crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-25 04:25:29 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions 5
OpenMC/tests/input_set.py

903 lines
37 KiB
Python
Raw Blame History

import openmc
from openmc.source import Source
from openmc.stats import Box
import numpy as np
class InputSet(object):
def __init__(self):
self.settings = openmc.Settings()
self.materials = openmc.Materials()
self.geometry = openmc.Geometry()
self.tallies = None
self.plots = None
def export(self):
self.settings.export_to_xml()
self.materials.export_to_xml()
self.geometry.export_to_xml()
if self.tallies is not None:
self.tallies.export_to_xml()
if self.plots is not None:
self.plots.export_to_xml()
def build_default_materials_and_geometry(self):
# Define materials.
fuel = openmc.Material(name='Fuel', material_id=1)
fuel.set_density('g/cm3', 10.062)
fuel.add_nuclide("U234", 4.9476e-6)
fuel.add_nuclide("U235", 4.8218e-4)
fuel.add_nuclide("U236", 9.0402e-5)
fuel.add_nuclide("U238", 2.1504e-2)
fuel.add_nuclide("Np237", 7.3733e-6)
fuel.add_nuclide("Pu238", 1.5148e-6)
fuel.add_nuclide("Pu239", 1.3955e-4)
fuel.add_nuclide("Pu240", 3.4405e-5)
fuel.add_nuclide("Pu241", 2.1439e-5)
fuel.add_nuclide("Pu242", 3.7422e-6)
fuel.add_nuclide("Am241", 4.5041e-7)
fuel.add_nuclide("Am242_m1", 9.2301e-9)
fuel.add_nuclide("Am243", 4.7878e-7)
fuel.add_nuclide("Cm242", 1.0485e-7)
fuel.add_nuclide("Cm243", 1.4268e-9)
fuel.add_nuclide("Cm244", 8.8756e-8)
fuel.add_nuclide("Cm245", 3.5285e-9)
fuel.add_nuclide("Mo95", 2.6497e-5)
fuel.add_nuclide("Tc99", 3.2772e-5)
fuel.add_nuclide("Ru101", 3.0742e-5)
fuel.add_nuclide("Ru103", 2.3505e-6)
fuel.add_nuclide("Ag109", 2.0009e-6)
fuel.add_nuclide("Xe135", 1.0801e-8)
fuel.add_nuclide("Cs133", 3.4612e-5)
fuel.add_nuclide("Nd143", 2.6078e-5)
fuel.add_nuclide("Nd145", 1.9898e-5)
fuel.add_nuclide("Sm147", 1.6128e-6)
fuel.add_nuclide("Sm149", 1.1627e-7)
fuel.add_nuclide("Sm150", 7.1727e-6)
fuel.add_nuclide("Sm151", 5.4947e-7)
fuel.add_nuclide("Sm152", 3.0221e-6)
fuel.add_nuclide("Eu153", 2.6209e-6)
fuel.add_nuclide("Gd155", 1.5369e-9)
fuel.add_nuclide("O16", 4.5737e-2)
clad = openmc.Material(name='Cladding', material_id=2)
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(name='Cold borated water', material_id=3)
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(name='Hot borated water', material_id=4)
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(name='Reactor pressure vessel steel',
material_id=5)
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("Ni61", 0.0001183, 'wo')
rpv_steel.add_nuclide("Ni62", 0.0003835, 'wo')
rpv_steel.add_nuclide("Ni64", 0.0001008, 'wo')
rpv_steel.add_nuclide("Mn55", 0.01, 'wo')
rpv_steel.add_nuclide("Mo92", 0.000849, 'wo')
rpv_steel.add_nuclide("Mo94", 0.0005418, 'wo')
rpv_steel.add_nuclide("Mo95", 0.0009438, 'wo')
rpv_steel.add_nuclide("Mo96", 0.0010002, 'wo')
rpv_steel.add_nuclide("Mo97", 0.0005796, 'wo')
rpv_steel.add_nuclide("Mo98", 0.0014814, 'wo')
rpv_steel.add_nuclide("Mo100", 0.0006042, 'wo')
rpv_steel.add_nuclide("Si28", 0.00367464, 'wo')
rpv_steel.add_nuclide("Si29", 0.00019336, 'wo')
rpv_steel.add_nuclide("Si30", 0.000132, 'wo')
rpv_steel.add_nuclide("Cr50", 0.00010435, 'wo')
rpv_steel.add_nuclide("Cr52", 0.002092475, 'wo')
rpv_steel.add_nuclide("Cr53", 0.00024185, 'wo')
rpv_steel.add_nuclide("Cr54", 6.1325e-05, 'wo')
rpv_steel.add_nuclide("C0", 0.0025, 'wo')
rpv_steel.add_nuclide("Cu63", 0.0013696, 'wo')
rpv_steel.add_nuclide("Cu65", 0.0006304, 'wo')
lower_rad_ref = openmc.Material(name='Lower radial reflector',
material_id=6)
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("Ni60", 0.022034425592, 'wo')
lower_rad_ref.add_nuclide("Ni61", 0.000973510811, 'wo')
lower_rad_ref.add_nuclide("Ni62", 0.003155886695, 'wo')
lower_rad_ref.add_nuclide("Ni64", 0.000829500336, 'wo')
lower_rad_ref.add_nuclide("Mn55", 0.0182870, 'wo')
lower_rad_ref.add_nuclide("Si28", 0.00839976771, 'wo')
lower_rad_ref.add_nuclide("Si29", 0.00044199679, 'wo')
lower_rad_ref.add_nuclide("Si30", 0.0003017355, 'wo')
lower_rad_ref.add_nuclide("Cr50", 0.007251360806, 'wo')
lower_rad_ref.add_nuclide("Cr52", 0.145407678031, 'wo')
lower_rad_ref.add_nuclide("Cr53", 0.016806340306, 'wo')
lower_rad_ref.add_nuclide("Cr54", 0.004261520857, 'wo')
lower_rad_ref.add_s_alpha_beta('c_H_in_H2O')
upper_rad_ref = openmc.Material(name='Upper radial reflector /'
'Top plate region', material_id=7)
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("Ni60", 0.022240333032, 'wo')
upper_rad_ref.add_nuclide("Ni61", 0.000982608081, 'wo')
upper_rad_ref.add_nuclide("Ni62", 0.003185377845, 'wo')
upper_rad_ref.add_nuclide("Ni64", 0.000837251856, 'wo')
upper_rad_ref.add_nuclide("Mn55", 0.0184579, 'wo')
upper_rad_ref.add_nuclide("Si28", 0.00847831314, 'wo')
upper_rad_ref.add_nuclide("Si29", 0.00044612986, 'wo')
upper_rad_ref.add_nuclide("Si30", 0.000304557, 'wo')
upper_rad_ref.add_nuclide("Cr50", 0.00731912987, 'wo')
upper_rad_ref.add_nuclide("Cr52", 0.146766614995, 'wo')
upper_rad_ref.add_nuclide("Cr53", 0.01696340737, 'wo')
upper_rad_ref.add_nuclide("Cr54", 0.004301347765, 'wo')
upper_rad_ref.add_s_alpha_beta('c_H_in_H2O')
bot_plate = openmc.Material(name='Bottom plate region', material_id=8)
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("Ni60", 0.023850159704, 'wo')
bot_plate.add_nuclide("Ni61", 0.001053732407, 'wo')
bot_plate.add_nuclide("Ni62", 0.003415945715, 'wo')
bot_plate.add_nuclide("Ni64", 0.000897854832, 'wo')
bot_plate.add_nuclide("Mn55", 0.0197940, 'wo')
bot_plate.add_nuclide("Si28", 0.00909197802, 'wo')
bot_plate.add_nuclide("Si29", 0.00047842098, 'wo')
bot_plate.add_nuclide("Si30", 0.000326601, 'wo')
bot_plate.add_nuclide("Cr50", 0.007848910646, 'wo')
bot_plate.add_nuclide("Cr52", 0.157390026871, 'wo')
bot_plate.add_nuclide("Cr53", 0.018191270146, 'wo')
bot_plate.add_nuclide("Cr54", 0.004612692337, 'wo')
bot_plate.add_s_alpha_beta('c_H_in_H2O')
bot_nozzle = openmc.Material(name='Bottom nozzle region',
material_id=9)
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("Ni60", 0.018811987544, 'wo')
bot_nozzle.add_nuclide("Ni61", 0.000831139127, 'wo')
bot_nozzle.add_nuclide("Ni62", 0.002694352115, 'wo')
bot_nozzle.add_nuclide("Ni64", 0.000708189552, 'wo')
bot_nozzle.add_nuclide("Mn55", 0.0156126, 'wo')
bot_nozzle.add_nuclide("Si28", 0.007171335558, 'wo')
bot_nozzle.add_nuclide("Si29", 0.000377356542, 'wo')
bot_nozzle.add_nuclide("Si30", 0.0002576079, 'wo')
bot_nozzle.add_nuclide("Cr50", 0.006190885148, 'wo')
bot_nozzle.add_nuclide("Cr52", 0.124142524198, 'wo')
bot_nozzle.add_nuclide("Cr53", 0.014348496148, 'wo')
bot_nozzle.add_nuclide("Cr54", 0.003638294506, 'wo')
bot_nozzle.add_s_alpha_beta('c_H_in_H2O')
top_nozzle = openmc.Material(name='Top nozzle region', material_id=10)
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("Ni60", 0.0163554502, 'wo')
top_nozzle.add_nuclide("Ni61", 0.000722605975, 'wo')
top_nozzle.add_nuclide("Ni62", 0.002342513875, 'wo')
top_nozzle.add_nuclide("Ni64", 0.0006157116, 'wo')
top_nozzle.add_nuclide("Mn55", 0.0135739, 'wo')
top_nozzle.add_nuclide("Si28", 0.006234853554, 'wo')
top_nozzle.add_nuclide("Si29", 0.000328078746, 'wo')
top_nozzle.add_nuclide("Si30", 0.0002239677, 'wo')
top_nozzle.add_nuclide("Cr50", 0.005382452306, 'wo')
top_nozzle.add_nuclide("Cr52", 0.107931450781, 'wo')
top_nozzle.add_nuclide("Cr53", 0.012474806806, 'wo')
top_nozzle.add_nuclide("Cr54", 0.003163190107, 'wo')
top_nozzle.add_s_alpha_beta('c_H_in_H2O')
top_fa = openmc.Material(name='Top of fuel assemblies', material_id=11)
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(name='Bottom of fuel assemblies',
material_id=12)
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.
self.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)
s8.boundary_type = 'vacuum'
s31 = openmc.ZPlane(z0=-229.0, surface_id=31)
s31.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)
s39.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)
c21.region = -s1
c21.fill = fuel
c22 = openmc.Cell(cell_id=22)
c22.region = +s1 & -s2
c22.fill = clad
c23 = openmc.Cell(cell_id=23)
c23.region = +s2
c23.fill = cold_water
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)
c24.region = -s3
c24.fill = cold_water
c25 = openmc.Cell(cell_id=25)
c25.region = +s3 & -s4
c25.fill = clad
c26 = openmc.Cell(cell_id=26)
c26.region = +s4
c26.fill = cold_water
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)
c27.region = -s1
c27.fill = fuel
c28 = openmc.Cell(cell_id=28)
c28.region = +s1 & -s2
c28.fill = clad
c29 = openmc.Cell(cell_id=29)
c29.region = +s2
c29.fill = hot_water
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)
c30.region = -s3
c30.fill = hot_water
c31 = openmc.Cell(cell_id=31)
c31.region = +s3 & -s4
c31.fill = clad
c32 = openmc.Cell(cell_id=32)
c32.region = +s4
c32.fill = hot_water
tube_hot.add_cells((c30, c31, c32))
# 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 = [
[fuel_cold]*17,
[fuel_cold]*17,
[fuel_cold]*5 + [tube_cold] + [fuel_cold]*2 + [tube_cold]
+ [fuel_cold]*2 + [tube_cold] + [fuel_cold]*5,
[fuel_cold]*3 + [tube_cold] + [fuel_cold]*9 + [tube_cold]
+ [fuel_cold]*3,
[fuel_cold]*17,
[fuel_cold]*2 + [tube_cold] + [fuel_cold]*2 + [tube_cold]
+ [fuel_cold]*2 + [tube_cold] + [fuel_cold]*2 + [tube_cold]
+ [fuel_cold]*2 + [tube_cold] + [fuel_cold]*2,
[fuel_cold]*17,
[fuel_cold]*17,
[fuel_cold]*2 + [tube_cold] + [fuel_cold]*2 + [tube_cold]
+ [fuel_cold]*2 + [tube_cold] + [fuel_cold]*2 + [tube_cold]
+ [fuel_cold]*2 + [tube_cold] + [fuel_cold]*2,
[fuel_cold]*17,
[fuel_cold]*17,
[fuel_cold]*2 + [tube_cold] + [fuel_cold]*2 + [tube_cold]
+ [fuel_cold]*2 + [tube_cold] + [fuel_cold]*2 + [tube_cold]
+ [fuel_cold]*2 + [tube_cold] + [fuel_cold]*2,
[fuel_cold]*17,
[fuel_cold]*3 + [tube_cold] + [fuel_cold]*9 + [tube_cold]
+ [fuel_cold]*3,
[fuel_cold]*5 + [tube_cold] + [fuel_cold]*2 + [tube_cold]
+ [fuel_cold]*2 + [tube_cold] + [fuel_cold]*5,
[fuel_cold]*17,
[fuel_cold]*17 ]
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 = [
[fuel_hot]*17,
[fuel_hot]*17,
[fuel_hot]*5 + [tube_hot] + [fuel_hot]*2 + [tube_hot]
+ [fuel_hot]*2 + [tube_hot] + [fuel_hot]*5,
[fuel_hot]*3 + [tube_hot] + [fuel_hot]*9 + [tube_hot]
+ [fuel_hot]*3,
[fuel_hot]*17,
[fuel_hot]*2 + [tube_hot] + [fuel_hot]*2 + [tube_hot]
+ [fuel_hot]*2 + [tube_hot] + [fuel_hot]*2 + [tube_hot]
+ [fuel_hot]*2 + [tube_hot] + [fuel_hot]*2,
[fuel_hot]*17,
[fuel_hot]*17,
[fuel_hot]*2 + [tube_hot] + [fuel_hot]*2 + [tube_hot]
+ [fuel_hot]*2 + [tube_hot] + [fuel_hot]*2 + [tube_hot]
+ [fuel_hot]*2 + [tube_hot] + [fuel_hot]*2,
[fuel_hot]*17,
[fuel_hot]*17,
[fuel_hot]*2 + [tube_hot] + [fuel_hot]*2 + [tube_hot]
+ [fuel_hot]*2 + [tube_hot] + [fuel_hot]*2 + [tube_hot]
+ [fuel_hot]*2 + [tube_hot] + [fuel_hot]*2,
[fuel_hot]*17,
[fuel_hot]*3 + [tube_hot] + [fuel_hot]*9 + [tube_hot]
+ [fuel_hot]*3,
[fuel_hot]*5 + [tube_hot] + [fuel_hot]*2 + [tube_hot]
+ [fuel_hot]*2 + [tube_hot] + [fuel_hot]*5,
[fuel_hot]*17,
[fuel_hot]*17 ]
# Define assemblies.
fa_cw = openmc.Universe(name='Water assembly (cold)', universe_id=5)
c50 = openmc.Cell(cell_id=50)
c50.region = +s34 & -s35
c50.fill = cold_water
fa_cw.add_cells((c50, ))
fa_hw = openmc.Universe(name='Water assembly (hot)', universe_id=7)
c70 = openmc.Cell(cell_id=70)
c70.region = +s35 & -s36
c70.fill = hot_water
fa_hw.add_cells((c70, ))
fa_cold = openmc.Universe(name='Fuel assembly (cold)', universe_id=6)
c60 = openmc.Cell(cell_id=60)
c60.region = +s34 & -s35
c60.fill = l100
fa_cold.add_cells((c60, ))
fa_hot = openmc.Universe(name='Fuel assembly (hot)', universe_id=8)
c80 = openmc.Cell(cell_id=80)
c80.region = +s35 & -s36
c80.fill = l101
fa_hot.add_cells((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)
c1.region = -s6 & +s34 & -s35
c1.fill = l200
c2 = openmc.Cell(cell_id=2)
c2.region = -s6 & +s35 & -s36
c2.fill = l201
c3 = openmc.Cell(cell_id=3)
c3.region = -s7 & +s31 & -s32
c3.fill = bot_plate
c4 = openmc.Cell(cell_id=4)
c4.region = -s5 & +s32 & -s33
c4.fill = bot_nozzle
c5 = openmc.Cell(cell_id=5)
c5.region = -s5 & +s33 & -s34
c5.fill = bot_fa
c6 = openmc.Cell(cell_id=6)
c6.region = -s5 & +s36 & -s37
c6.fill = top_fa
c7 = openmc.Cell(cell_id=7)
c7.region = -s5 & +s37 & -s38
c7.fill = top_nozzle
c8 = openmc.Cell(cell_id=8)
c8.region = -s7 & +s38 & -s39
c8.fill = upper_rad_ref
c9 = openmc.Cell(cell_id=9)
c9.region = +s6 & -s7 & +s32 & -s38
c9.fill = bot_nozzle
c10 = openmc.Cell(cell_id=10)
c10.region = +s7 & -s8 & +s31 & -s39
c10.fill = rpv_steel
c11 = openmc.Cell(cell_id=11)
c11.region = +s5 & -s6 & +s32 & -s34
c11.fill = lower_rad_ref
c12 = openmc.Cell(cell_id=12)
c12.region = +s5 & -s6 & +s36 & -s38
c12.fill = upper_rad_ref
root.add_cells((c1, c2, c3, c4, c5, c6, c7, c8, c9, c10, c11, c12))
# Assign root universe to geometry
self.geometry.root_universe = root
def build_default_settings(self):
self.settings.batches = 10
self.settings.inactive = 5
self.settings.particles = 100
self.settings.source = Source(space=Box(
[-160, -160, -183], [160, 160, 183]))
def build_defualt_plots(self):
plot = openmc.Plot()
plot.filename = 'mat'
plot.origin = (125, 125, 0)
plot.width = (250, 250)
plot.pixels = (3000, 3000)
plot.color = 'mat'
self.plots.add_plot(plot)
class PinCellInputSet(object):
def __init__(self):
self.settings = openmc.Settings()
self.materials = openmc.Materials()
self.geometry = openmc.Geometry()
self.tallies = None
self.plots = None
def export(self):
self.settings.export_to_xml()
self.materials.export_to_xml()
self.geometry.export_to_xml()
if self.tallies is not None:
self.tallies.export_to_xml()
if self.plots is not None:
self.plots.export_to_xml()
def build_default_materials_and_geometry(self):
# 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.
self.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')
left = openmc.XPlane(x0=-0.63, name='left')
right = openmc.XPlane(x0=0.63, name='right')
bottom = openmc.YPlane(y0=-0.63, name='bottom')
top = openmc.YPlane(y0=0.63, name='top')
left.boundary_type = 'reflective'
right.boundary_type = 'reflective'
top.boundary_type = 'reflective'
bottom.boundary_type = 'reflective'
# Instantiate Cells
fuel_pin = openmc.Cell(name='cell 1')
cladding = openmc.Cell(name='cell 3')
water = openmc.Cell(name='cell 2')
# 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
# Register Materials with Cells
fuel_pin.fill = fuel
cladding.fill = clad
water.fill = hot_water
# Instantiate Universe
root = openmc.Universe(universe_id=0, name='root universe')
# Register Cells with Universe
root.add_cells([fuel_pin, cladding, water])
# Instantiate a Geometry, register the root Universe, and export to XML
self.geometry.root_universe = root
def build_default_settings(self):
self.settings.batches = 10
self.settings.inactive = 5
self.settings.particles = 100
self.settings.source = Source(space=Box([-0.63, -0.63, -1],
[0.63, 0.63, 1],
only_fissionable=True))
def build_defualt_plots(self):
plot = openmc.Plot()
plot.filename = 'mat'
plot.origin = (0.0, 0.0, 0)
plot.width = (1.26, 1.26)
plot.pixels = (300, 300)
plot.color = 'mat'
self.plots.add_plot(plot)
class AssemblyInputSet(object):
def __init__(self):
self.settings = openmc.Settings()
self.materials = openmc.Materials()
self.geometry = openmc.Geometry()
self.tallies = None
self.plots = None
def export(self):
self.settings.export_to_xml()
self.materials.export_to_xml()
self.geometry.export_to_xml()
if self.tallies is not None:
self.tallies.export_to_xml()
if self.plots is not None:
self.plots.export_to_xml()
def build_default_materials_and_geometry(self):
# 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.
self.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
min_x = openmc.XPlane(x0=-10.71, boundary_type='reflective')
max_x = openmc.XPlane(x0=+10.71, boundary_type='reflective')
min_y = openmc.YPlane(y0=-10.71, boundary_type='reflective')
max_y = openmc.YPlane(y0=+10.71, boundary_type='reflective')
# Create a Universe to encapsulate a fuel pin
fuel_pin_universe = openmc.Universe(name='Fuel Pin')
# Create fuel Cell
fuel_cell = openmc.Cell(name='fuel')
fuel_cell.fill = fuel
fuel_cell.region = -fuel_or
fuel_pin_universe.add_cell(fuel_cell)
# Create a clad Cell
clad_cell = openmc.Cell(name='clad')
clad_cell.fill = clad
clad_cell.region = +fuel_or & -clad_or
fuel_pin_universe.add_cell(clad_cell)
# Create a moderator Cell
hot_water_cell = openmc.Cell(name='hot water')
hot_water_cell.fill = hot_water
hot_water_cell.region = +clad_or
fuel_pin_universe.add_cell(hot_water_cell)
# Create a Universe to encapsulate a control rod guide tube
guide_tube_universe = openmc.Universe(name='Guide Tube')
# Create guide tube inner Cell
gt_inner_cell = openmc.Cell(name='guide tube inner water')
gt_inner_cell.fill = hot_water
gt_inner_cell.region = -fuel_or
guide_tube_universe.add_cell(gt_inner_cell)
# Create a clad Cell
gt_clad_cell = openmc.Cell(name='guide tube clad')
gt_clad_cell.fill = clad
gt_clad_cell.region = +fuel_or & -clad_or
guide_tube_universe.add_cell(gt_clad_cell)
# Create a guide tube outer Cell
gt_outer_cell = openmc.Cell(name='guide tube outer water')
gt_outer_cell.fill = hot_water
gt_outer_cell.region = +clad_or
guide_tube_universe.add_cell(gt_outer_cell)
# Create fuel assembly Lattice
assembly = openmc.RectLattice(name='Fuel Assembly')
assembly.pitch = (1.26, 1.26)
assembly.lower_left = [-1.26 * 17. / 2.0] * 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])
# Initialize an empty 17x17 array of the lattice universes
universes = np.empty((17, 17), dtype=openmc.Universe)
# Fill the array with the fuel pin and guide tube universes
universes[:,:] = fuel_pin_universe
universes[template_x, template_y] = guide_tube_universe
# Store the array of universes in the lattice
assembly.universes = universes
# Create root Cell
root_cell = openmc.Cell(name='root cell')
root_cell.fill = assembly
# Add boundary planes
root_cell.region = +min_x & -max_x & +min_y & -max_y
# Create root Universe
root_universe = openmc.Universe(universe_id=0, name='root universe')
root_universe.add_cell(root_cell)
# Instantiate a Geometry, register the root Universe, and export to XML
self.geometry.root_universe = root_universe
def build_default_settings(self):
self.settings.batches = 10
self.settings.inactive = 5
self.settings.particles = 100
self.settings.source = Source(space=Box([-10.71, -10.71, -1],
[10.71, 10.71, 1],
only_fissionable=True))
def build_defualt_plots(self):
plot = openmc.Plot()
plot.filename = 'mat'
plot.origin = (0.0, 0.0, 0)
plot.width = (21.42, 21.42)
plot.pixels = (300, 300)
plot.color = 'mat'
self.plots.add_plot(plot)
class MGInputSet(InputSet):
def build_default_materials_and_geometry(self):
# Define materials needed for 1D/1G slab problem
uo2_data = openmc.Macroscopic('uo2_iso')
uo2 = openmc.Material(name='UO2', material_id=1)
uo2.set_density('macro', 1.0)
uo2.add_macroscopic(uo2_data)
clad_data = openmc.Macroscopic('clad_ang_mu')
clad = openmc.Material(name='Clad', material_id=2)
clad.set_density('macro', 1.0)
clad.add_macroscopic(clad_data)
water_data = openmc.Macroscopic('lwtr_iso_mu')
water = openmc.Material(name='LWTR', material_id=3)
water.set_density('macro', 1.0)
water.add_macroscopic(water_data)
# Define the materials file.
self.materials += (uo2, clad, water)
# Define surfaces.
# Assembly/Problem Boundary
left = openmc.XPlane(x0=0.0, surface_id=200,
boundary_type='reflective')
right = openmc.XPlane(x0=10.0, surface_id=201,
boundary_type='reflective')
bottom = openmc.YPlane(y0=0.0, surface_id=300,
boundary_type='reflective')
top = openmc.YPlane(y0=10.0, surface_id=301,
boundary_type='reflective')
down = openmc.ZPlane(z0=0.0, surface_id=0,
boundary_type='reflective')
fuel_clad_intfc = openmc.ZPlane(z0=2.0, surface_id=1)
clad_lwtr_intfc = openmc.ZPlane(z0=2.4, surface_id=2)
up = openmc.ZPlane(z0=5.0, surface_id=3,
boundary_type='reflective')
# Define cells
c1 = openmc.Cell(cell_id=1)
c1.region = +left & -right & +bottom & -top & +down & -fuel_clad_intfc
c1.fill = uo2
c2 = openmc.Cell(cell_id=2)
c2.region = +left & -right & +bottom & -top & +fuel_clad_intfc & -clad_lwtr_intfc
c2.fill = clad
c3 = openmc.Cell(cell_id=3)
c3.region = +left & -right & +bottom & -top & +clad_lwtr_intfc & -up
c3.fill = water
# Define root universe.
root = openmc.Universe(universe_id=0, name='root universe')
root.add_cells((c1, c2, c3))
# Assign root universe to geometry
self.geometry.root_universe = root
def build_default_settings(self):
self.settings.batches = 10
self.settings.inactive = 5
self.settings.particles = 100
self.settings.source = Source(space=Box([0.0, 0.0, 0.0],
[10.0, 10.0, 2.0]))
self.settings.energy_mode = "multi-group"
self.settings.cross_sections = "../1d_mgxs.xml"
def build_defualt_plots(self):
plot = openmc.Plot()
plot.filename = 'mat'
plot.origin = (5.0, 5.0, 2.5)
plot.width = (2.5, 2.5)
plot.basis = 'xz'
plot.pixels = (3000, 3000)
plot.color = 'mat'
self.plots.add_plot(plot)
Reference in a new issue View git blame Copy permalink