=0, r=0.39218, name='Fuel OR') clad_or = openmc.ZCylinder(x0=0, y0=0, r=0.45720, name='Clad OR') # Create boundary planes to surround the geometry pitch = 21.42 min_x = openmc.XPlane(x0=-pitch/2, boundary_type='reflective') max_x = openmc.XPlane(x0=+pitch/2, boundary_type='reflective') min_y = openmc.YPlane(y0=-pitch/2, boundary_type='reflective') max_y = openmc.YPlane(y0=+pitch/2, boundary_type='reflective') # Create a fuel pin universe fuel_pin_universe = openmc.Universe(name='Fuel Pin') fuel_cell = openmc.Cell(name='fuel', fill=fuel, region=-fuel_or) clad_cell = openmc.Cell(name='clad', fill=clad, region=+fuel_or & -clad_or) hot_water_cell = openmc.Cell(name='hot water', fill=hot_water, region=+clad_or) fuel_pin_universe.add_cells([fuel_cell, clad_cell, hot_water_cell]) # Create a control rod guide tube universe guide_tube_universe = openmc.Universe(name='Guide Tube') gt_inner_cell = openmc.Cell(name='guide tube inner water', fill=hot_water, region=-fuel_or) gt_clad_cell = openmc.Cell(name='guide tube clad', fill=clad, region=+fuel_or & -clad_or) gt_outer_cell = openmc.Cell(name='guide tube outer water', fill=hot_water, region=+clad_or) guide_tube_universe.add_cells([gt_inner_cell, gt_clad_cell, gt_outer_cell]) # Create fuel assembly Lattice assembly = openmc.RectLattice(name='Fuel Assembly') assembly.pitch = (pitch/17, pitch/17) assembly.lower_left = (-pitch/2, -pitch/2) # Create array indices for guide tube locations in lattice template_x = np.array([5, 8, 11, 3, 13, 2, 5, 8, 11, 14, 2, 5, 8, 11, 14, 2, 5, 8, 11, 14, 3, 13, 5, 8, 11]) template_y = np.array([2, 2, 2, 3, 3, 5, 5, 5, 5, 5, 8, 8, 8, 8, 8, 11, 11, 11, 11, 11, 13, 13, 14, 14, 14]) # Create 17x17 array of universes assembly.universes = np.tile(fuel_pin_universe, (17, 17)) assembly.universes[template_x, template_y] = guide_tube_universe # Create root Cell root_cell = openmc.Cell(name='root cell', fill=assembly) root_cell.region = +min_x & -max_x & +min_y & -max_y # Create root Universe model.geometry.root_universe = openmc.Universe(name='root universe') model.geometry.root_universe.add_cell(root_cell) model.settings.batches = 10 model.settings.inactive = 5 model.settings.particles = 100 model.settings.source = openmc.Source(space=openmc.stats.Box( [-pitch/2, -pitch/2, -1], [pitch/2, pitch/2, 1], only_fissionable=True)) plot = openmc.Plot() plot.origin = (0.0, 0.0, 0) plot.width = (21.42, 21.42) plot.pixels = (300, 300) plot.color_by = 'material' model.plots.append(plot) return model
[docs]def slab_mg(num_regions=1, mat_names=None, mgxslib_name='2g.h5'): """Create a 1D slab model. Parameters ---------- num_regions : int, optional Number of regions in the problem, each with a unique MGXS dataset. Defaults to 1. mat_names : Iterable of str, optional List of the material names to use; defaults to ['mat_1', 'mat_2',...]. mgxslib_name : str, optional MGXS Library file to use; defaults to '2g.h5'. Returns ------- model : openmc.model.Model One-group, 1D slab model """ openmc.check_type('num_regions', num_regions, Integral) openmc.check_greater_than('num_regions', num_regions, 0) if mat_names is not None: openmc.check_length('mat_names', mat_names, num_regions) openmc.check_iterable_type('mat_names', mat_names, str) else: mat_names = [] for i in range(num_regions): mat_names.append('mat_' + str(i + 1)) # # Make Materials materials_file = openmc.Materials() macros = [] mats = [] for i in range(len(mat_names)): macros.append(openmc.Macroscopic('mat_' + str(i + 1))) mats.append(openmc.Material(name=mat_names[i])) mats[-1].set_density('macro', 1.0) mats[-1].add_macroscopic(macros[-1]) materials_file += mats materials_file.cross_sections = mgxslib_name # # Make Geometry rad_outer = 929.45 # Set a cell boundary to exist for every material above (exclude the 0) rads = np.linspace(0., rad_outer, len(mats) + 1, endpoint=True)[1:] # Instantiate Universe root = openmc.Universe(universe_id=0, name='root universe') cells = [] surfs = [] surfs.append(openmc.XPlane(x0=0., boundary_type='reflective')) for r, rad in enumerate(rads): if r == len(rads) - 1: surfs.append(openmc.XPlane(x0=rad, boundary_type='vacuum')) else: surfs.append(openmc.XPlane(x0=rad)) # Instantiate Cells cells = [] for c in range(len(surfs) - 1): cells.append(openmc.Cell()) cells[-1].region = (+surfs[c] & -surfs[c + 1]) cells[-1].fill = mats[c] # Register Cells with Universe root.add_cells(cells) # Instantiate a Geometry, register the root Universe, and export to XML geometry_file = openmc.Geometry(root) # # Make Settings # Instantiate a Settings object, set all runtime parameters settings_file = openmc.Settings() settings_file.energy_mode = "multi-group" settings_file.tabular_legendre = {'enable': False} settings_file.batches = 10 settings_file.inactive = 5 settings_file.particles = 1000 # Build source distribution INF = 1000. bounds = [0., -INF, -INF, rads[0], INF, INF] uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:]) settings_file.source = openmc.source.Source(space=uniform_dist) settings_file.output = {'summary': False} model = openmc.model.Model() model.geometry = geometry_file model.materials = materials_file model.settings = settings_file model.xs_data = macros return model