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https://github.com/openmc-dev/openmc.git
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Merge branch 'develop' into separate_filters
* develop: (91 commits) Update resonance scattering test result removed additional unnecessary modifications removed unnecessary modifications updated to only modify the _swap_filters method Check for elastic scattering with isotropic mu. changed == to is fixed issue in tallies.py in making sure static copy of other filter gets updated and updated tests fixed bug for misaligned energy and energyout filters When 1 temp is available, revert to nearest temp on all processes added other_old to _swap_filter method fixed tally alignment method in tallies.py Make sure get_pandas_dataframe() works with 1D mesh filter Fix bug with SurfaceFilter bin ordering Check for void materials in tracklength tallies Make sure source is in geometry before fiss. check Make parent class for filters with IDed objects Allow objects in addition to ids in Filters Cleaned up rxn_rate_tally property for consistent scattering matrices Simplified code for xs_tally property for consistent scattering matrices Update inputs for test_diff_tally ... Conflicts: openmc/filter.py src/output.F90
This commit is contained in:
amandalund
commit
375125c603
230 changed files with 16397 additions and 11457 deletions
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@ -1,798 +0,0 @@
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import numpy as np
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import openmc
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from openmc.source import Source
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from openmc.stats import Box
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class InputSet(object):
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def __init__(self):
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self.settings = openmc.Settings()
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self.materials = openmc.Materials()
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self.geometry = openmc.Geometry()
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self.tallies = None
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self.plots = None
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def export(self):
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self.settings.export_to_xml()
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self.materials.export_to_xml()
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self.geometry.export_to_xml()
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if self.tallies is not None:
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self.tallies.export_to_xml()
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if self.plots is not None:
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self.plots.export_to_xml()
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def build_default_materials_and_geometry(self):
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# Define materials.
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fuel = openmc.Material(name='Fuel', material_id=1)
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fuel.set_density('g/cm3', 10.062)
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fuel.add_nuclide("U234", 4.9476e-6)
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fuel.add_nuclide("U235", 4.8218e-4)
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fuel.add_nuclide("U238", 2.1504e-2)
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fuel.add_nuclide("Xe135", 1.0801e-8)
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fuel.add_nuclide("O16", 4.5737e-2)
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clad = openmc.Material(name='Cladding', material_id=2)
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clad.set_density('g/cm3', 5.77)
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clad.add_nuclide("Zr90", 0.5145)
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clad.add_nuclide("Zr91", 0.1122)
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clad.add_nuclide("Zr92", 0.1715)
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clad.add_nuclide("Zr94", 0.1738)
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clad.add_nuclide("Zr96", 0.0280)
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cold_water = openmc.Material(name='Cold borated water', material_id=3)
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cold_water.set_density('atom/b-cm', 0.07416)
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cold_water.add_nuclide("H1", 2.0)
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cold_water.add_nuclide("O16", 1.0)
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cold_water.add_nuclide("B10", 6.490e-4)
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cold_water.add_nuclide("B11", 2.689e-3)
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cold_water.add_s_alpha_beta('c_H_in_H2O')
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hot_water = openmc.Material(name='Hot borated water', material_id=4)
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hot_water.set_density('atom/b-cm', 0.06614)
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hot_water.add_nuclide("H1", 2.0)
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hot_water.add_nuclide("O16", 1.0)
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hot_water.add_nuclide("B10", 6.490e-4)
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hot_water.add_nuclide("B11", 2.689e-3)
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hot_water.add_s_alpha_beta('c_H_in_H2O')
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rpv_steel = openmc.Material(name='Reactor pressure vessel steel',
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material_id=5)
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rpv_steel.set_density('g/cm3', 7.9)
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rpv_steel.add_nuclide("Fe54", 0.05437098, 'wo')
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rpv_steel.add_nuclide("Fe56", 0.88500663, 'wo')
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rpv_steel.add_nuclide("Fe57", 0.0208008, 'wo')
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rpv_steel.add_nuclide("Fe58", 0.00282159, 'wo')
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rpv_steel.add_nuclide("Ni58", 0.0067198, 'wo')
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rpv_steel.add_nuclide("Ni60", 0.0026776, 'wo')
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rpv_steel.add_nuclide("Mn55", 0.01, 'wo')
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rpv_steel.add_nuclide("Cr52", 0.002092475, 'wo')
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rpv_steel.add_nuclide("C0", 0.0025, 'wo')
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rpv_steel.add_nuclide("Cu63", 0.0013696, 'wo')
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lower_rad_ref = openmc.Material(name='Lower radial reflector',
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material_id=6)
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lower_rad_ref.set_density('g/cm3', 4.32)
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lower_rad_ref.add_nuclide("H1", 0.0095661, 'wo')
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lower_rad_ref.add_nuclide("O16", 0.0759107, 'wo')
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lower_rad_ref.add_nuclide("B10", 3.08409e-5, 'wo')
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lower_rad_ref.add_nuclide("B11", 1.40499e-4, 'wo')
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lower_rad_ref.add_nuclide("Fe54", 0.035620772088, 'wo')
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lower_rad_ref.add_nuclide("Fe56", 0.579805982228, 'wo')
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lower_rad_ref.add_nuclide("Fe57", 0.01362750048, 'wo')
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lower_rad_ref.add_nuclide("Fe58", 0.001848545204, 'wo')
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lower_rad_ref.add_nuclide("Ni58", 0.055298376566, 'wo')
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lower_rad_ref.add_nuclide("Mn55", 0.0182870, 'wo')
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lower_rad_ref.add_nuclide("Cr52", 0.145407678031, 'wo')
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lower_rad_ref.add_s_alpha_beta('c_H_in_H2O')
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upper_rad_ref = openmc.Material(name='Upper radial reflector /'
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'Top plate region', material_id=7)
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upper_rad_ref.set_density('g/cm3', 4.28)
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upper_rad_ref.add_nuclide("H1", 0.0086117, 'wo')
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upper_rad_ref.add_nuclide("O16", 0.0683369, 'wo')
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upper_rad_ref.add_nuclide("B10", 2.77638e-5, 'wo')
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upper_rad_ref.add_nuclide("B11", 1.26481e-4, 'wo')
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upper_rad_ref.add_nuclide("Fe54", 0.035953677186, 'wo')
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upper_rad_ref.add_nuclide("Fe56", 0.585224740891, 'wo')
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upper_rad_ref.add_nuclide("Fe57", 0.01375486056, 'wo')
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upper_rad_ref.add_nuclide("Fe58", 0.001865821363, 'wo')
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upper_rad_ref.add_nuclide("Ni58", 0.055815129186, 'wo')
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upper_rad_ref.add_nuclide("Mn55", 0.0184579, 'wo')
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upper_rad_ref.add_nuclide("Cr52", 0.146766614995, 'wo')
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upper_rad_ref.add_s_alpha_beta('c_H_in_H2O')
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bot_plate = openmc.Material(name='Bottom plate region', material_id=8)
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bot_plate.set_density('g/cm3', 7.184)
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bot_plate.add_nuclide("H1", 0.0011505, 'wo')
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bot_plate.add_nuclide("O16", 0.0091296, 'wo')
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bot_plate.add_nuclide("B10", 3.70915e-6, 'wo')
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bot_plate.add_nuclide("B11", 1.68974e-5, 'wo')
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bot_plate.add_nuclide("Fe54", 0.03855611055, 'wo')
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bot_plate.add_nuclide("Fe56", 0.627585036425, 'wo')
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bot_plate.add_nuclide("Fe57", 0.014750478, 'wo')
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bot_plate.add_nuclide("Fe58", 0.002000875025, 'wo')
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bot_plate.add_nuclide("Ni58", 0.059855207342, 'wo')
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bot_plate.add_nuclide("Mn55", 0.0197940, 'wo')
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bot_plate.add_nuclide("Cr52", 0.157390026871, 'wo')
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bot_plate.add_s_alpha_beta('c_H_in_H2O')
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bot_nozzle = openmc.Material(name='Bottom nozzle region',
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material_id=9)
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bot_nozzle.set_density('g/cm3', 2.53)
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bot_nozzle.add_nuclide("H1", 0.0245014, 'wo')
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bot_nozzle.add_nuclide("O16", 0.1944274, 'wo')
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bot_nozzle.add_nuclide("B10", 7.89917e-5, 'wo')
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bot_nozzle.add_nuclide("B11", 3.59854e-4, 'wo')
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bot_nozzle.add_nuclide("Fe54", 0.030411411144, 'wo')
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bot_nozzle.add_nuclide("Fe56", 0.495012237964, 'wo')
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bot_nozzle.add_nuclide("Fe57", 0.01163454624, 'wo')
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bot_nozzle.add_nuclide("Fe58", 0.001578204652, 'wo')
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bot_nozzle.add_nuclide("Ni58", 0.047211231662, 'wo')
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bot_nozzle.add_nuclide("Mn55", 0.0156126, 'wo')
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bot_nozzle.add_nuclide("Cr52", 0.124142524198, 'wo')
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bot_nozzle.add_s_alpha_beta('c_H_in_H2O')
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top_nozzle = openmc.Material(name='Top nozzle region', material_id=10)
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top_nozzle.set_density('g/cm3', 1.746)
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top_nozzle.add_nuclide("H1", 0.0358870, 'wo')
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top_nozzle.add_nuclide("O16", 0.2847761, 'wo')
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top_nozzle.add_nuclide("B10", 1.15699e-4, 'wo')
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top_nozzle.add_nuclide("B11", 5.27075e-4, 'wo')
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top_nozzle.add_nuclide("Fe54", 0.02644016154, 'wo')
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top_nozzle.add_nuclide("Fe56", 0.43037146399, 'wo')
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top_nozzle.add_nuclide("Fe57", 0.0101152584, 'wo')
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top_nozzle.add_nuclide("Fe58", 0.00137211607, 'wo')
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top_nozzle.add_nuclide("Ni58", 0.04104621835, 'wo')
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top_nozzle.add_nuclide("Mn55", 0.0135739, 'wo')
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top_nozzle.add_nuclide("Cr52", 0.107931450781, 'wo')
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top_nozzle.add_s_alpha_beta('c_H_in_H2O')
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top_fa = openmc.Material(name='Top of fuel assemblies', material_id=11)
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top_fa.set_density('g/cm3', 3.044)
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top_fa.add_nuclide("H1", 0.0162913, 'wo')
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top_fa.add_nuclide("O16", 0.1292776, 'wo')
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top_fa.add_nuclide("B10", 5.25228e-5, 'wo')
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top_fa.add_nuclide("B11", 2.39272e-4, 'wo')
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top_fa.add_nuclide("Zr90", 0.43313403903, 'wo')
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top_fa.add_nuclide("Zr91", 0.09549277374, 'wo')
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top_fa.add_nuclide("Zr92", 0.14759527104, 'wo')
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top_fa.add_nuclide("Zr94", 0.15280552077, 'wo')
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top_fa.add_nuclide("Zr96", 0.02511169542, 'wo')
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top_fa.add_s_alpha_beta('c_H_in_H2O')
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bot_fa = openmc.Material(name='Bottom of fuel assemblies',
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material_id=12)
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bot_fa.set_density('g/cm3', 1.762)
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bot_fa.add_nuclide("H1", 0.0292856, 'wo')
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bot_fa.add_nuclide("O16", 0.2323919, 'wo')
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bot_fa.add_nuclide("B10", 9.44159e-5, 'wo')
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bot_fa.add_nuclide("B11", 4.30120e-4, 'wo')
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bot_fa.add_nuclide("Zr90", 0.3741373658, 'wo')
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bot_fa.add_nuclide("Zr91", 0.0824858164, 'wo')
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bot_fa.add_nuclide("Zr92", 0.1274914944, 'wo')
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bot_fa.add_nuclide("Zr94", 0.1319920622, 'wo')
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bot_fa.add_nuclide("Zr96", 0.0216912612, 'wo')
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bot_fa.add_s_alpha_beta('c_H_in_H2O')
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# Define the materials file.
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self.materials += (fuel, clad, cold_water, hot_water, rpv_steel,
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lower_rad_ref, upper_rad_ref, bot_plate,
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bot_nozzle, top_nozzle, top_fa, bot_fa)
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# Define surfaces.
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s1 = openmc.ZCylinder(R=0.41, surface_id=1)
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s2 = openmc.ZCylinder(R=0.475, surface_id=2)
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s3 = openmc.ZCylinder(R=0.56, surface_id=3)
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s4 = openmc.ZCylinder(R=0.62, surface_id=4)
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s5 = openmc.ZCylinder(R=187.6, surface_id=5)
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s6 = openmc.ZCylinder(R=209.0, surface_id=6)
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s7 = openmc.ZCylinder(R=229.0, surface_id=7)
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s8 = openmc.ZCylinder(R=249.0, surface_id=8)
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s8.boundary_type = 'vacuum'
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s31 = openmc.ZPlane(z0=-229.0, surface_id=31)
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s31.boundary_type = 'vacuum'
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s32 = openmc.ZPlane(z0=-199.0, surface_id=32)
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s33 = openmc.ZPlane(z0=-193.0, surface_id=33)
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s34 = openmc.ZPlane(z0=-183.0, surface_id=34)
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s35 = openmc.ZPlane(z0=0.0, surface_id=35)
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s36 = openmc.ZPlane(z0=183.0, surface_id=36)
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s37 = openmc.ZPlane(z0=203.0, surface_id=37)
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s38 = openmc.ZPlane(z0=215.0, surface_id=38)
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s39 = openmc.ZPlane(z0=223.0, surface_id=39)
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s39.boundary_type = 'vacuum'
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# Define pin cells.
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fuel_cold = openmc.Universe(name='Fuel pin, cladding, cold water',
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universe_id=1)
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c21 = openmc.Cell(cell_id=21)
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c21.region = -s1
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c21.fill = fuel
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c22 = openmc.Cell(cell_id=22)
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c22.region = +s1 & -s2
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c22.fill = clad
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c23 = openmc.Cell(cell_id=23)
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c23.region = +s2
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c23.fill = cold_water
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fuel_cold.add_cells((c21, c22, c23))
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tube_cold = openmc.Universe(name='Instrumentation guide tube, '
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'cold water', universe_id=2)
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c24 = openmc.Cell(cell_id=24)
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c24.region = -s3
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c24.fill = cold_water
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c25 = openmc.Cell(cell_id=25)
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c25.region = +s3 & -s4
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c25.fill = clad
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c26 = openmc.Cell(cell_id=26)
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c26.region = +s4
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c26.fill = cold_water
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tube_cold.add_cells((c24, c25, c26))
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fuel_hot = openmc.Universe(name='Fuel pin, cladding, hot water',
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universe_id=3)
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c27 = openmc.Cell(cell_id=27)
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c27.region = -s1
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c27.fill = fuel
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c28 = openmc.Cell(cell_id=28)
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c28.region = +s1 & -s2
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c28.fill = clad
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c29 = openmc.Cell(cell_id=29)
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c29.region = +s2
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c29.fill = hot_water
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fuel_hot.add_cells((c27, c28, c29))
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|
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tube_hot = openmc.Universe(name='Instrumentation guide tube, hot water',
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universe_id=4)
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c30 = openmc.Cell(cell_id=30)
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c30.region = -s3
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c30.fill = hot_water
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c31 = openmc.Cell(cell_id=31)
|
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c31.region = +s3 & -s4
|
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c31.fill = clad
|
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c32 = openmc.Cell(cell_id=32)
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c32.region = +s4
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c32.fill = hot_water
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tube_hot.add_cells((c30, c31, c32))
|
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|
||||
# Define fuel lattices.
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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_by = 'material'
|
||||
|
||||
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', boundary_type='reflective')
|
||||
right = openmc.XPlane(x0=0.63, name='right', boundary_type='reflective')
|
||||
bottom = openmc.YPlane(y0=-0.63, name='bottom',
|
||||
boundary_type='reflective')
|
||||
top = openmc.YPlane(y0=0.63, name='top', boundary_type='reflective')
|
||||
|
||||
# Instantiate Cells
|
||||
fuel_pin = openmc.Cell(name='cell 1', fill=fuel)
|
||||
cladding = openmc.Cell(name='cell 3', fill=clad)
|
||||
water = openmc.Cell(name='cell 2', 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
|
||||
|
||||
# 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_by = 'material'
|
||||
|
||||
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_by = 'material'
|
||||
|
||||
self.plots.add_plot(plot)
|
||||
|
||||
|
||||
class MGInputSet(InputSet):
|
||||
def build_default_materials_and_geometry(self, reps=None, as_macro=True):
|
||||
# Define materials needed for 1D/1G slab problem
|
||||
mat_names = ['uo2', 'clad', 'lwtr']
|
||||
mgxs_reps = ['ang', 'ang_mu', 'iso', 'iso_mu']
|
||||
|
||||
if reps is None:
|
||||
reps = mgxs_reps
|
||||
|
||||
xs = []
|
||||
mats = []
|
||||
i = 0
|
||||
for mat in mat_names:
|
||||
for rep in reps:
|
||||
i += 1
|
||||
if as_macro:
|
||||
xs.append(openmc.Macroscopic(mat + '_' + rep))
|
||||
mats.append(openmc.Material(name=str(i)))
|
||||
mats[-1].set_density('macro', 1.)
|
||||
mats[-1].add_macroscopic(xs[-1])
|
||||
else:
|
||||
xs.append(openmc.Nuclide(mat + '_' + rep))
|
||||
mats.append(openmc.Material(name=str(i)))
|
||||
mats[-1].set_density('atom/b-cm', 1.)
|
||||
mats[-1].add_nuclide(xs[-1].name, 1.0, 'ao')
|
||||
|
||||
# Define the materials file
|
||||
self.xs_data = xs
|
||||
self.materials += mats
|
||||
self.materials.cross_sections = "../1d_mgxs.h5"
|
||||
|
||||
# Define surfaces.
|
||||
# Assembly/Problem Boundary
|
||||
left = openmc.XPlane(x0=0.0, boundary_type='reflective')
|
||||
right = openmc.XPlane(x0=10.0, boundary_type='reflective')
|
||||
bottom = openmc.YPlane(y0=0.0, boundary_type='reflective')
|
||||
top = openmc.YPlane(y0=10.0, boundary_type='reflective')
|
||||
# for each material add a plane
|
||||
planes = [openmc.ZPlane(z0=0.0, boundary_type='reflective')]
|
||||
dz = round(5. / float(len(mats)), 4)
|
||||
for i in range(len(mats) - 1):
|
||||
planes.append(openmc.ZPlane(z0=dz * float(i + 1)))
|
||||
planes.append(openmc.ZPlane(z0=5.0, boundary_type='reflective'))
|
||||
|
||||
# Define cells for each material
|
||||
cells = []
|
||||
xy = +left & -right & +bottom & -top
|
||||
for i, mat in enumerate(mats):
|
||||
cells.append(openmc.Cell())
|
||||
cells[-1].region = xy & +planes[i] & -planes[i + 1]
|
||||
cells[-1].fill = mat
|
||||
|
||||
# Define root universe.
|
||||
root = openmc.Universe(universe_id=0, name='root universe')
|
||||
root.add_cells(cells)
|
||||
|
||||
# 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, 5.]))
|
||||
self.settings.energy_mode = "multi-group"
|
||||
|
||||
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_by = 'material'
|
||||
|
||||
self.plots.add_plot(plot)
|
||||
|
|
@ -184,8 +184,8 @@ class Test(object):
|
|||
build_str += "-Ddebug=ON "
|
||||
if self.optimize:
|
||||
build_str += "-Doptimize=ON "
|
||||
if self.openmp:
|
||||
build_str += "-Dopenmp=ON "
|
||||
if not self.openmp:
|
||||
build_str += "-Dopenmp=OFF "
|
||||
if self.coverage:
|
||||
build_str += "-Dcoverage=ON "
|
||||
self.build_opts = build_str
|
||||
|
|
|
|||
|
|
@ -56,7 +56,7 @@
|
|||
</geometry>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<materials>
|
||||
<material id="1" name="Fuel">
|
||||
<material id="1" name="UOX fuel">
|
||||
<density units="g/cm3" value="10.062" />
|
||||
<nuclide ao="4.9476e-06" name="U234" />
|
||||
<nuclide ao="0.00048218" name="U235" />
|
||||
|
|
@ -105,7 +105,7 @@
|
|||
<nuclide name="Zr96" wo="0.0216912612" />
|
||||
<sab name="c_H_in_H2O" />
|
||||
</material>
|
||||
<material id="2" name="Cladding">
|
||||
<material id="2" name="Zircaloy">
|
||||
<density units="g/cm3" value="5.77" />
|
||||
<nuclide ao="0.5145" name="Zr90" />
|
||||
<nuclide ao="0.1122" name="Zr91" />
|
||||
|
|
@ -157,7 +157,7 @@
|
|||
<nuclide name="Cr52" wo="0.145407678031" />
|
||||
<sab name="c_H_in_H2O" />
|
||||
</material>
|
||||
<material id="7" name="Upper radial reflector /Top plate region">
|
||||
<material id="7" name="Upper radial reflector / Top plate region">
|
||||
<density units="g/cm3" value="4.28" />
|
||||
<nuclide name="H1" wo="0.0086117" />
|
||||
<nuclide name="O16" wo="0.0683369" />
|
||||
|
|
|
|||
|
|
@ -10,15 +10,11 @@ import openmc
|
|||
|
||||
|
||||
class AsymmetricLatticeTestHarness(PyAPITestHarness):
|
||||
|
||||
def _build_inputs(self):
|
||||
"""Build an axis-asymmetric lattice of fuel assemblies"""
|
||||
|
||||
# Build full core geometry from underlying input set
|
||||
self._input_set.build_default_materials_and_geometry()
|
||||
def __init__(self, *args, **kwargs):
|
||||
super(AsymmetricLatticeTestHarness, self).__init__(*args, **kwargs)
|
||||
|
||||
# Extract universes encapsulating fuel and water assemblies
|
||||
geometry = self._input_set.geometry
|
||||
geometry = self._model.geometry
|
||||
water = geometry.get_universes_by_name('water assembly (hot)')[0]
|
||||
fuel = geometry.get_universes_by_name('fuel assembly (hot)')[0]
|
||||
|
||||
|
|
@ -46,7 +42,7 @@ class AsymmetricLatticeTestHarness(PyAPITestHarness):
|
|||
root_univ.add_cell(root_cell)
|
||||
|
||||
# Over-ride geometry in the input set with this 3x3 lattice
|
||||
self._input_set.geometry.root_universe = root_univ
|
||||
self._model.geometry.root_universe = root_univ
|
||||
|
||||
# Initialize a "distribcell" filter for the fuel pin cell
|
||||
distrib_filter = openmc.DistribcellFilter(27)
|
||||
|
|
@ -56,22 +52,12 @@ class AsymmetricLatticeTestHarness(PyAPITestHarness):
|
|||
tally.filters.append(distrib_filter)
|
||||
tally.scores.append('nu-fission')
|
||||
|
||||
# Initialize the tallies file
|
||||
tallies_file = openmc.Tallies([tally])
|
||||
|
||||
# Assign the tallies file to the input set
|
||||
self._input_set.tallies = tallies_file
|
||||
|
||||
# Build default settings
|
||||
self._input_set.build_default_settings()
|
||||
self._model.tallies.append(tally)
|
||||
|
||||
# Specify summary output and correct source sampling box
|
||||
source = openmc.Source(space=openmc.stats.Box([-32, -32, 0], [32, 32, 32]))
|
||||
source.space.only_fissionable = True
|
||||
self._input_set.settings.source = source
|
||||
|
||||
# Write input XML files
|
||||
self._input_set.export()
|
||||
self._model.settings.source = openmc.Source(space=openmc.stats.Box(
|
||||
[-32, -32, 0], [32, 32, 32], only_fissionable = True))
|
||||
|
||||
def _get_results(self, hash_output=True):
|
||||
"""Digest info in statepoint and summary and return as a string."""
|
||||
|
|
@ -105,5 +91,5 @@ class AsymmetricLatticeTestHarness(PyAPITestHarness):
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = AsymmetricLatticeTestHarness('statepoint.10.h5', True)
|
||||
harness = AsymmetricLatticeTestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import CMFDTestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = CMFDTestHarness('statepoint.20.*', True)
|
||||
harness = CMFDTestHarness('statepoint.20.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import CMFDTestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = CMFDTestHarness('statepoint.20.*', True)
|
||||
harness = CMFDTestHarness('statepoint.20.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -6,5 +6,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*', True)
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*', True)
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -70,5 +70,5 @@ class CreateFissionNeutronsTestHarness(PyAPITestHarness):
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = CreateFissionNeutronsTestHarness('statepoint.10.h5', True)
|
||||
harness = CreateFissionNeutronsTestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*')
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -148,7 +148,7 @@
|
|||
</geometry>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<materials>
|
||||
<material id="1" name="Fuel">
|
||||
<material id="1" name="UOX fuel">
|
||||
<density units="g/cm3" value="10.062" />
|
||||
<nuclide ao="4.9476e-06" name="U234" />
|
||||
<nuclide ao="0.00048218" name="U235" />
|
||||
|
|
@ -197,7 +197,7 @@
|
|||
<nuclide name="Zr96" wo="0.0216912612" />
|
||||
<sab name="c_H_in_H2O" />
|
||||
</material>
|
||||
<material id="2" name="Cladding">
|
||||
<material id="2" name="Zircaloy">
|
||||
<density units="g/cm3" value="5.77" />
|
||||
<nuclide ao="0.5145" name="Zr90" />
|
||||
<nuclide ao="0.1122" name="Zr91" />
|
||||
|
|
@ -249,7 +249,7 @@
|
|||
<nuclide name="Cr52" wo="0.145407678031" />
|
||||
<sab name="c_H_in_H2O" />
|
||||
</material>
|
||||
<material id="7" name="Upper radial reflector /Top plate region">
|
||||
<material id="7" name="Upper radial reflector / Top plate region">
|
||||
<density units="g/cm3" value="4.28" />
|
||||
<nuclide name="H1" wo="0.0086117" />
|
||||
<nuclide name="O16" wo="0.0683369" />
|
||||
|
|
@ -306,7 +306,7 @@
|
|||
<parameters>-160 -160 -183 160 160 183</parameters>
|
||||
</space>
|
||||
</source>
|
||||
<temperature_multipole>True</temperature_multipole>
|
||||
<temperature_multipole>true</temperature_multipole>
|
||||
</settings>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<tallies>
|
||||
|
|
|
|||
|
|
@ -11,19 +11,16 @@ from testing_harness import PyAPITestHarness
|
|||
import openmc
|
||||
|
||||
class DiffTallyTestHarness(PyAPITestHarness):
|
||||
def _build_inputs(self):
|
||||
# Build default materials/geometry
|
||||
self._input_set.build_default_materials_and_geometry()
|
||||
def __init__(self, *args, **kwargs):
|
||||
super(DiffTallyTestHarness, self).__init__(*args, **kwargs)
|
||||
|
||||
# Set settings explicitly
|
||||
self._input_set.settings.batches = 3
|
||||
self._input_set.settings.inactive = 0
|
||||
self._input_set.settings.particles = 100
|
||||
self._input_set.settings.source = openmc.Source(space=openmc.stats.Box(
|
||||
self._model.settings.batches = 3
|
||||
self._model.settings.inactive = 0
|
||||
self._model.settings.particles = 100
|
||||
self._model.settings.source = openmc.Source(space=openmc.stats.Box(
|
||||
[-160, -160, -183], [160, 160, 183]))
|
||||
self._input_set.settings.temperature['multipole'] = True
|
||||
|
||||
self._input_set.tallies = openmc.Tallies()
|
||||
self._model.settings.temperature['multipole'] = True
|
||||
|
||||
filt_mats = openmc.MaterialFilter((1, 3))
|
||||
filt_eout = openmc.EnergyoutFilter((0.0, 0.625, 20.0e6))
|
||||
|
|
@ -64,7 +61,7 @@ class DiffTallyTestHarness(PyAPITestHarness):
|
|||
t.add_score('flux')
|
||||
t.add_filter(filt_mats)
|
||||
t.derivative = derivs[i]
|
||||
self._input_set.tallies.append(t)
|
||||
self._model.tallies.append(t)
|
||||
|
||||
# Cover supported scores with a collision estimator.
|
||||
for i in range(5):
|
||||
|
|
@ -78,7 +75,7 @@ class DiffTallyTestHarness(PyAPITestHarness):
|
|||
t.add_nuclide('total')
|
||||
t.add_nuclide('U235')
|
||||
t.derivative = derivs[i]
|
||||
self._input_set.tallies.append(t)
|
||||
self._model.tallies.append(t)
|
||||
|
||||
# Cover an analog estimator.
|
||||
for i in range(5):
|
||||
|
|
@ -87,7 +84,7 @@ class DiffTallyTestHarness(PyAPITestHarness):
|
|||
t.add_filter(filt_mats)
|
||||
t.estimator = 'analog'
|
||||
t.derivative = derivs[i]
|
||||
self._input_set.tallies.append(t)
|
||||
self._model.tallies.append(t)
|
||||
|
||||
# Energyout filter and total nuclide for the density derivatives.
|
||||
for i in range(2):
|
||||
|
|
@ -99,7 +96,7 @@ class DiffTallyTestHarness(PyAPITestHarness):
|
|||
t.add_nuclide('total')
|
||||
t.add_nuclide('U235')
|
||||
t.derivative = derivs[i]
|
||||
self._input_set.tallies.append(t)
|
||||
self._model.tallies.append(t)
|
||||
|
||||
# Energyout filter without total nuclide for other derivatives.
|
||||
for i in range(2, 5):
|
||||
|
|
@ -110,9 +107,7 @@ class DiffTallyTestHarness(PyAPITestHarness):
|
|||
t.add_filter(filt_eout)
|
||||
t.add_nuclide('U235')
|
||||
t.derivative = derivs[i]
|
||||
self._input_set.tallies.append(t)
|
||||
|
||||
self._input_set.export()
|
||||
self._model.tallies.append(t)
|
||||
|
||||
def _get_results(self):
|
||||
# Read the statepoint and summary files.
|
||||
|
|
@ -131,5 +126,5 @@ class DiffTallyTestHarness(PyAPITestHarness):
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = DiffTallyTestHarness('statepoint.3.h5', True)
|
||||
harness = DiffTallyTestHarness('statepoint.3.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -46,9 +46,6 @@
|
|||
<parameters>-1 -1 -1 1 1 1</parameters>
|
||||
</space>
|
||||
</source>
|
||||
<output>
|
||||
<summary>true</summary>
|
||||
</output>
|
||||
</settings>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<plots>
|
||||
|
|
|
|||
|
|
@ -5,8 +5,6 @@ import sys
|
|||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import TestHarness, PyAPITestHarness
|
||||
import openmc
|
||||
from openmc.stats import Box
|
||||
from openmc.source import Source
|
||||
|
||||
|
||||
class DistribmatTestHarness(PyAPITestHarness):
|
||||
|
|
@ -31,25 +29,18 @@ class DistribmatTestHarness(PyAPITestHarness):
|
|||
mats_file = openmc.Materials([moderator, dense_fuel, light_fuel])
|
||||
mats_file.export_to_xml()
|
||||
|
||||
|
||||
####################
|
||||
# Geometry
|
||||
####################
|
||||
|
||||
c1 = openmc.Cell(cell_id=1)
|
||||
c1.fill = moderator
|
||||
mod_univ = openmc.Universe(universe_id=1)
|
||||
mod_univ.add_cell(c1)
|
||||
c1 = openmc.Cell(cell_id=1, fill=moderator)
|
||||
mod_univ = openmc.Universe(universe_id=1, cells=[c1])
|
||||
|
||||
r0 = openmc.ZCylinder(R=0.3)
|
||||
c11 = openmc.Cell(cell_id=11)
|
||||
c11.region = -r0
|
||||
c11 = openmc.Cell(cell_id=11, region=-r0)
|
||||
c11.fill = [dense_fuel, light_fuel, None, dense_fuel]
|
||||
c12 = openmc.Cell(cell_id=12)
|
||||
c12.region = +r0
|
||||
c12.fill = moderator
|
||||
fuel_univ = openmc.Universe(universe_id=11)
|
||||
fuel_univ.add_cells((c11, c12))
|
||||
c12 = openmc.Cell(cell_id=12, region=+r0, fill=moderator)
|
||||
fuel_univ = openmc.Universe(universe_id=11, cells=[c11, c12])
|
||||
|
||||
lat = openmc.RectLattice(lattice_id=101)
|
||||
lat.lower_left = [-2.0, -2.0]
|
||||
|
|
@ -63,17 +54,13 @@ class DistribmatTestHarness(PyAPITestHarness):
|
|||
y1 = openmc.YPlane(y0=3.0)
|
||||
for s in [x0, x1, y0, y1]:
|
||||
s.boundary_type = 'reflective'
|
||||
c101 = openmc.Cell(cell_id=101)
|
||||
c101 = openmc.Cell(cell_id=101, fill=lat)
|
||||
c101.region = +x0 & -x1 & +y0 & -y1
|
||||
c101.fill = lat
|
||||
root_univ = openmc.Universe(universe_id=0)
|
||||
root_univ.add_cell(c101)
|
||||
root_univ = openmc.Universe(universe_id=0, cells=[c101])
|
||||
|
||||
geometry = openmc.Geometry()
|
||||
geometry.root_universe = root_univ
|
||||
geometry = openmc.Geometry(root_univ)
|
||||
geometry.export_to_xml()
|
||||
|
||||
|
||||
####################
|
||||
# Settings
|
||||
####################
|
||||
|
|
@ -82,36 +69,32 @@ class DistribmatTestHarness(PyAPITestHarness):
|
|||
sets_file.batches = 5
|
||||
sets_file.inactive = 0
|
||||
sets_file.particles = 1000
|
||||
sets_file.source = Source(space=Box([-1, -1, -1], [1, 1, 1]))
|
||||
sets_file.output = {'summary': True}
|
||||
sets_file.source = openmc.Source(space=openmc.stats.Box(
|
||||
[-1, -1, -1], [1, 1, 1]))
|
||||
sets_file.export_to_xml()
|
||||
|
||||
|
||||
####################
|
||||
# Plots
|
||||
####################
|
||||
|
||||
plots_file = openmc.Plots()
|
||||
plot1 = openmc.Plot(plot_id=1)
|
||||
plot1.basis = 'xy'
|
||||
plot1.color_by = 'cell'
|
||||
plot1.filename = 'cellplot'
|
||||
plot1.origin = (0, 0, 0)
|
||||
plot1.width = (7, 7)
|
||||
plot1.pixels = (400, 400)
|
||||
|
||||
plot = openmc.Plot(plot_id=1)
|
||||
plot.basis = 'xy'
|
||||
plot.color_by = 'cell'
|
||||
plot.filename = 'cellplot'
|
||||
plot.origin = (0, 0, 0)
|
||||
plot.width = (7, 7)
|
||||
plot.pixels = (400, 400)
|
||||
plots_file.add_plot(plot)
|
||||
plot2 = openmc.Plot(plot_id=2)
|
||||
plot2.basis = 'xy'
|
||||
plot2.color_by = 'material'
|
||||
plot2.filename = 'matplot'
|
||||
plot2.origin = (0, 0, 0)
|
||||
plot2.width = (7, 7)
|
||||
plot2.pixels = (400, 400)
|
||||
|
||||
plot = openmc.Plot(plot_id=2)
|
||||
plot.basis = 'xy'
|
||||
plot.color_by = 'material'
|
||||
plot.filename = 'matplot'
|
||||
plot.origin = (0, 0, 0)
|
||||
plot.width = (7, 7)
|
||||
plot.pixels = (400, 400)
|
||||
plots_file.add_plot(plot)
|
||||
|
||||
plots_file.export_to_xml()
|
||||
plots = openmc.Plots([plot1, plot2])
|
||||
plots.export_to_xml()
|
||||
|
||||
def _get_results(self):
|
||||
outstr = super(DistribmatTestHarness, self)._get_results()
|
||||
|
|
@ -119,12 +102,6 @@ class DistribmatTestHarness(PyAPITestHarness):
|
|||
outstr += str(su.geometry.get_all_cells()[11])
|
||||
return outstr
|
||||
|
||||
def _cleanup(self):
|
||||
f = os.path.join(os.getcwd(), 'plots.xml')
|
||||
if os.path.exists(f):
|
||||
os.remove(f)
|
||||
super(DistribmatTestHarness, self)._cleanup()
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = DistribmatTestHarness('statepoint.5.h5')
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.7.*')
|
||||
harness = TestHarness('statepoint.7.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*')
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -74,5 +74,5 @@ class EnergyCutoffTestHarness(PyAPITestHarness):
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = EnergyCutoffTestHarness('statepoint.10.h5', True)
|
||||
harness = EnergyCutoffTestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*')
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -26,5 +26,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*')
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -5,7 +5,7 @@ import os
|
|||
import sys
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import TestHarness
|
||||
from openmc.statepoint import StatePoint
|
||||
from openmc import StatePoint
|
||||
|
||||
|
||||
class EntropyTestHarness(TestHarness):
|
||||
|
|
@ -13,21 +13,19 @@ class EntropyTestHarness(TestHarness):
|
|||
"""Digest info in the statepoint and return as a string."""
|
||||
# Read the statepoint file.
|
||||
statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0]
|
||||
sp = StatePoint(statepoint)
|
||||
with StatePoint(statepoint) as sp:
|
||||
# Write out k-combined.
|
||||
outstr = 'k-combined:\n'
|
||||
outstr += '{0:12.6E} {1:12.6E}\n'.format(*sp.k_combined)
|
||||
|
||||
# Write out k-combined.
|
||||
outstr = 'k-combined:\n'
|
||||
form = '{0:12.6E} {1:12.6E}\n'
|
||||
outstr += form.format(sp.k_combined[0], sp.k_combined[1])
|
||||
|
||||
# Write out entropy data.
|
||||
outstr += 'entropy:\n'
|
||||
results = ['{0:12.6E}'.format(x) for x in sp.entropy]
|
||||
outstr += '\n'.join(results) + '\n'
|
||||
# Write out entropy data.
|
||||
outstr += 'entropy:\n'
|
||||
results = ['{0:12.6E}'.format(x) for x in sp.entropy]
|
||||
outstr += '\n'.join(results) + '\n'
|
||||
|
||||
return outstr
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = EntropyTestHarness('statepoint.10.*')
|
||||
harness = EntropyTestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -10,7 +10,7 @@ from testing_harness import *
|
|||
|
||||
class DistribcellTestHarness(TestHarness):
|
||||
def __init__(self):
|
||||
super(DistribcellTestHarness, self).__init__(None, True)
|
||||
super(DistribcellTestHarness, self).__init__(None)
|
||||
|
||||
def execute_test(self):
|
||||
"""Run OpenMC with the appropriate arguments and check the outputs."""
|
||||
|
|
@ -41,8 +41,8 @@ class DistribcellTestHarness(TestHarness):
|
|||
base_dir = os.getcwd()
|
||||
try:
|
||||
dirs = ('case-1', '../case-2', '../case-3', '../case-4')
|
||||
sps = ('statepoint.1.*', 'statepoint.1.*', 'statepoint.3.*',
|
||||
'statepoint.1.*')
|
||||
sps = ('statepoint.1.h5', 'statepoint.1.h5', 'statepoint.3.h5',
|
||||
'statepoint.1.h5')
|
||||
tallies_out_present = (True, True, False, True)
|
||||
hash_out = (False, False, True, False)
|
||||
for i in range(len(dirs)):
|
||||
|
|
|
|||
|
|
@ -148,7 +148,7 @@
|
|||
</geometry>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<materials>
|
||||
<material id="1" name="Fuel">
|
||||
<material id="1" name="UOX fuel">
|
||||
<density units="g/cm3" value="10.062" />
|
||||
<nuclide ao="4.9476e-06" name="U234" />
|
||||
<nuclide ao="0.00048218" name="U235" />
|
||||
|
|
@ -197,7 +197,7 @@
|
|||
<nuclide name="Zr96" wo="0.0216912612" />
|
||||
<sab name="c_H_in_H2O" />
|
||||
</material>
|
||||
<material id="2" name="Cladding">
|
||||
<material id="2" name="Zircaloy">
|
||||
<density units="g/cm3" value="5.77" />
|
||||
<nuclide ao="0.5145" name="Zr90" />
|
||||
<nuclide ao="0.1122" name="Zr91" />
|
||||
|
|
@ -250,7 +250,7 @@
|
|||
<nuclide name="Cr52" wo="0.145407678031" />
|
||||
<sab name="c_H_in_H2O" />
|
||||
</material>
|
||||
<material id="7" name="Upper radial reflector /Top plate region">
|
||||
<material id="7" name="Upper radial reflector / Top plate region">
|
||||
<density units="g/cm3" value="4.28" />
|
||||
<nuclide name="H1" wo="0.0086117" />
|
||||
<nuclide name="O16" wo="0.0683369" />
|
||||
|
|
|
|||
|
|
@ -3,20 +3,17 @@
|
|||
import os
|
||||
import sys
|
||||
import glob
|
||||
import hashlib
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import PyAPITestHarness
|
||||
import openmc
|
||||
|
||||
|
||||
class FilterEnergyFunHarness(PyAPITestHarness):
|
||||
def _build_inputs(self):
|
||||
# Build the default material, geometry, settings inputs.
|
||||
self._input_set.build_default_materials_and_geometry()
|
||||
self._input_set.build_default_settings()
|
||||
def __init__(self, *args, **kwargs):
|
||||
super(FilterEnergyFunHarness, self).__init__(*args, **kwargs)
|
||||
|
||||
# Add Am241 to the fuel.
|
||||
self._input_set.materials[1].add_nuclide('Am241', 1e-7)
|
||||
self._model.materials[1].add_nuclide('Am241', 1e-7)
|
||||
|
||||
# Define Am242m / Am242 branching ratio from ENDF/B-VII.1 data.
|
||||
x = [1e-5, 3.69e-1, 1e3, 1e5, 6e5, 1e6, 2e6, 4e6, 3e7]
|
||||
|
|
@ -37,10 +34,7 @@ class FilterEnergyFunHarness(PyAPITestHarness):
|
|||
t.scores = ['(n,gamma)']
|
||||
t.nuclides = ['Am241']
|
||||
tallies[1].filters = [filt1]
|
||||
self._input_set.tallies = openmc.Tallies(tallies)
|
||||
|
||||
# Export inputs to xml.
|
||||
self._input_set.export()
|
||||
self._model.tallies = tallies
|
||||
|
||||
def _get_results(self):
|
||||
# Read the statepoint file.
|
||||
|
|
@ -55,5 +49,5 @@ class FilterEnergyFunHarness(PyAPITestHarness):
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = FilterEnergyFunHarness('statepoint.10.h5', True)
|
||||
harness = FilterEnergyFunHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -148,7 +148,7 @@
|
|||
</geometry>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<materials>
|
||||
<material id="1" name="Fuel">
|
||||
<material id="1" name="UOX fuel">
|
||||
<density units="g/cm3" value="10.062" />
|
||||
<nuclide ao="4.9476e-06" name="U234" />
|
||||
<nuclide ao="0.00048218" name="U235" />
|
||||
|
|
@ -197,7 +197,7 @@
|
|||
<nuclide name="Zr96" wo="0.0216912612" />
|
||||
<sab name="c_H_in_H2O" />
|
||||
</material>
|
||||
<material id="2" name="Cladding">
|
||||
<material id="2" name="Zircaloy">
|
||||
<density units="g/cm3" value="5.77" />
|
||||
<nuclide ao="0.5145" name="Zr90" />
|
||||
<nuclide ao="0.1122" name="Zr91" />
|
||||
|
|
@ -249,7 +249,7 @@
|
|||
<nuclide name="Cr52" wo="0.145407678031" />
|
||||
<sab name="c_H_in_H2O" />
|
||||
</material>
|
||||
<material id="7" name="Upper radial reflector /Top plate region">
|
||||
<material id="7" name="Upper radial reflector / Top plate region">
|
||||
<density units="g/cm3" value="4.28" />
|
||||
<nuclide name="H1" wo="0.0086117" />
|
||||
<nuclide name="O16" wo="0.0683369" />
|
||||
|
|
@ -306,9 +306,6 @@
|
|||
<parameters>-160 -160 -183 160 160 183</parameters>
|
||||
</space>
|
||||
</source>
|
||||
<output>
|
||||
<summary>true</summary>
|
||||
</output>
|
||||
</settings>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<tallies>
|
||||
|
|
|
|||
|
|
@ -2,21 +2,14 @@
|
|||
|
||||
import os
|
||||
import sys
|
||||
import glob
|
||||
import hashlib
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import HashedPyAPITestHarness
|
||||
import openmc
|
||||
|
||||
|
||||
class FilterMeshTestHarness(HashedPyAPITestHarness):
|
||||
def _build_inputs(self):
|
||||
|
||||
# The summary.h5 file needs to be created to read in the tallies
|
||||
self._input_set.settings.output = {'summary': True}
|
||||
|
||||
# Initialize the tallies file
|
||||
tallies_file = openmc.Tallies()
|
||||
def __init__(self, *args, **kwargs):
|
||||
super(FilterMeshTestHarness, self).__init__(*args, **kwargs)
|
||||
|
||||
# Initialize Meshes
|
||||
mesh_1d = openmc.Mesh(mesh_id=1)
|
||||
|
|
@ -38,46 +31,42 @@ class FilterMeshTestHarness(HashedPyAPITestHarness):
|
|||
mesh_3d.upper_right = [182.07, 182.07, 183.00]
|
||||
|
||||
# Initialize the filters
|
||||
mesh_1d_filter = openmc.MeshFilter(mesh_1d)
|
||||
mesh_2d_filter = openmc.MeshFilter(mesh_2d)
|
||||
mesh_3d_filter = openmc.MeshFilter(mesh_3d)
|
||||
mesh_1d_filter = openmc.MeshFilter(mesh_1d)
|
||||
mesh_2d_filter = openmc.MeshFilter(mesh_2d)
|
||||
mesh_3d_filter = openmc.MeshFilter(mesh_3d)
|
||||
|
||||
# Initialized the tallies
|
||||
tally = openmc.Tally(name='tally 1')
|
||||
tally.filters = [mesh_1d_filter]
|
||||
tally.scores = ['total']
|
||||
tallies_file.append(tally)
|
||||
self._model.tallies.append(tally)
|
||||
|
||||
tally = openmc.Tally(name='tally 2')
|
||||
tally.filters = [mesh_1d_filter]
|
||||
tally.scores = ['current']
|
||||
tallies_file.append(tally)
|
||||
self._model.tallies.append(tally)
|
||||
|
||||
tally = openmc.Tally(name='tally 3')
|
||||
tally.filters = [mesh_2d_filter]
|
||||
tally.scores = ['total']
|
||||
tallies_file.append(tally)
|
||||
self._model.tallies.append(tally)
|
||||
|
||||
tally = openmc.Tally(name='tally 4')
|
||||
tally.filters = [mesh_2d_filter]
|
||||
tally.scores = ['current']
|
||||
tallies_file.append(tally)
|
||||
self._model.tallies.append(tally)
|
||||
|
||||
tally = openmc.Tally(name='tally 5')
|
||||
tally.filters = [mesh_3d_filter]
|
||||
tally.scores = ['total']
|
||||
tallies_file.append(tally)
|
||||
self._model.tallies.append(tally)
|
||||
|
||||
tally = openmc.Tally(name='tally 6')
|
||||
tally.filters = [mesh_3d_filter]
|
||||
tally.scores = ['current']
|
||||
tallies_file.append(tally)
|
||||
|
||||
# Export tallies to file
|
||||
self._input_set.tallies = tallies_file
|
||||
super(FilterMeshTestHarness, self)._build_inputs()
|
||||
self._model.tallies.append(tally)
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = FilterMeshTestHarness('statepoint.10.h5', True)
|
||||
harness = FilterMeshTestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -6,7 +6,7 @@ import sys
|
|||
import numpy as np
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import TestHarness
|
||||
from openmc.statepoint import StatePoint
|
||||
from openmc import StatePoint
|
||||
|
||||
|
||||
class FixedSourceTestHarness(TestHarness):
|
||||
|
|
@ -14,31 +14,27 @@ class FixedSourceTestHarness(TestHarness):
|
|||
"""Digest info in the statepoint and return as a string."""
|
||||
# Read the statepoint file.
|
||||
statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0]
|
||||
sp = StatePoint(statepoint)
|
||||
|
||||
# Write out tally data.
|
||||
outstr = ''
|
||||
if self._tallies:
|
||||
tally_num = 1
|
||||
for tally_ind in sp.tallies:
|
||||
with StatePoint(statepoint) as sp:
|
||||
# Write out tally data.
|
||||
for i, tally_ind in enumerate(sp.tallies):
|
||||
tally = sp.tallies[tally_ind]
|
||||
results = np.zeros((tally.sum.size*2, ))
|
||||
results[0::2] = tally.sum.ravel()
|
||||
results[1::2] = tally.sum_sq.ravel()
|
||||
results = ['{0:12.6E}'.format(x) for x in results]
|
||||
|
||||
outstr += 'tally ' + str(tally_num) + ':\n'
|
||||
outstr += 'tally ' + str(i + 1) + ':\n'
|
||||
outstr += '\n'.join(results) + '\n'
|
||||
tally_num += 1
|
||||
|
||||
gt = sp.global_tallies
|
||||
outstr += 'leakage:\n'
|
||||
outstr += '{0:12.6E}'.format(gt[gt['name'] == b'leakage'][0]['sum']) + '\n'
|
||||
outstr += '{0:12.6E}'.format(gt[gt['name'] == b'leakage'][0]['sum_sq']) + '\n'
|
||||
gt = sp.global_tallies
|
||||
outstr += 'leakage:\n'
|
||||
outstr += '{0:12.6E}'.format(gt[gt['name'] == b'leakage'][0]['sum']) + '\n'
|
||||
outstr += '{0:12.6E}'.format(gt[gt['name'] == b'leakage'][0]['sum_sq']) + '\n'
|
||||
|
||||
return outstr
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = FixedSourceTestHarness('statepoint.10.*', True)
|
||||
harness = FixedSourceTestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*')
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -148,7 +148,7 @@
|
|||
</geometry>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<materials>
|
||||
<material id="1" name="Fuel">
|
||||
<material id="1" name="UOX fuel">
|
||||
<density units="g/cm3" value="10.062" />
|
||||
<nuclide ao="4.9476e-06" name="U234" scattering="iso-in-lab" />
|
||||
<nuclide ao="0.00048218" name="U235" scattering="iso-in-lab" />
|
||||
|
|
@ -197,7 +197,7 @@
|
|||
<nuclide name="Zr96" scattering="iso-in-lab" wo="0.0216912612" />
|
||||
<sab name="c_H_in_H2O" />
|
||||
</material>
|
||||
<material id="2" name="Cladding">
|
||||
<material id="2" name="Zircaloy">
|
||||
<density units="g/cm3" value="5.77" />
|
||||
<nuclide ao="0.5145" name="Zr90" scattering="iso-in-lab" />
|
||||
<nuclide ao="0.1122" name="Zr91" scattering="iso-in-lab" />
|
||||
|
|
@ -249,7 +249,7 @@
|
|||
<nuclide name="Cr52" scattering="iso-in-lab" wo="0.145407678031" />
|
||||
<sab name="c_H_in_H2O" />
|
||||
</material>
|
||||
<material id="7" name="Upper radial reflector /Top plate region">
|
||||
<material id="7" name="Upper radial reflector / Top plate region">
|
||||
<density units="g/cm3" value="4.28" />
|
||||
<nuclide name="H1" scattering="iso-in-lab" wo="0.0086117" />
|
||||
<nuclide name="O16" scattering="iso-in-lab" wo="0.0683369" />
|
||||
|
|
|
|||
|
|
@ -2,25 +2,12 @@
|
|||
|
||||
import os
|
||||
import sys
|
||||
import glob
|
||||
import hashlib
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import PyAPITestHarness
|
||||
import openmc
|
||||
import openmc.mgxs
|
||||
|
||||
|
||||
class IsoInLabTestHarness(PyAPITestHarness):
|
||||
|
||||
def _build_inputs(self):
|
||||
"""Write input XML files with iso-in-lab scattering."""
|
||||
|
||||
self._input_set.build_default_materials_and_geometry()
|
||||
self._input_set.build_default_settings()
|
||||
self._input_set.materials.make_isotropic_in_lab()
|
||||
self._input_set.export()
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = IsoInLabTestHarness('statepoint.10.*')
|
||||
# Force iso-in-lab scattering.
|
||||
harness = PyAPITestHarness('statepoint.10.h5')
|
||||
harness._model.materials.make_isotropic_in_lab()
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*')
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*')
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*')
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*')
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -1,17 +1,17 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<geometry>
|
||||
<cell id="10000" material="10000" region="10000 -10001 10002 -10003 10004 -10005" universe="0" />
|
||||
<cell id="10001" material="10001" region="10000 -10001 10002 -10003 10005 -10006" universe="0" />
|
||||
<cell id="10002" material="10002" region="10000 -10001 10002 -10003 10006 -10007" universe="0" />
|
||||
<cell id="10003" material="10003" region="10000 -10001 10002 -10003 10007 -10008" universe="0" />
|
||||
<cell id="10004" material="10004" region="10000 -10001 10002 -10003 10008 -10009" universe="0" />
|
||||
<cell id="10005" material="10005" region="10000 -10001 10002 -10003 10009 -10010" universe="0" />
|
||||
<cell id="10006" material="10006" region="10000 -10001 10002 -10003 10010 -10011" universe="0" />
|
||||
<cell id="10007" material="10007" region="10000 -10001 10002 -10003 10011 -10012" universe="0" />
|
||||
<cell id="10008" material="10008" region="10000 -10001 10002 -10003 10012 -10013" universe="0" />
|
||||
<cell id="10009" material="10009" region="10000 -10001 10002 -10003 10013 -10014" universe="0" />
|
||||
<cell id="10010" material="10010" region="10000 -10001 10002 -10003 10014 -10015" universe="0" />
|
||||
<cell id="10011" material="10011" region="10000 -10001 10002 -10003 10015 -10016" universe="0" />
|
||||
<cell id="10000" material="10000" region="10000 -10001 10002 -10003 10004 -10005" universe="10000" />
|
||||
<cell id="10001" material="10001" region="10000 -10001 10002 -10003 10005 -10006" universe="10000" />
|
||||
<cell id="10002" material="10002" region="10000 -10001 10002 -10003 10006 -10007" universe="10000" />
|
||||
<cell id="10003" material="10003" region="10000 -10001 10002 -10003 10007 -10008" universe="10000" />
|
||||
<cell id="10004" material="10004" region="10000 -10001 10002 -10003 10008 -10009" universe="10000" />
|
||||
<cell id="10005" material="10005" region="10000 -10001 10002 -10003 10009 -10010" universe="10000" />
|
||||
<cell id="10006" material="10006" region="10000 -10001 10002 -10003 10010 -10011" universe="10000" />
|
||||
<cell id="10007" material="10007" region="10000 -10001 10002 -10003 10011 -10012" universe="10000" />
|
||||
<cell id="10008" material="10008" region="10000 -10001 10002 -10003 10012 -10013" universe="10000" />
|
||||
<cell id="10009" material="10009" region="10000 -10001 10002 -10003 10013 -10014" universe="10000" />
|
||||
<cell id="10010" material="10010" region="10000 -10001 10002 -10003 10014 -10015" universe="10000" />
|
||||
<cell id="10011" material="10011" region="10000 -10001 10002 -10003 10015 -10016" universe="10000" />
|
||||
<surface boundary="reflective" coeffs="0.0" id="10000" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="10.0" id="10001" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="0.0" id="10002" type="y-plane" />
|
||||
|
|
|
|||
|
|
@ -3,15 +3,11 @@
|
|||
import os
|
||||
import sys
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import TestHarness, PyAPITestHarness
|
||||
import openmc
|
||||
|
||||
|
||||
class MGBasicTestHarness(PyAPITestHarness):
|
||||
def _build_inputs(self):
|
||||
super(MGBasicTestHarness, self)._build_inputs()
|
||||
from testing_harness import PyAPITestHarness
|
||||
from openmc.examples import slab_mg
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = MGBasicTestHarness('statepoint.10.*', False, mg=True)
|
||||
model = slab_mg()
|
||||
harness = PyAPITestHarness('statepoint.10.h5', model)
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -206,5 +206,5 @@ class MGXSTestHarness(PyAPITestHarness):
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = MGXSTestHarness('statepoint.10.*', False)
|
||||
harness = MGXSTestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -1,8 +1,8 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<geometry>
|
||||
<cell id="10000" material="10000" region="10000 -10001 10002 -10003 10004 -10005" universe="0" />
|
||||
<cell id="10001" material="10001" region="10000 -10001 10002 -10003 10005 -10006" universe="0" />
|
||||
<cell id="10002" material="10002" region="10000 -10001 10002 -10003 10006 -10007" universe="0" />
|
||||
<cell id="10000" material="10000" region="10000 -10001 10002 -10003 10004 -10005" universe="10000" />
|
||||
<cell id="10001" material="10001" region="10000 -10001 10002 -10003 10005 -10006" universe="10000" />
|
||||
<cell id="10002" material="10002" region="10000 -10001 10002 -10003 10006 -10007" universe="10000" />
|
||||
<surface boundary="reflective" coeffs="0.0" id="10000" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="10.0" id="10001" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="0.0" id="10002" type="y-plane" />
|
||||
|
|
|
|||
|
|
@ -5,24 +5,12 @@ import sys
|
|||
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import PyAPITestHarness
|
||||
from input_set import MGInputSet
|
||||
|
||||
|
||||
class MGMaxOrderTestHarness(PyAPITestHarness):
|
||||
def __init__(self, statepoint_name, tallies_present, mg=False):
|
||||
PyAPITestHarness.__init__(self, statepoint_name, tallies_present)
|
||||
self._input_set = MGInputSet()
|
||||
|
||||
def _build_inputs(self):
|
||||
"""Write input XML files."""
|
||||
reps = ['iso']
|
||||
self._input_set.build_default_materials_and_geometry(reps=reps)
|
||||
self._input_set.build_default_settings()
|
||||
# Enforce Legendre scattering
|
||||
self._input_set.settings.tabular_legendre = {'enable': False}
|
||||
self._input_set.export()
|
||||
from openmc.examples import slab_mg
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = MGMaxOrderTestHarness('statepoint.10.*', False, mg=True)
|
||||
model = slab_mg(reps=['iso'])
|
||||
model.settings.tabular_legendre = {'enable': False}
|
||||
|
||||
harness = PyAPITestHarness('statepoint.10.h5', model)
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -1,8 +1,8 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<geometry>
|
||||
<cell id="10000" material="10000" region="10000 -10001 10002 -10003 10004 -10005" universe="0" />
|
||||
<cell id="10001" material="10001" region="10000 -10001 10002 -10003 10005 -10006" universe="0" />
|
||||
<cell id="10002" material="10002" region="10000 -10001 10002 -10003 10006 -10007" universe="0" />
|
||||
<cell id="10000" material="10000" region="10000 -10001 10002 -10003 10004 -10005" universe="10000" />
|
||||
<cell id="10001" material="10001" region="10000 -10001 10002 -10003 10005 -10006" universe="10000" />
|
||||
<cell id="10002" material="10002" region="10000 -10001 10002 -10003 10006 -10007" universe="10000" />
|
||||
<surface boundary="reflective" coeffs="0.0" id="10000" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="10.0" id="10001" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="0.0" id="10002" type="y-plane" />
|
||||
|
|
|
|||
|
|
@ -5,24 +5,11 @@ import sys
|
|||
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import PyAPITestHarness
|
||||
from input_set import MGInputSet
|
||||
|
||||
|
||||
class MGMaxOrderTestHarness(PyAPITestHarness):
|
||||
def __init__(self, statepoint_name, tallies_present, mg=False):
|
||||
PyAPITestHarness.__init__(self, statepoint_name, tallies_present)
|
||||
self._input_set = MGInputSet()
|
||||
|
||||
def _build_inputs(self):
|
||||
"""Write input XML files."""
|
||||
reps = ['iso']
|
||||
self._input_set.build_default_materials_and_geometry(reps=reps)
|
||||
self._input_set.build_default_settings()
|
||||
# Set P1 scattering
|
||||
self._input_set.settings.max_order = 1
|
||||
self._input_set.export()
|
||||
from openmc.examples import slab_mg
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = MGMaxOrderTestHarness('statepoint.10.*', False, mg=True)
|
||||
model = slab_mg(reps=['iso'])
|
||||
model.settings.max_order = 1
|
||||
harness = PyAPITestHarness('statepoint.10.h5', model)
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -1,17 +1,17 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<geometry>
|
||||
<cell id="10000" material="10000" region="10000 -10001 10002 -10003 10004 -10005" universe="0" />
|
||||
<cell id="10001" material="10001" region="10000 -10001 10002 -10003 10005 -10006" universe="0" />
|
||||
<cell id="10002" material="10002" region="10000 -10001 10002 -10003 10006 -10007" universe="0" />
|
||||
<cell id="10003" material="10003" region="10000 -10001 10002 -10003 10007 -10008" universe="0" />
|
||||
<cell id="10004" material="10004" region="10000 -10001 10002 -10003 10008 -10009" universe="0" />
|
||||
<cell id="10005" material="10005" region="10000 -10001 10002 -10003 10009 -10010" universe="0" />
|
||||
<cell id="10006" material="10006" region="10000 -10001 10002 -10003 10010 -10011" universe="0" />
|
||||
<cell id="10007" material="10007" region="10000 -10001 10002 -10003 10011 -10012" universe="0" />
|
||||
<cell id="10008" material="10008" region="10000 -10001 10002 -10003 10012 -10013" universe="0" />
|
||||
<cell id="10009" material="10009" region="10000 -10001 10002 -10003 10013 -10014" universe="0" />
|
||||
<cell id="10010" material="10010" region="10000 -10001 10002 -10003 10014 -10015" universe="0" />
|
||||
<cell id="10011" material="10011" region="10000 -10001 10002 -10003 10015 -10016" universe="0" />
|
||||
<cell id="10000" material="10000" region="10000 -10001 10002 -10003 10004 -10005" universe="10000" />
|
||||
<cell id="10001" material="10001" region="10000 -10001 10002 -10003 10005 -10006" universe="10000" />
|
||||
<cell id="10002" material="10002" region="10000 -10001 10002 -10003 10006 -10007" universe="10000" />
|
||||
<cell id="10003" material="10003" region="10000 -10001 10002 -10003 10007 -10008" universe="10000" />
|
||||
<cell id="10004" material="10004" region="10000 -10001 10002 -10003 10008 -10009" universe="10000" />
|
||||
<cell id="10005" material="10005" region="10000 -10001 10002 -10003 10009 -10010" universe="10000" />
|
||||
<cell id="10006" material="10006" region="10000 -10001 10002 -10003 10010 -10011" universe="10000" />
|
||||
<cell id="10007" material="10007" region="10000 -10001 10002 -10003 10011 -10012" universe="10000" />
|
||||
<cell id="10008" material="10008" region="10000 -10001 10002 -10003 10012 -10013" universe="10000" />
|
||||
<cell id="10009" material="10009" region="10000 -10001 10002 -10003 10013 -10014" universe="10000" />
|
||||
<cell id="10010" material="10010" region="10000 -10001 10002 -10003 10014 -10015" universe="10000" />
|
||||
<cell id="10011" material="10011" region="10000 -10001 10002 -10003 10015 -10016" universe="10000" />
|
||||
<surface boundary="reflective" coeffs="0.0" id="10000" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="10.0" id="10001" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="0.0" id="10002" type="y-plane" />
|
||||
|
|
|
|||
|
|
@ -5,21 +5,10 @@ import sys
|
|||
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import PyAPITestHarness
|
||||
from input_set import MGInputSet
|
||||
|
||||
|
||||
class MGNuclideTestHarness(PyAPITestHarness):
|
||||
def __init__(self, statepoint_name, tallies_present, mg=False):
|
||||
PyAPITestHarness.__init__(self, statepoint_name, tallies_present)
|
||||
self._input_set = MGInputSet()
|
||||
|
||||
def _build_inputs(self):
|
||||
"""Write input XML files."""
|
||||
self._input_set.build_default_materials_and_geometry(as_macro=False)
|
||||
self._input_set.build_default_settings()
|
||||
self._input_set.export()
|
||||
from openmc.examples import slab_mg
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = MGNuclideTestHarness('statepoint.10.*', False, mg=True)
|
||||
model = slab_mg(as_macro=False)
|
||||
harness = PyAPITestHarness('statepoint.10.h5', model)
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -1,17 +1,17 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<geometry>
|
||||
<cell id="10000" material="10000" region="10000 -10001 10002 -10003 10004 -10005" universe="0" />
|
||||
<cell id="10001" material="10001" region="10000 -10001 10002 -10003 10005 -10006" universe="0" />
|
||||
<cell id="10002" material="10002" region="10000 -10001 10002 -10003 10006 -10007" universe="0" />
|
||||
<cell id="10003" material="10003" region="10000 -10001 10002 -10003 10007 -10008" universe="0" />
|
||||
<cell id="10004" material="10004" region="10000 -10001 10002 -10003 10008 -10009" universe="0" />
|
||||
<cell id="10005" material="10005" region="10000 -10001 10002 -10003 10009 -10010" universe="0" />
|
||||
<cell id="10006" material="10006" region="10000 -10001 10002 -10003 10010 -10011" universe="0" />
|
||||
<cell id="10007" material="10007" region="10000 -10001 10002 -10003 10011 -10012" universe="0" />
|
||||
<cell id="10008" material="10008" region="10000 -10001 10002 -10003 10012 -10013" universe="0" />
|
||||
<cell id="10009" material="10009" region="10000 -10001 10002 -10003 10013 -10014" universe="0" />
|
||||
<cell id="10010" material="10010" region="10000 -10001 10002 -10003 10014 -10015" universe="0" />
|
||||
<cell id="10011" material="10011" region="10000 -10001 10002 -10003 10015 -10016" universe="0" />
|
||||
<cell id="10000" material="10000" region="10000 -10001 10002 -10003 10004 -10005" universe="10000" />
|
||||
<cell id="10001" material="10001" region="10000 -10001 10002 -10003 10005 -10006" universe="10000" />
|
||||
<cell id="10002" material="10002" region="10000 -10001 10002 -10003 10006 -10007" universe="10000" />
|
||||
<cell id="10003" material="10003" region="10000 -10001 10002 -10003 10007 -10008" universe="10000" />
|
||||
<cell id="10004" material="10004" region="10000 -10001 10002 -10003 10008 -10009" universe="10000" />
|
||||
<cell id="10005" material="10005" region="10000 -10001 10002 -10003 10009 -10010" universe="10000" />
|
||||
<cell id="10006" material="10006" region="10000 -10001 10002 -10003 10010 -10011" universe="10000" />
|
||||
<cell id="10007" material="10007" region="10000 -10001 10002 -10003 10011 -10012" universe="10000" />
|
||||
<cell id="10008" material="10008" region="10000 -10001 10002 -10003 10012 -10013" universe="10000" />
|
||||
<cell id="10009" material="10009" region="10000 -10001 10002 -10003 10013 -10014" universe="10000" />
|
||||
<cell id="10010" material="10010" region="10000 -10001 10002 -10003 10014 -10015" universe="10000" />
|
||||
<cell id="10011" material="10011" region="10000 -10001 10002 -10003 10015 -10016" universe="10000" />
|
||||
<surface boundary="reflective" coeffs="0.0" id="10000" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="10.0" id="10001" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="0.0" id="10002" type="y-plane" />
|
||||
|
|
|
|||
|
|
@ -3,19 +3,12 @@
|
|||
import os
|
||||
import sys
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import TestHarness, PyAPITestHarness
|
||||
import openmc
|
||||
|
||||
|
||||
class MGBasicTestHarness(PyAPITestHarness):
|
||||
def _build_inputs(self):
|
||||
"""Write input XML files."""
|
||||
self._input_set.build_default_materials_and_geometry()
|
||||
self._input_set.build_default_settings()
|
||||
self._input_set.settings.survival_biasing = True
|
||||
self._input_set.export()
|
||||
from testing_harness import PyAPITestHarness
|
||||
from openmc.examples import slab_mg
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = MGBasicTestHarness('statepoint.10.h5', False, mg=True)
|
||||
model = slab_mg()
|
||||
model.settings.survival_biasing = True
|
||||
harness = PyAPITestHarness('statepoint.10.h5', model)
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -1,17 +1,17 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<geometry>
|
||||
<cell id="10000" material="10000" region="10000 -10001 10002 -10003 10004 -10005" universe="0" />
|
||||
<cell id="10001" material="10001" region="10000 -10001 10002 -10003 10005 -10006" universe="0" />
|
||||
<cell id="10002" material="10002" region="10000 -10001 10002 -10003 10006 -10007" universe="0" />
|
||||
<cell id="10003" material="10003" region="10000 -10001 10002 -10003 10007 -10008" universe="0" />
|
||||
<cell id="10004" material="10004" region="10000 -10001 10002 -10003 10008 -10009" universe="0" />
|
||||
<cell id="10005" material="10005" region="10000 -10001 10002 -10003 10009 -10010" universe="0" />
|
||||
<cell id="10006" material="10006" region="10000 -10001 10002 -10003 10010 -10011" universe="0" />
|
||||
<cell id="10007" material="10007" region="10000 -10001 10002 -10003 10011 -10012" universe="0" />
|
||||
<cell id="10008" material="10008" region="10000 -10001 10002 -10003 10012 -10013" universe="0" />
|
||||
<cell id="10009" material="10009" region="10000 -10001 10002 -10003 10013 -10014" universe="0" />
|
||||
<cell id="10010" material="10010" region="10000 -10001 10002 -10003 10014 -10015" universe="0" />
|
||||
<cell id="10011" material="10011" region="10000 -10001 10002 -10003 10015 -10016" universe="0" />
|
||||
<cell id="10000" material="10000" region="10000 -10001 10002 -10003 10004 -10005" universe="10000" />
|
||||
<cell id="10001" material="10001" region="10000 -10001 10002 -10003 10005 -10006" universe="10000" />
|
||||
<cell id="10002" material="10002" region="10000 -10001 10002 -10003 10006 -10007" universe="10000" />
|
||||
<cell id="10003" material="10003" region="10000 -10001 10002 -10003 10007 -10008" universe="10000" />
|
||||
<cell id="10004" material="10004" region="10000 -10001 10002 -10003 10008 -10009" universe="10000" />
|
||||
<cell id="10005" material="10005" region="10000 -10001 10002 -10003 10009 -10010" universe="10000" />
|
||||
<cell id="10006" material="10006" region="10000 -10001 10002 -10003 10010 -10011" universe="10000" />
|
||||
<cell id="10007" material="10007" region="10000 -10001 10002 -10003 10011 -10012" universe="10000" />
|
||||
<cell id="10008" material="10008" region="10000 -10001 10002 -10003 10012 -10013" universe="10000" />
|
||||
<cell id="10009" material="10009" region="10000 -10001 10002 -10003 10013 -10014" universe="10000" />
|
||||
<cell id="10010" material="10010" region="10000 -10001 10002 -10003 10014 -10015" universe="10000" />
|
||||
<cell id="10011" material="10011" region="10000 -10001 10002 -10003 10015 -10016" universe="10000" />
|
||||
<surface boundary="reflective" coeffs="0.0" id="10000" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="10.0" id="10001" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="0.0" id="10002" type="y-plane" />
|
||||
|
|
|
|||
|
|
@ -5,100 +5,91 @@ import sys
|
|||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import HashedPyAPITestHarness
|
||||
import openmc
|
||||
|
||||
|
||||
class MGTalliesTestHarness(HashedPyAPITestHarness):
|
||||
def _build_inputs(self):
|
||||
"""Write input XML files."""
|
||||
self._input_set.build_default_materials_and_geometry(as_macro=False)
|
||||
self._input_set.build_default_settings()
|
||||
|
||||
# Instantiate a tally mesh
|
||||
mesh = openmc.Mesh(mesh_id=1)
|
||||
mesh.type = 'regular'
|
||||
mesh.dimension = [1, 1, 10]
|
||||
mesh.lower_left = [0.0, 0.0, 0.0]
|
||||
mesh.upper_right = [10, 10, 5]
|
||||
|
||||
# Instantiate some tally filters
|
||||
energy_filter = openmc.EnergyFilter([0.0, 20.0e6])
|
||||
energyout_filter = openmc.EnergyoutFilter([0.0, 20.0e6])
|
||||
matching_energy_filter = openmc.EnergyFilter([1e-5, 0.0635, 10.0,
|
||||
1.0e2, 1.0e3, 0.5e6,
|
||||
1.0e6, 20.0e6])
|
||||
matching_eout_filter = openmc.EnergyoutFilter([1e-5, 0.0635, 10.0,
|
||||
1.0e2, 1.0e3, 0.5e6,
|
||||
1.0e6, 20.0e6])
|
||||
mesh_filter = openmc.MeshFilter(mesh)
|
||||
|
||||
mat_ids = [mat.id for mat in self._input_set.materials]
|
||||
mat_filter = openmc.MaterialFilter(mat_ids)
|
||||
|
||||
nuclides = [xs.name for xs in self._input_set.xs_data]
|
||||
|
||||
scores= {False: ['total', 'absorption', 'flux', 'fission', 'nu-fission'],
|
||||
True: ['total', 'absorption', 'fission', 'nu-fission']}
|
||||
|
||||
tallies = []
|
||||
|
||||
for do_nuclides in [False, True]:
|
||||
tallies.append(openmc.Tally())
|
||||
tallies[-1].filters = [mesh_filter]
|
||||
tallies[-1].estimator = 'analog'
|
||||
tallies[-1].scores = scores[do_nuclides]
|
||||
if do_nuclides:
|
||||
tallies[-1].nuclides = nuclides
|
||||
|
||||
tallies.append(openmc.Tally())
|
||||
tallies[-1].filters = [mesh_filter]
|
||||
tallies[-1].estimator = 'tracklength'
|
||||
tallies[-1].scores = scores[do_nuclides]
|
||||
if do_nuclides:
|
||||
tallies[-1].nuclides = nuclides
|
||||
|
||||
# Impose energy bins that dont match the MG structure and those
|
||||
# that do
|
||||
for match_energy_bins in [False, True]:
|
||||
if match_energy_bins:
|
||||
e_filter = matching_energy_filter
|
||||
eout_filter = matching_eout_filter
|
||||
else:
|
||||
e_filter = energy_filter
|
||||
eout_filter = energyout_filter
|
||||
|
||||
tallies.append(openmc.Tally())
|
||||
tallies[-1].filters = [mat_filter, e_filter]
|
||||
tallies[-1].estimator = 'analog'
|
||||
tallies[-1].scores = scores[do_nuclides] + ['scatter',
|
||||
'nu-scatter']
|
||||
if do_nuclides:
|
||||
tallies[-1].nuclides = nuclides
|
||||
|
||||
tallies.append(openmc.Tally())
|
||||
tallies[-1].filters = [mat_filter, e_filter]
|
||||
tallies[-1].estimator = 'collision'
|
||||
tallies[-1].scores = scores[do_nuclides]
|
||||
if do_nuclides:
|
||||
tallies[-1].nuclides = nuclides
|
||||
|
||||
tallies.append(openmc.Tally())
|
||||
tallies[-1].filters = [mat_filter, e_filter]
|
||||
tallies[-1].estimator = 'tracklength'
|
||||
tallies[-1].scores = scores[do_nuclides]
|
||||
if do_nuclides:
|
||||
tallies[-1].nuclides = nuclides
|
||||
|
||||
tallies.append(openmc.Tally())
|
||||
tallies[-1].filters = [mat_filter, e_filter, eout_filter]
|
||||
tallies[-1].scores = ['scatter', 'nu-scatter', 'nu-fission']
|
||||
if do_nuclides:
|
||||
tallies[-1].nuclides = nuclides
|
||||
|
||||
self._input_set.tallies = openmc.Tallies(tallies)
|
||||
|
||||
self._input_set.export()
|
||||
from openmc.examples import slab_mg
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = MGTalliesTestHarness('statepoint.10.h5', True, mg=True)
|
||||
model = slab_mg(as_macro=False)
|
||||
|
||||
# Instantiate a tally mesh
|
||||
mesh = openmc.Mesh(mesh_id=1)
|
||||
mesh.type = 'regular'
|
||||
mesh.dimension = [1, 1, 10]
|
||||
mesh.lower_left = [0.0, 0.0, 0.0]
|
||||
mesh.upper_right = [10, 10, 5]
|
||||
|
||||
# Instantiate some tally filters
|
||||
energy_filter = openmc.EnergyFilter([0.0, 20.0e6])
|
||||
energyout_filter = openmc.EnergyoutFilter([0.0, 20.0e6])
|
||||
energies = [1e-5, 0.0635, 10.0, 1.0e2, 1.0e3, 0.5e6, 1.0e6, 20.0e6]
|
||||
matching_energy_filter = openmc.EnergyFilter(energies)
|
||||
matching_eout_filter = openmc.EnergyoutFilter(energies)
|
||||
mesh_filter = openmc.MeshFilter(mesh)
|
||||
|
||||
mat_filter = openmc.MaterialFilter(model.materials)
|
||||
|
||||
nuclides = [xs.name for xs in model.xs_data]
|
||||
|
||||
scores= {False: ['total', 'absorption', 'flux', 'fission', 'nu-fission'],
|
||||
True: ['total', 'absorption', 'fission', 'nu-fission']}
|
||||
|
||||
for do_nuclides in [False, True]:
|
||||
t = openmc.Tally()
|
||||
t.filters = [mesh_filter]
|
||||
t.estimator = 'analog'
|
||||
t.scores = scores[do_nuclides]
|
||||
if do_nuclides:
|
||||
t.nuclides = nuclides
|
||||
model.tallies.append(t)
|
||||
|
||||
t = openmc.Tally()
|
||||
t.filters = [mesh_filter]
|
||||
t.estimator = 'tracklength'
|
||||
t.scores = scores[do_nuclides]
|
||||
if do_nuclides:
|
||||
t.nuclides = nuclides
|
||||
model.tallies.append(t)
|
||||
|
||||
# Impose energy bins that dont match the MG structure and those
|
||||
# that do
|
||||
for match_energy_bins in [False, True]:
|
||||
if match_energy_bins:
|
||||
e_filter = matching_energy_filter
|
||||
eout_filter = matching_eout_filter
|
||||
else:
|
||||
e_filter = energy_filter
|
||||
eout_filter = energyout_filter
|
||||
|
||||
t = openmc.Tally()
|
||||
t.filters = [mat_filter, e_filter]
|
||||
t.estimator = 'analog'
|
||||
t.scores = scores[do_nuclides] + ['scatter', 'nu-scatter']
|
||||
if do_nuclides:
|
||||
t.nuclides = nuclides
|
||||
model.tallies.append(t)
|
||||
|
||||
t = openmc.Tally()
|
||||
t.filters = [mat_filter, e_filter]
|
||||
t.estimator = 'collision'
|
||||
t.scores = scores[do_nuclides]
|
||||
if do_nuclides:
|
||||
t.nuclides = nuclides
|
||||
model.tallies.append(t)
|
||||
|
||||
t = openmc.Tally()
|
||||
t.filters = [mat_filter, e_filter]
|
||||
t.estimator = 'tracklength'
|
||||
t.scores = scores[do_nuclides]
|
||||
if do_nuclides:
|
||||
t.nuclides = nuclides
|
||||
model.tallies.append(t)
|
||||
|
||||
t = openmc.Tally()
|
||||
t.filters = [mat_filter, e_filter, eout_filter]
|
||||
t.scores = ['scatter', 'nu-scatter', 'nu-fission']
|
||||
if do_nuclides:
|
||||
t.nuclides = nuclides
|
||||
model.tallies.append(t)
|
||||
|
||||
harness = HashedPyAPITestHarness('statepoint.10.h5', model)
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -1,8 +1,8 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<geometry>
|
||||
<cell id="10000" material="10000" name="cell 1" region="-10000" universe="0" />
|
||||
<cell id="10001" material="10001" name="cell 3" region="10000 -10001" universe="0" />
|
||||
<cell id="10002" material="10002" name="cell 2" region="10001 10002 -10003 10004 -10005" universe="0" />
|
||||
<cell id="10000" material="10000" name="Fuel" region="-10000" universe="0" />
|
||||
<cell id="10001" material="10001" name="Cladding" region="10000 -10001" universe="0" />
|
||||
<cell id="10002" material="10002" name="Water" region="10001 10002 -10003 10004 -10005" universe="0" />
|
||||
<surface coeffs="0 0 0.39218" id="10000" name="Fuel OR" type="z-cylinder" />
|
||||
<surface coeffs="0 0 0.4572" id="10001" name="Clad OR" type="z-cylinder" />
|
||||
<surface boundary="reflective" coeffs="-0.63" id="10002" name="left" type="x-plane" />
|
||||
|
|
@ -12,14 +12,14 @@
|
|||
</geometry>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<materials>
|
||||
<material id="10000" name="Fuel">
|
||||
<material id="10000" name="UO2 (2.4%)">
|
||||
<density units="g/cm3" value="10.29769" />
|
||||
<nuclide ao="4.4843e-06" name="U234" />
|
||||
<nuclide ao="0.00055815" name="U235" />
|
||||
<nuclide ao="0.022408" name="U238" />
|
||||
<nuclide ao="0.045829" name="O16" />
|
||||
</material>
|
||||
<material id="10001" name="Cladding">
|
||||
<material id="10001" name="Zircaloy">
|
||||
<density units="g/cm3" value="6.55" />
|
||||
<nuclide ao="0.021827" name="Zr90" />
|
||||
<nuclide ao="0.00476" name="Zr91" />
|
||||
|
|
|
|||
|
|
@ -3,27 +3,23 @@
|
|||
import os
|
||||
import sys
|
||||
import glob
|
||||
import hashlib
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import PyAPITestHarness
|
||||
from input_set import PinCellInputSet
|
||||
import openmc
|
||||
import openmc.mgxs
|
||||
from openmc.examples import pwr_pin_cell
|
||||
|
||||
|
||||
class MGXSTestHarness(PyAPITestHarness):
|
||||
def _build_inputs(self):
|
||||
# Set the input set to use the pincell model
|
||||
self._input_set = PinCellInputSet()
|
||||
|
||||
def __init__(self, *args, **kwargs):
|
||||
# Generate inputs using parent class routine
|
||||
super(MGXSTestHarness, self)._build_inputs()
|
||||
super(MGXSTestHarness, self).__init__(*args, **kwargs)
|
||||
|
||||
# Initialize a two-group structure
|
||||
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625, 20.e6])
|
||||
|
||||
# Initialize MGXS Library for a few cross section types
|
||||
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
|
||||
self.mgxs_lib = openmc.mgxs.Library(self._model.geometry)
|
||||
self.mgxs_lib.by_nuclide = False
|
||||
self.mgxs_lib.mgxs_types = ['total', 'absorption', 'nu-fission matrix',
|
||||
'nu-scatter matrix', 'multiplicity matrix']
|
||||
|
|
@ -34,9 +30,7 @@ class MGXSTestHarness(PyAPITestHarness):
|
|||
self.mgxs_lib.build_library()
|
||||
|
||||
# Initialize a tallies file
|
||||
self._input_set.tallies = openmc.Tallies()
|
||||
self.mgxs_lib.add_to_tallies_file(self._input_set.tallies, merge=False)
|
||||
self._input_set.tallies.export_to_xml()
|
||||
self.mgxs_lib.add_to_tallies_file(self._model.tallies, merge=False)
|
||||
|
||||
def _run_openmc(self):
|
||||
# Initial run
|
||||
|
|
@ -55,18 +49,18 @@ class MGXSTestHarness(PyAPITestHarness):
|
|||
statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0]
|
||||
sp = openmc.StatePoint(statepoint)
|
||||
self.mgxs_lib.load_from_statepoint(sp)
|
||||
self._input_set.mgxs_file, self._input_set.materials, \
|
||||
self._input_set.geometry = self.mgxs_lib.create_mg_mode()
|
||||
self._model.mgxs_file, self._model.materials, \
|
||||
self._model.geometry = self.mgxs_lib.create_mg_mode()
|
||||
|
||||
# Modify materials and settings so we can run in MG mode
|
||||
self._input_set.materials.cross_sections = './mgxs.h5'
|
||||
self._input_set.settings.energy_mode = 'multi-group'
|
||||
self._model.materials.cross_sections = './mgxs.h5'
|
||||
self._model.settings.energy_mode = 'multi-group'
|
||||
|
||||
# Write modified input files
|
||||
self._input_set.settings.export_to_xml()
|
||||
self._input_set.geometry.export_to_xml()
|
||||
self._input_set.materials.export_to_xml()
|
||||
self._input_set.mgxs_file.export_to_hdf5()
|
||||
self._model.settings.export_to_xml()
|
||||
self._model.geometry.export_to_xml()
|
||||
self._model.materials.export_to_xml()
|
||||
self._model.mgxs_file.export_to_hdf5()
|
||||
# Dont need tallies.xml, so remove the file
|
||||
if os.path.exists('./tallies.xml'):
|
||||
os.remove('./tallies.xml')
|
||||
|
|
@ -92,5 +86,8 @@ class MGXSTestHarness(PyAPITestHarness):
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = MGXSTestHarness('statepoint.10.*', False)
|
||||
# Set the input set to use the pincell model
|
||||
model = pwr_pin_cell()
|
||||
|
||||
harness = MGXSTestHarness('statepoint.10.h5', model)
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -1,8 +1,8 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<geometry>
|
||||
<cell id="10000" material="10000" name="cell 1" region="-10000" universe="0" />
|
||||
<cell id="10001" material="10001" name="cell 3" region="10000 -10001" universe="0" />
|
||||
<cell id="10002" material="10002" name="cell 2" region="10001 10002 -10003 10004 -10005" universe="0" />
|
||||
<cell id="10000" material="10000" name="Fuel" region="-10000" universe="0" />
|
||||
<cell id="10001" material="10001" name="Cladding" region="10000 -10001" universe="0" />
|
||||
<cell id="10002" material="10002" name="Water" region="10001 10002 -10003 10004 -10005" universe="0" />
|
||||
<surface coeffs="0 0 0.39218" id="10000" name="Fuel OR" type="z-cylinder" />
|
||||
<surface coeffs="0 0 0.4572" id="10001" name="Clad OR" type="z-cylinder" />
|
||||
<surface boundary="reflective" coeffs="-0.63" id="10002" name="left" type="x-plane" />
|
||||
|
|
@ -12,14 +12,14 @@
|
|||
</geometry>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<materials>
|
||||
<material id="10000" name="Fuel">
|
||||
<material id="10000" name="UO2 (2.4%)">
|
||||
<density units="g/cm3" value="10.29769" />
|
||||
<nuclide ao="4.4843e-06" name="U234" />
|
||||
<nuclide ao="0.00055815" name="U235" />
|
||||
<nuclide ao="0.022408" name="U238" />
|
||||
<nuclide ao="0.045829" name="O16" />
|
||||
</material>
|
||||
<material id="10001" name="Cladding">
|
||||
<material id="10001" name="Zircaloy">
|
||||
<density units="g/cm3" value="6.55" />
|
||||
<nuclide ao="0.021827" name="Zr90" />
|
||||
<nuclide ao="0.00476" name="Zr91" />
|
||||
|
|
|
|||
|
|
@ -6,24 +6,20 @@ import glob
|
|||
import hashlib
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import PyAPITestHarness
|
||||
from input_set import PinCellInputSet
|
||||
import openmc
|
||||
import openmc.mgxs
|
||||
from openmc.examples import pwr_pin_cell
|
||||
|
||||
|
||||
class MGXSTestHarness(PyAPITestHarness):
|
||||
def _build_inputs(self):
|
||||
# Set the input set to use the pincell model
|
||||
self._input_set = PinCellInputSet()
|
||||
|
||||
# Generate inputs using parent class routine
|
||||
super(MGXSTestHarness, self)._build_inputs()
|
||||
def __init__(self, *args, **kwargs):
|
||||
super(MGXSTestHarness, self).__init__(*args, **kwargs)
|
||||
|
||||
# Initialize a two-group structure
|
||||
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625, 20.e6])
|
||||
|
||||
# Initialize MGXS Library for a few cross section types
|
||||
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
|
||||
self.mgxs_lib = openmc.mgxs.Library(self._model.geometry)
|
||||
self.mgxs_lib.by_nuclide = False
|
||||
|
||||
# Test all MGXS types
|
||||
|
|
@ -35,10 +31,8 @@ class MGXSTestHarness(PyAPITestHarness):
|
|||
self.mgxs_lib.domain_type = 'material'
|
||||
self.mgxs_lib.build_library()
|
||||
|
||||
# Initialize a tallies file
|
||||
self._input_set.tallies = openmc.Tallies()
|
||||
self.mgxs_lib.add_to_tallies_file(self._input_set.tallies, merge=False)
|
||||
self._input_set.tallies.export_to_xml()
|
||||
# Add tallies
|
||||
self.mgxs_lib.add_to_tallies_file(self._model.tallies, merge=False)
|
||||
|
||||
def _get_results(self, hash_output=False):
|
||||
"""Digest info in the statepoint and return as a string."""
|
||||
|
|
@ -72,5 +66,7 @@ class MGXSTestHarness(PyAPITestHarness):
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = MGXSTestHarness('statepoint.10.*', True)
|
||||
# Use the pincell model
|
||||
model = pwr_pin_cell()
|
||||
harness = MGXSTestHarness('statepoint.10.h5', model)
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -6,7 +6,7 @@
|
|||
<cell id="10003" material="10002" name="guide tube inner water" region="-10000" universe="10001" />
|
||||
<cell id="10004" material="10001" name="guide tube clad" region="10000 -10001" universe="10001" />
|
||||
<cell id="10005" material="10002" name="guide tube outer water" region="10001" universe="10001" />
|
||||
<cell fill="10002" id="10006" name="root cell" region="10002 -10003 10004 -10005" universe="0" />
|
||||
<cell fill="10002" id="10006" name="root cell" region="10002 -10003 10004 -10005" universe="10003" />
|
||||
<lattice id="10002" name="Fuel Assembly">
|
||||
<pitch>1.26 1.26</pitch>
|
||||
<dimension>17 17</dimension>
|
||||
|
|
|
|||
|
|
@ -6,25 +6,22 @@ import glob
|
|||
import hashlib
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import PyAPITestHarness
|
||||
from input_set import AssemblyInputSet
|
||||
import openmc
|
||||
import openmc.mgxs
|
||||
from openmc.examples import pwr_assembly
|
||||
|
||||
|
||||
class MGXSTestHarness(PyAPITestHarness):
|
||||
def _build_inputs(self):
|
||||
# Set the input set to use the pincell model
|
||||
self._input_set = AssemblyInputSet()
|
||||
|
||||
def __init__(self, *args, **kwargs):
|
||||
# Generate inputs using parent class routine
|
||||
super(MGXSTestHarness, self)._build_inputs()
|
||||
super(MGXSTestHarness, self).__init__(*args, **kwargs)
|
||||
|
||||
# Initialize a one-group structure
|
||||
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 20.e6])
|
||||
|
||||
# Initialize MGXS Library for a few cross section types
|
||||
# for one material-filled cell in the geometry
|
||||
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
|
||||
self.mgxs_lib = openmc.mgxs.Library(self._model.geometry)
|
||||
self.mgxs_lib.by_nuclide = False
|
||||
|
||||
# Test all MGXS types
|
||||
|
|
@ -38,10 +35,9 @@ class MGXSTestHarness(PyAPITestHarness):
|
|||
self.mgxs_lib.domains = [c for c in cells if c.name == 'fuel']
|
||||
self.mgxs_lib.build_library()
|
||||
|
||||
# Initialize a tallies file
|
||||
self._input_set.tallies = openmc.Tallies()
|
||||
self.mgxs_lib.add_to_tallies_file(self._input_set.tallies, merge=False)
|
||||
self._input_set.tallies.export_to_xml()
|
||||
# Add tallies
|
||||
self.mgxs_lib.add_to_tallies_file(self._model.tallies, merge=False)
|
||||
self._model.tallies.export_to_xml()
|
||||
|
||||
def _get_results(self, hash_output=False):
|
||||
"""Digest info in the statepoint and return as a string."""
|
||||
|
|
@ -74,5 +70,6 @@ class MGXSTestHarness(PyAPITestHarness):
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = MGXSTestHarness('statepoint.10.h5', True)
|
||||
model = pwr_assembly()
|
||||
harness = MGXSTestHarness('statepoint.10.h5', model)
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -1,8 +1,8 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<geometry>
|
||||
<cell id="10000" material="10000" name="cell 1" region="-10000" universe="0" />
|
||||
<cell id="10001" material="10001" name="cell 3" region="10000 -10001" universe="0" />
|
||||
<cell id="10002" material="10002" name="cell 2" region="10001 10002 -10003 10004 -10005" universe="0" />
|
||||
<cell id="10000" material="10000" name="Fuel" region="-10000" universe="0" />
|
||||
<cell id="10001" material="10001" name="Cladding" region="10000 -10001" universe="0" />
|
||||
<cell id="10002" material="10002" name="Water" region="10001 10002 -10003 10004 -10005" universe="0" />
|
||||
<surface coeffs="0 0 0.39218" id="10000" name="Fuel OR" type="z-cylinder" />
|
||||
<surface coeffs="0 0 0.4572" id="10001" name="Clad OR" type="z-cylinder" />
|
||||
<surface boundary="reflective" coeffs="-0.63" id="10002" name="left" type="x-plane" />
|
||||
|
|
@ -12,14 +12,14 @@
|
|||
</geometry>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<materials>
|
||||
<material id="10000" name="Fuel">
|
||||
<material id="10000" name="UO2 (2.4%)">
|
||||
<density units="g/cm3" value="10.29769" />
|
||||
<nuclide ao="4.4843e-06" name="U234" />
|
||||
<nuclide ao="0.00055815" name="U235" />
|
||||
<nuclide ao="0.022408" name="U238" />
|
||||
<nuclide ao="0.045829" name="O16" />
|
||||
</material>
|
||||
<material id="10001" name="Cladding">
|
||||
<material id="10001" name="Zircaloy">
|
||||
<density units="g/cm3" value="6.55" />
|
||||
<nuclide ao="0.021827" name="Zr90" />
|
||||
<nuclide ao="0.00476" name="Zr91" />
|
||||
|
|
|
|||
|
|
@ -105,18 +105,18 @@ domain=10000 type=prompt-nu-fission matrix
|
|||
[[3.14909051e-03 0.00000000e+00]
|
||||
[2.86750878e-02 0.00000000e+00]]
|
||||
domain=10000 type=delayed-nu-fission
|
||||
[[2.29808266e-05 1.06974147e-04]
|
||||
[1.43606354e-04 5.52167849e-04]
|
||||
[1.51382232e-04 5.27147626e-04]
|
||||
[7.42603126e-05 2.22017986e-04]
|
||||
[4.14908415e-05 9.10244168e-05]
|
||||
[1.70015984e-05 3.81298021e-05]]
|
||||
[[1.66363187e-06 9.49155601e-06]
|
||||
[1.05907827e-05 4.89925095e-05]
|
||||
[1.12671254e-05 4.67725251e-05]
|
||||
[5.22610330e-06 1.87563055e-05]
|
||||
[2.99830756e-06 7.68983466e-06]
|
||||
[1.22654681e-06 3.22124422e-06]]
|
||||
[[4.31687649e-06 1.06974147e-04]
|
||||
[2.69760050e-05 5.52167849e-04]
|
||||
[2.84366794e-05 5.27147626e-04]
|
||||
[7.42603126e-05 1.18190938e-03]
|
||||
[4.14908415e-05 4.84567103e-04]
|
||||
[1.70015984e-05 2.02983423e-04]]
|
||||
[[2.89748553e-07 9.49155601e-06]
|
||||
[1.85003751e-06 4.89925095e-05]
|
||||
[1.97097930e-06 4.67725251e-05]
|
||||
[5.22610330e-06 1.04867938e-04]
|
||||
[2.99830756e-06 4.29944539e-05]
|
||||
[1.22654681e-06 1.80102228e-05]]
|
||||
domain=10000 type=chi-delayed
|
||||
[[0.00000000e+00 0.00000000e+00]
|
||||
[1.00000000e+00 0.00000000e+00]
|
||||
|
|
@ -131,18 +131,18 @@ domain=10000 type=chi-delayed
|
|||
[0.00000000e+00 0.00000000e+00]
|
||||
[0.00000000e+00 0.00000000e+00]]
|
||||
domain=10000 type=beta
|
||||
[[4.89188226e-05 2.27713711e-04]
|
||||
[3.05691952e-04 1.17538858e-03]
|
||||
[3.22244307e-04 1.12212853e-03]
|
||||
[3.82159878e-03 1.14255332e-02]
|
||||
[2.13520982e-03 4.68431640e-03]
|
||||
[8.74939593e-04 1.96224336e-03]]
|
||||
[[4.67388636e-06 2.46946655e-05]
|
||||
[2.95223864e-05 1.27466313e-04]
|
||||
[3.12884979e-05 1.21690467e-04]
|
||||
[3.21434953e-04 1.09939768e-03]
|
||||
[1.82980531e-04 4.50738369e-04]
|
||||
[7.48900067e-05 1.88812689e-04]]
|
||||
[[2.22155945e-04 2.27713711e-04]
|
||||
[1.38824446e-03 1.17538858e-03]
|
||||
[1.46341397e-03 1.12212853e-03]
|
||||
[3.82159878e-03 2.51590670e-03]
|
||||
[2.13520982e-03 1.03148823e-03]
|
||||
[8.74939593e-04 4.32086725e-04]]
|
||||
[[1.80847602e-05 2.46946655e-05]
|
||||
[1.14688936e-04 1.27466313e-04]
|
||||
[1.21787672e-04 1.21690467e-04]
|
||||
[3.21434953e-04 2.72840272e-04]
|
||||
[1.82980531e-04 1.11860871e-04]
|
||||
[7.48900067e-05 4.68581181e-05]]
|
||||
domain=10000 type=decay-rate
|
||||
[[1.34450193e-02 1.33360001e-02]
|
||||
[3.20638663e-02 3.27389978e-02]
|
||||
|
|
@ -167,7 +167,7 @@ domain=10000 type=delayed-nu-fission matrix
|
|||
[1.18579136e-03 0.00000000e+00]]
|
||||
|
||||
[[0.00000000e+00 0.00000000e+00]
|
||||
[8.59786782e-04 0.00000000e+00]]
|
||||
[4.82335163e-03 0.00000000e+00]]
|
||||
|
||||
[[0.00000000e+00 0.00000000e+00]
|
||||
[0.00000000e+00 0.00000000e+00]]
|
||||
|
|
@ -184,7 +184,7 @@ domain=10000 type=delayed-nu-fission matrix
|
|||
[1.18610370e-03 0.00000000e+00]]
|
||||
|
||||
[[0.00000000e+00 0.00000000e+00]
|
||||
[2.22194557e-04 0.00000000e+00]]
|
||||
[1.23402593e-03 0.00000000e+00]]
|
||||
|
||||
[[0.00000000e+00 0.00000000e+00]
|
||||
[0.00000000e+00 0.00000000e+00]]
|
||||
|
|
|
|||
|
|
@ -10,27 +10,24 @@ import h5py
|
|||
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import PyAPITestHarness
|
||||
from input_set import PinCellInputSet
|
||||
import openmc
|
||||
import openmc.mgxs
|
||||
from openmc.examples import pwr_pin_cell
|
||||
|
||||
|
||||
np.set_printoptions(formatter={'float_kind': '{:.8e}'.format})
|
||||
|
||||
|
||||
class MGXSTestHarness(PyAPITestHarness):
|
||||
def _build_inputs(self):
|
||||
# Set the input set to use the pincell model
|
||||
self._input_set = PinCellInputSet()
|
||||
|
||||
def __init__(self, *args, **kwargs):
|
||||
# Generate inputs using parent class routine
|
||||
super(MGXSTestHarness, self)._build_inputs()
|
||||
super(MGXSTestHarness, self).__init__(*args, **kwargs)
|
||||
|
||||
# Initialize a two-group structure
|
||||
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625, 20.e6])
|
||||
|
||||
# Initialize MGXS Library for a few cross section types
|
||||
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
|
||||
self.mgxs_lib = openmc.mgxs.Library(self._model.geometry)
|
||||
self.mgxs_lib.by_nuclide = False
|
||||
|
||||
# Test all MGXS types
|
||||
|
|
@ -42,10 +39,8 @@ class MGXSTestHarness(PyAPITestHarness):
|
|||
self.mgxs_lib.domain_type = 'material'
|
||||
self.mgxs_lib.build_library()
|
||||
|
||||
# Initialize a tallies file
|
||||
self._input_set.tallies = openmc.Tallies()
|
||||
self.mgxs_lib.add_to_tallies_file(self._input_set.tallies, merge=False)
|
||||
self._input_set.tallies.export_to_xml()
|
||||
# Add tallies
|
||||
self.mgxs_lib.add_to_tallies_file(self._model.tallies, merge=False)
|
||||
|
||||
def _get_results(self, hash_output=False):
|
||||
"""Digest info in the statepoint and return as a string."""
|
||||
|
|
@ -59,21 +54,18 @@ class MGXSTestHarness(PyAPITestHarness):
|
|||
|
||||
# Export the MGXS Library to an HDF5 file
|
||||
self.mgxs_lib.build_hdf5_store(directory='.')
|
||||
|
||||
|
||||
# Open the MGXS HDF5 file
|
||||
f = h5py.File('mgxs.h5', 'r')
|
||||
with h5py.File('mgxs.h5', 'r') as f:
|
||||
|
||||
# Build a string from the datasets in the HDF5 file
|
||||
outstr = ''
|
||||
for domain in self.mgxs_lib.domains:
|
||||
for mgxs_type in self.mgxs_lib.mgxs_types:
|
||||
outstr += 'domain={0} type={1}\n'.format(domain.id, mgxs_type)
|
||||
avg_key = 'material/{0}/{1}/average'.format(domain.id, mgxs_type)
|
||||
std_key = 'material/{0}/{1}/std. dev.'.format(domain.id, mgxs_type)
|
||||
outstr += '{}\n{}\n'.format(f[avg_key][...], f[std_key][...])
|
||||
|
||||
# Close the MGXS HDF5 file
|
||||
f.close()
|
||||
# Build a string from the datasets in the HDF5 file
|
||||
outstr = ''
|
||||
for domain in self.mgxs_lib.domains:
|
||||
for mgxs_type in self.mgxs_lib.mgxs_types:
|
||||
outstr += 'domain={0} type={1}\n'.format(domain.id, mgxs_type)
|
||||
avg_key = 'material/{0}/{1}/average'.format(domain.id, mgxs_type)
|
||||
std_key = 'material/{0}/{1}/std. dev.'.format(domain.id, mgxs_type)
|
||||
outstr += '{}\n{}\n'.format(f[avg_key][...], f[std_key][...])
|
||||
|
||||
# Hash the results if necessary
|
||||
if hash_output:
|
||||
|
|
@ -85,12 +77,12 @@ class MGXSTestHarness(PyAPITestHarness):
|
|||
|
||||
def _cleanup(self):
|
||||
super(MGXSTestHarness, self)._cleanup()
|
||||
f = os.path.join(os.getcwd(), 'tallies.xml')
|
||||
if os.path.exists(f): os.remove(f)
|
||||
f = os.path.join(os.getcwd(), 'mgxs.h5')
|
||||
if os.path.exists(f): os.remove(f)
|
||||
if os.path.exists(f):
|
||||
os.remove(f)
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = MGXSTestHarness('statepoint.10.*', True)
|
||||
model = pwr_pin_cell()
|
||||
harness = MGXSTestHarness('statepoint.10.h5', model)
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -148,7 +148,7 @@
|
|||
</geometry>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<materials>
|
||||
<material id="1" name="Fuel">
|
||||
<material id="1" name="UOX fuel">
|
||||
<density units="g/cm3" value="10.062" />
|
||||
<nuclide ao="4.9476e-06" name="U234" />
|
||||
<nuclide ao="0.00048218" name="U235" />
|
||||
|
|
@ -197,7 +197,7 @@
|
|||
<nuclide name="Zr96" wo="0.0216912612" />
|
||||
<sab name="c_H_in_H2O" />
|
||||
</material>
|
||||
<material id="2" name="Cladding">
|
||||
<material id="2" name="Zircaloy">
|
||||
<density units="g/cm3" value="5.77" />
|
||||
<nuclide ao="0.5145" name="Zr90" />
|
||||
<nuclide ao="0.1122" name="Zr91" />
|
||||
|
|
@ -249,7 +249,7 @@
|
|||
<nuclide name="Cr52" wo="0.145407678031" />
|
||||
<sab name="c_H_in_H2O" />
|
||||
</material>
|
||||
<material id="7" name="Upper radial reflector /Top plate region">
|
||||
<material id="7" name="Upper radial reflector / Top plate region">
|
||||
<density units="g/cm3" value="4.28" />
|
||||
<nuclide name="H1" wo="0.0086117" />
|
||||
<nuclide name="O16" wo="0.0683369" />
|
||||
|
|
|
|||
|
|
@ -11,16 +11,15 @@ import openmc.mgxs
|
|||
|
||||
|
||||
class MGXSTestHarness(PyAPITestHarness):
|
||||
def _build_inputs(self):
|
||||
# Generate inputs using parent class routine
|
||||
super(MGXSTestHarness, self)._build_inputs()
|
||||
def __init__(self, *args, **kwargs):
|
||||
super(MGXSTestHarness, self).__init__(*args, **kwargs)
|
||||
|
||||
# Initialize a one-group structure
|
||||
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 20.e6])
|
||||
|
||||
# Initialize MGXS Library for a few cross section types
|
||||
# for one material-filled cell in the geometry
|
||||
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
|
||||
self.mgxs_lib = openmc.mgxs.Library(self._model.geometry)
|
||||
self.mgxs_lib.by_nuclide = False
|
||||
|
||||
# Test all MGXS types
|
||||
|
|
@ -41,10 +40,8 @@ class MGXSTestHarness(PyAPITestHarness):
|
|||
self.mgxs_lib.domains = [mesh]
|
||||
self.mgxs_lib.build_library()
|
||||
|
||||
# Initialize a tallies file
|
||||
self._input_set.tallies = openmc.Tallies()
|
||||
self.mgxs_lib.add_to_tallies_file(self._input_set.tallies, merge=False)
|
||||
self._input_set.tallies.export_to_xml()
|
||||
# Add tallies
|
||||
self.mgxs_lib.add_to_tallies_file(self._model.tallies, merge=False)
|
||||
|
||||
def _get_results(self, hash_output=False):
|
||||
"""Digest info in the statepoint and return as a string."""
|
||||
|
|
@ -74,5 +71,5 @@ class MGXSTestHarness(PyAPITestHarness):
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = MGXSTestHarness('statepoint.10.h5', True)
|
||||
harness = MGXSTestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -1,8 +1,8 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<geometry>
|
||||
<cell id="10000" material="10000" name="cell 1" region="-10000" universe="0" />
|
||||
<cell id="10001" material="10001" name="cell 3" region="10000 -10001" universe="0" />
|
||||
<cell id="10002" material="10002" name="cell 2" region="10001 10002 -10003 10004 -10005" universe="0" />
|
||||
<cell id="10000" material="10000" name="Fuel" region="-10000" universe="0" />
|
||||
<cell id="10001" material="10001" name="Cladding" region="10000 -10001" universe="0" />
|
||||
<cell id="10002" material="10002" name="Water" region="10001 10002 -10003 10004 -10005" universe="0" />
|
||||
<surface coeffs="0 0 0.39218" id="10000" name="Fuel OR" type="z-cylinder" />
|
||||
<surface coeffs="0 0 0.4572" id="10001" name="Clad OR" type="z-cylinder" />
|
||||
<surface boundary="reflective" coeffs="-0.63" id="10002" name="left" type="x-plane" />
|
||||
|
|
@ -12,14 +12,14 @@
|
|||
</geometry>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<materials>
|
||||
<material id="10000" name="Fuel">
|
||||
<material id="10000" name="UO2 (2.4%)">
|
||||
<density units="g/cm3" value="10.29769" />
|
||||
<nuclide ao="4.4843e-06" name="U234" />
|
||||
<nuclide ao="0.00055815" name="U235" />
|
||||
<nuclide ao="0.022408" name="U238" />
|
||||
<nuclide ao="0.045829" name="O16" />
|
||||
</material>
|
||||
<material id="10001" name="Cladding">
|
||||
<material id="10001" name="Zircaloy">
|
||||
<density units="g/cm3" value="6.55" />
|
||||
<nuclide ao="0.021827" name="Zr90" />
|
||||
<nuclide ao="0.00476" name="Zr91" />
|
||||
|
|
|
|||
|
|
@ -128,19 +128,19 @@
|
|||
2 10000 1 2 total 0.000000 0.000000
|
||||
1 10000 2 1 total 0.445819 0.028675
|
||||
0 10000 2 2 total 0.000000 0.000000
|
||||
material delayedgroup group in nuclide mean std. dev.
|
||||
1 10000 1 1 total 0.000023 0.000002
|
||||
3 10000 2 1 total 0.000144 0.000011
|
||||
5 10000 3 1 total 0.000151 0.000011
|
||||
7 10000 4 1 total 0.000074 0.000005
|
||||
9 10000 5 1 total 0.000041 0.000003
|
||||
11 10000 6 1 total 0.000017 0.000001
|
||||
0 10000 1 2 total 0.000107 0.000009
|
||||
2 10000 2 2 total 0.000552 0.000049
|
||||
4 10000 3 2 total 0.000527 0.000047
|
||||
6 10000 4 2 total 0.000222 0.000019
|
||||
8 10000 5 2 total 0.000091 0.000008
|
||||
10 10000 6 2 total 0.000038 0.000003
|
||||
material delayedgroup group in nuclide mean std. dev.
|
||||
1 10000 1 1 total 0.000004 2.897486e-07
|
||||
3 10000 2 1 total 0.000027 1.850038e-06
|
||||
5 10000 3 1 total 0.000028 1.970979e-06
|
||||
7 10000 4 1 total 0.000074 5.226103e-06
|
||||
9 10000 5 1 total 0.000041 2.998308e-06
|
||||
11 10000 6 1 total 0.000017 1.226547e-06
|
||||
0 10000 1 2 total 0.000107 9.491556e-06
|
||||
2 10000 2 2 total 0.000552 4.899251e-05
|
||||
4 10000 3 2 total 0.000527 4.677253e-05
|
||||
6 10000 4 2 total 0.001182 1.048679e-04
|
||||
8 10000 5 2 total 0.000485 4.299445e-05
|
||||
10 10000 6 2 total 0.000203 1.801022e-05
|
||||
material delayedgroup group out nuclide mean std. dev.
|
||||
1 10000 1 1 total 0.0 0.000000
|
||||
3 10000 2 1 total 1.0 0.869128
|
||||
|
|
@ -155,18 +155,18 @@
|
|||
8 10000 5 2 total 0.0 0.000000
|
||||
10 10000 6 2 total 0.0 0.000000
|
||||
material delayedgroup group in nuclide mean std. dev.
|
||||
1 10000 1 1 total 0.000049 0.000005
|
||||
3 10000 2 1 total 0.000306 0.000030
|
||||
5 10000 3 1 total 0.000322 0.000031
|
||||
1 10000 1 1 total 0.000222 0.000018
|
||||
3 10000 2 1 total 0.001388 0.000115
|
||||
5 10000 3 1 total 0.001463 0.000122
|
||||
7 10000 4 1 total 0.003822 0.000321
|
||||
9 10000 5 1 total 0.002135 0.000183
|
||||
11 10000 6 1 total 0.000875 0.000075
|
||||
0 10000 1 2 total 0.000228 0.000025
|
||||
2 10000 2 2 total 0.001175 0.000127
|
||||
4 10000 3 2 total 0.001122 0.000122
|
||||
6 10000 4 2 total 0.011426 0.001099
|
||||
8 10000 5 2 total 0.004684 0.000451
|
||||
10 10000 6 2 total 0.001962 0.000189
|
||||
6 10000 4 2 total 0.002516 0.000273
|
||||
8 10000 5 2 total 0.001031 0.000112
|
||||
10 10000 6 2 total 0.000432 0.000047
|
||||
material delayedgroup group in nuclide mean std. dev.
|
||||
1 10000 1 1 total 0.013445 0.001084
|
||||
3 10000 2 1 total 0.032064 0.002658
|
||||
|
|
@ -196,7 +196,7 @@
|
|||
1 10000 1 2 1 total 0.000000 0.000000
|
||||
5 10000 2 2 1 total 0.002538 0.001561
|
||||
9 10000 3 2 1 total 0.001186 0.001186
|
||||
13 10000 4 2 1 total 0.000860 0.000222
|
||||
13 10000 4 2 1 total 0.004823 0.001234
|
||||
17 10000 5 2 1 total 0.000000 0.000000
|
||||
21 10000 6 2 1 total 0.000000 0.000000
|
||||
0 10000 1 2 2 total 0.000000 0.000000
|
||||
|
|
|
|||
|
|
@ -6,24 +6,21 @@ import glob
|
|||
import hashlib
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import PyAPITestHarness
|
||||
from input_set import PinCellInputSet
|
||||
import openmc
|
||||
import openmc.mgxs
|
||||
from openmc.examples import pwr_pin_cell
|
||||
|
||||
|
||||
class MGXSTestHarness(PyAPITestHarness):
|
||||
def _build_inputs(self):
|
||||
# Set the input set to use the pincell model
|
||||
self._input_set = PinCellInputSet()
|
||||
|
||||
def __init__(self, *args, **kwargs):
|
||||
# Generate inputs using parent class routine
|
||||
super(MGXSTestHarness, self)._build_inputs()
|
||||
super(MGXSTestHarness, self).__init__(*args, **kwargs)
|
||||
|
||||
# Initialize a two-group structure
|
||||
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625, 20.e6])
|
||||
|
||||
# Initialize MGXS Library for a few cross section types
|
||||
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
|
||||
self.mgxs_lib = openmc.mgxs.Library(self._model.geometry)
|
||||
self.mgxs_lib.by_nuclide = False
|
||||
|
||||
# Test all MGXS types
|
||||
|
|
@ -35,10 +32,8 @@ class MGXSTestHarness(PyAPITestHarness):
|
|||
self.mgxs_lib.domain_type = 'material'
|
||||
self.mgxs_lib.build_library()
|
||||
|
||||
# Initialize a tallies file
|
||||
self._input_set.tallies = openmc.Tallies()
|
||||
self.mgxs_lib.add_to_tallies_file(self._input_set.tallies, merge=False)
|
||||
self._input_set.tallies.export_to_xml()
|
||||
# Add tallies
|
||||
self.mgxs_lib.add_to_tallies_file(self._model.tallies, merge=False)
|
||||
|
||||
def _get_results(self, hash_output=False):
|
||||
"""Digest info in the statepoint and return as a string."""
|
||||
|
|
@ -68,5 +63,6 @@ class MGXSTestHarness(PyAPITestHarness):
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = MGXSTestHarness('statepoint.10.h5', True)
|
||||
model = pwr_pin_cell()
|
||||
harness = MGXSTestHarness('statepoint.10.h5', model)
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -1,8 +1,8 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<geometry>
|
||||
<cell id="10000" material="10000" name="cell 1" region="-10000" universe="0" />
|
||||
<cell id="10001" material="10001" name="cell 3" region="10000 -10001" universe="0" />
|
||||
<cell id="10002" material="10002" name="cell 2" region="10001 10002 -10003 10004 -10005" universe="0" />
|
||||
<cell id="10000" material="10000" name="Fuel" region="-10000" universe="0" />
|
||||
<cell id="10001" material="10001" name="Cladding" region="10000 -10001" universe="0" />
|
||||
<cell id="10002" material="10002" name="Water" region="10001 10002 -10003 10004 -10005" universe="0" />
|
||||
<surface coeffs="0 0 0.39218" id="10000" name="Fuel OR" type="z-cylinder" />
|
||||
<surface coeffs="0 0 0.4572" id="10001" name="Clad OR" type="z-cylinder" />
|
||||
<surface boundary="reflective" coeffs="-0.63" id="10002" name="left" type="x-plane" />
|
||||
|
|
@ -12,14 +12,14 @@
|
|||
</geometry>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<materials>
|
||||
<material id="10000" name="Fuel">
|
||||
<material id="10000" name="UO2 (2.4%)">
|
||||
<density units="g/cm3" value="10.29769" />
|
||||
<nuclide ao="4.4843e-06" name="U234" />
|
||||
<nuclide ao="0.00055815" name="U235" />
|
||||
<nuclide ao="0.022408" name="U238" />
|
||||
<nuclide ao="0.045829" name="O16" />
|
||||
</material>
|
||||
<material id="10001" name="Cladding">
|
||||
<material id="10001" name="Zircaloy">
|
||||
<density units="g/cm3" value="6.55" />
|
||||
<nuclide ao="0.021827" name="Zr90" />
|
||||
<nuclide ao="0.00476" name="Zr91" />
|
||||
|
|
|
|||
|
|
@ -1 +1 @@
|
|||
107576b21fa8ed72f71ac65866e4ad1100cc62df527f6f4e6bb8a6318f3694614b6ba1c72634b2e97474a75ea1b3112dcb9b4b36e58f0417e5b04aee5d3c7570
|
||||
ea1c7567cb5399ab26297b5df0c1c21b52863303746d04f1698760d88b1aafb625d5743969ad30b194c353d106ed4287a8bc755ea6404c2f5dafb2ea930444a7
|
||||
|
|
@ -6,24 +6,20 @@ import glob
|
|||
import hashlib
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import PyAPITestHarness
|
||||
from input_set import PinCellInputSet
|
||||
import openmc
|
||||
import openmc.mgxs
|
||||
from openmc.examples import pwr_pin_cell
|
||||
|
||||
|
||||
class MGXSTestHarness(PyAPITestHarness):
|
||||
def _build_inputs(self):
|
||||
# Set the input set to use the pincell model
|
||||
self._input_set = PinCellInputSet()
|
||||
|
||||
# Generate inputs using parent class routine
|
||||
super(MGXSTestHarness, self)._build_inputs()
|
||||
def __init__(self, *args, **kwargs):
|
||||
super(MGXSTestHarness, self).__init__(*args, **kwargs)
|
||||
|
||||
# Initialize a two-group structure
|
||||
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625, 20.e6])
|
||||
|
||||
# Initialize MGXS Library for a few cross section types
|
||||
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
|
||||
self.mgxs_lib = openmc.mgxs.Library(self._model.geometry)
|
||||
self.mgxs_lib.by_nuclide = True
|
||||
# Test all MGXS types
|
||||
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES
|
||||
|
|
@ -32,10 +28,8 @@ class MGXSTestHarness(PyAPITestHarness):
|
|||
self.mgxs_lib.domain_type = 'material'
|
||||
self.mgxs_lib.build_library()
|
||||
|
||||
# Initialize a tallies file
|
||||
self._input_set.tallies = openmc.Tallies()
|
||||
self.mgxs_lib.add_to_tallies_file(self._input_set.tallies, merge=False)
|
||||
self._input_set.tallies.export_to_xml()
|
||||
# Add tallies
|
||||
self.mgxs_lib.add_to_tallies_file(self._model.tallies, merge=False)
|
||||
|
||||
def _get_results(self, hash_output=True):
|
||||
"""Digest info in the statepoint and return as a string."""
|
||||
|
|
@ -65,5 +59,6 @@ class MGXSTestHarness(PyAPITestHarness):
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = MGXSTestHarness('statepoint.10.h5', True)
|
||||
model = pwr_pin_cell()
|
||||
harness = MGXSTestHarness('statepoint.10.h5', model)
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -43,22 +43,13 @@
|
|||
<parameters>-1 -1 -1 1 1 1</parameters>
|
||||
</space>
|
||||
</source>
|
||||
<output>
|
||||
<summary>true</summary>
|
||||
</output>
|
||||
<temperature_multipole>True</temperature_multipole>
|
||||
<temperature_multipole>true</temperature_multipole>
|
||||
<temperature_tolerance>1000</temperature_tolerance>
|
||||
</settings>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<plots>
|
||||
<plot basis="xy" color_by="cell" filename="cellplot" id="1" type="slice">
|
||||
<origin>0 0 0</origin>
|
||||
<width>7 7</width>
|
||||
<pixels>400 400</pixels>
|
||||
</plot>
|
||||
<plot basis="xy" color_by="material" filename="matplot" id="2" type="slice">
|
||||
<origin>0 0 0</origin>
|
||||
<width>7 7</width>
|
||||
<pixels>400 400</pixels>
|
||||
</plot>
|
||||
</plots>
|
||||
<tallies>
|
||||
<tally id="10000">
|
||||
<nuclides>U235 O16 total</nuclides>
|
||||
<scores>total fission (n,gamma) elastic (n,p)</scores>
|
||||
</tally>
|
||||
</tallies>
|
||||
|
|
|
|||
|
|
@ -1,5 +1,36 @@
|
|||
k-combined:
|
||||
1.363786E+00 1.103929E-02
|
||||
tally 1:
|
||||
3.960375E+00
|
||||
3.138356E+00
|
||||
2.875799E+00
|
||||
1.655329E+00
|
||||
5.521904E-01
|
||||
6.105083E-02
|
||||
4.617974E-01
|
||||
4.274130E-02
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
2.254165E+01
|
||||
1.016444E+02
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
6.839351E-04
|
||||
9.359599E-08
|
||||
2.251829E+01
|
||||
1.014341E+02
|
||||
4.903575E-05
|
||||
1.199780E-09
|
||||
3.595002E+02
|
||||
2.586079E+04
|
||||
2.875799E+00
|
||||
1.655329E+00
|
||||
2.174747E+00
|
||||
9.465589E-01
|
||||
3.543564E+02
|
||||
2.512619E+04
|
||||
4.903575E-05
|
||||
1.199780E-09
|
||||
Cell
|
||||
ID = 11
|
||||
Name =
|
||||
|
|
|
|||
|
|
@ -4,99 +4,69 @@ import sys
|
|||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import TestHarness, PyAPITestHarness
|
||||
import openmc
|
||||
from openmc.stats import Box
|
||||
from openmc.source import Source
|
||||
import openmc.model
|
||||
|
||||
|
||||
def make_model():
|
||||
model = openmc.model.Model()
|
||||
|
||||
# Materials
|
||||
moderator = openmc.Material(material_id=1)
|
||||
moderator.set_density('g/cc', 1.0)
|
||||
moderator.add_nuclide('H1', 2.0)
|
||||
moderator.add_nuclide('O16', 1.0)
|
||||
moderator.add_s_alpha_beta('c_H_in_H2O')
|
||||
|
||||
dense_fuel = openmc.Material(material_id=2)
|
||||
dense_fuel.set_density('g/cc', 4.5)
|
||||
dense_fuel.add_nuclide('U235', 1.0)
|
||||
|
||||
model.materials += [moderator, dense_fuel]
|
||||
|
||||
# Geometry
|
||||
c1 = openmc.Cell(cell_id=1, fill=moderator)
|
||||
mod_univ = openmc.Universe(universe_id=1, cells=(c1,))
|
||||
|
||||
r0 = openmc.ZCylinder(R=0.3)
|
||||
c11 = openmc.Cell(cell_id=11, fill=dense_fuel, region=-r0)
|
||||
c11.temperature = [500, 0, 700, 800]
|
||||
c12 = openmc.Cell(cell_id=12, fill=moderator, region=+r0)
|
||||
fuel_univ = openmc.Universe(universe_id=11, cells=(c11, c12))
|
||||
|
||||
lat = openmc.RectLattice(lattice_id=101)
|
||||
lat.dimension = [2, 2]
|
||||
lat.lower_left = [-2.0, -2.0]
|
||||
lat.pitch = [2.0, 2.0]
|
||||
lat.universes = [[fuel_univ]*2]*2
|
||||
lat.outer = mod_univ
|
||||
|
||||
x0 = openmc.XPlane(x0=-3.0)
|
||||
x1 = openmc.XPlane(x0=3.0)
|
||||
y0 = openmc.YPlane(y0=-3.0)
|
||||
y1 = openmc.YPlane(y0=3.0)
|
||||
for s in [x0, x1, y0, y1]:
|
||||
s.boundary_type = 'reflective'
|
||||
c101 = openmc.Cell(cell_id=101, fill=lat, region=+x0 & -x1 & +y0 & -y1)
|
||||
model.geometry.root_universe = openmc.Universe(universe_id=0, cells=(c101,))
|
||||
|
||||
# Settings
|
||||
model.settings.batches = 5
|
||||
model.settings.inactive = 0
|
||||
model.settings.particles = 1000
|
||||
model.settings.source = openmc.Source(space=openmc.stats.Box(
|
||||
[-1, -1, -1], [1, 1, 1]))
|
||||
model.settings.temperature = {'tolerance': 1000, 'multipole': True}
|
||||
|
||||
# Tallies
|
||||
tally = openmc.Tally()
|
||||
tally.nuclides = ['U235', 'O16', 'total']
|
||||
tally.scores = ['total', 'fission', '(n,gamma)', 'elastic', '(n,p)']
|
||||
model.tallies.append(tally)
|
||||
|
||||
return model
|
||||
|
||||
|
||||
class MultipoleTestHarness(PyAPITestHarness):
|
||||
def _build_inputs(self):
|
||||
####################
|
||||
# Materials
|
||||
####################
|
||||
|
||||
moderator = openmc.Material(material_id=1)
|
||||
moderator.set_density('g/cc', 1.0)
|
||||
moderator.add_nuclide('H1', 2.0)
|
||||
moderator.add_nuclide('O16', 1.0)
|
||||
moderator.add_s_alpha_beta('c_H_in_H2O')
|
||||
|
||||
dense_fuel = openmc.Material(material_id=2)
|
||||
dense_fuel.set_density('g/cc', 4.5)
|
||||
dense_fuel.add_nuclide('U235', 1.0)
|
||||
|
||||
mats_file = openmc.Materials([moderator, dense_fuel])
|
||||
mats_file.export_to_xml()
|
||||
|
||||
####################
|
||||
# Geometry
|
||||
####################
|
||||
|
||||
c1 = openmc.Cell(cell_id=1, fill=moderator)
|
||||
mod_univ = openmc.Universe(universe_id=1, cells=(c1,))
|
||||
|
||||
r0 = openmc.ZCylinder(R=0.3)
|
||||
c11 = openmc.Cell(cell_id=11, fill=dense_fuel, region=-r0)
|
||||
c11.temperature = [500, 0, 700, 800]
|
||||
c12 = openmc.Cell(cell_id=12, fill=moderator, region=+r0)
|
||||
fuel_univ = openmc.Universe(universe_id=11, cells=(c11, c12))
|
||||
|
||||
lat = openmc.RectLattice(lattice_id=101)
|
||||
lat.dimension = [2, 2]
|
||||
lat.lower_left = [-2.0, -2.0]
|
||||
lat.pitch = [2.0, 2.0]
|
||||
lat.universes = [[fuel_univ]*2]*2
|
||||
lat.outer = mod_univ
|
||||
|
||||
x0 = openmc.XPlane(x0=-3.0)
|
||||
x1 = openmc.XPlane(x0=3.0)
|
||||
y0 = openmc.YPlane(y0=-3.0)
|
||||
y1 = openmc.YPlane(y0=3.0)
|
||||
for s in [x0, x1, y0, y1]:
|
||||
s.boundary_type = 'reflective'
|
||||
c101 = openmc.Cell(cell_id=101, fill=lat, region=+x0 & -x1 & +y0 & -y1)
|
||||
root_univ = openmc.Universe(universe_id=0, cells=(c101,))
|
||||
|
||||
geometry = openmc.Geometry(root_univ)
|
||||
geometry.export_to_xml()
|
||||
|
||||
####################
|
||||
# Settings
|
||||
####################
|
||||
|
||||
sets_file = openmc.Settings()
|
||||
sets_file.batches = 5
|
||||
sets_file.inactive = 0
|
||||
sets_file.particles = 1000
|
||||
sets_file.source = Source(space=Box([-1, -1, -1], [1, 1, 1]))
|
||||
sets_file.output = {'summary': True}
|
||||
sets_file.temperature = {'tolerance': 1000, 'multipole': True}
|
||||
sets_file.export_to_xml()
|
||||
|
||||
####################
|
||||
# Plots
|
||||
####################
|
||||
|
||||
plots_file = openmc.Plots()
|
||||
|
||||
plot = openmc.Plot(plot_id=1)
|
||||
plot.basis = 'xy'
|
||||
plot.color_by = 'cell'
|
||||
plot.filename = 'cellplot'
|
||||
plot.origin = (0, 0, 0)
|
||||
plot.width = (7, 7)
|
||||
plot.pixels = (400, 400)
|
||||
plots_file.append(plot)
|
||||
|
||||
plot = openmc.Plot(plot_id=2)
|
||||
plot.basis = 'xy'
|
||||
plot.color_by = 'material'
|
||||
plot.filename = 'matplot'
|
||||
plot.origin = (0, 0, 0)
|
||||
plot.width = (7, 7)
|
||||
plot.pixels = (400, 400)
|
||||
plots_file.append(plot)
|
||||
|
||||
plots_file.export_to_xml()
|
||||
|
||||
def execute_test(self):
|
||||
if not 'OPENMC_MULTIPOLE_LIBRARY' in os.environ:
|
||||
raise RuntimeError("The 'OPENMC_MULTIPOLE_LIBRARY' environment "
|
||||
|
|
@ -110,13 +80,8 @@ class MultipoleTestHarness(PyAPITestHarness):
|
|||
outstr += str(su.geometry.get_all_cells()[11])
|
||||
return outstr
|
||||
|
||||
def _cleanup(self):
|
||||
f = os.path.join(os.getcwd(), 'plots.xml')
|
||||
if os.path.exists(f):
|
||||
os.remove(f)
|
||||
super(MultipoleTestHarness, self)._cleanup()
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = MultipoleTestHarness('statepoint.5.h5')
|
||||
model = make_model()
|
||||
harness = MultipoleTestHarness('statepoint.5.h5', model)
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -29,5 +29,5 @@ class OutputTestHarness(TestHarness):
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = OutputTestHarness('statepoint.10.*')
|
||||
harness = OutputTestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -15,7 +15,7 @@ import openmc
|
|||
class PlotTestHarness(TestHarness):
|
||||
"""Specialized TestHarness for running OpenMC plotting tests."""
|
||||
def __init__(self, plot_names):
|
||||
super(PlotTestHarness, self).__init__(None, False)
|
||||
super(PlotTestHarness, self).__init__(None)
|
||||
self._plot_names = plot_names
|
||||
|
||||
def _run_openmc(self):
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*')
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*')
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*')
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -25,23 +25,10 @@
|
|||
</space>
|
||||
</source>
|
||||
<resonance_scattering>
|
||||
<scatterer>
|
||||
<nuclide>U238</nuclide>
|
||||
<method>DBRC</method>
|
||||
<E_min>1.0</E_min>
|
||||
<E_max>210.0</E_max>
|
||||
</scatterer>
|
||||
<scatterer>
|
||||
<nuclide>U235</nuclide>
|
||||
<method>WCM</method>
|
||||
<E_min>1.0</E_min>
|
||||
<E_max>210.0</E_max>
|
||||
</scatterer>
|
||||
<scatterer>
|
||||
<nuclide>Pu239</nuclide>
|
||||
<method>ARES</method>
|
||||
<E_min>1.0</E_min>
|
||||
<E_max>210.0</E_max>
|
||||
</scatterer>
|
||||
<enable>true</enable>
|
||||
<method>ares</method>
|
||||
<energy_min>1.0</energy_min>
|
||||
<energy_max>210.0</energy_max>
|
||||
<nuclides>U238 U235 Pu239</nuclides>
|
||||
</resonance_scattering>
|
||||
</settings>
|
||||
|
|
|
|||
|
|
@ -1,2 +1,2 @@
|
|||
k-combined:
|
||||
1.440556E+00 6.383274E-02
|
||||
1.432684E+00 1.233834E-02
|
||||
|
|
|
|||
|
|
@ -9,54 +9,43 @@ import openmc
|
|||
|
||||
class ResonanceScatteringTestHarness(PyAPITestHarness):
|
||||
def _build_inputs(self):
|
||||
# Nuclides
|
||||
u238 = openmc.Nuclide('U238')
|
||||
u235 = openmc.Nuclide('U235')
|
||||
pu239 = openmc.Nuclide('Pu239')
|
||||
h1 = openmc.Nuclide('H1')
|
||||
|
||||
# Materials
|
||||
mat = openmc.Material(material_id=1)
|
||||
mat.set_density('g/cc', 1.0)
|
||||
mat.add_nuclide(u238, 1.0)
|
||||
mat.add_nuclide(u235, 0.02)
|
||||
mat.add_nuclide(pu239, 0.02)
|
||||
mat.add_nuclide(h1, 20.0)
|
||||
mat.add_nuclide('U238', 1.0)
|
||||
mat.add_nuclide('U235', 0.02)
|
||||
mat.add_nuclide('Pu239', 0.02)
|
||||
mat.add_nuclide('H1', 20.0)
|
||||
|
||||
mats_file = openmc.Materials([mat])
|
||||
mats_file.export_to_xml()
|
||||
|
||||
# Geometry
|
||||
dumb_surface = openmc.XPlane(x0=100)
|
||||
dumb_surface.boundary_type = 'reflective'
|
||||
|
||||
c1 = openmc.Cell(cell_id=1)
|
||||
c1.fill = mat
|
||||
c1.region = -dumb_surface
|
||||
|
||||
root_univ = openmc.Universe(universe_id=0)
|
||||
root_univ.add_cell(c1)
|
||||
|
||||
geometry = openmc.Geometry()
|
||||
geometry.root_universe = root_univ
|
||||
dumb_surface = openmc.XPlane(x0=100, boundary_type='reflective')
|
||||
c1 = openmc.Cell(cell_id=1, fill=mat, region=-dumb_surface)
|
||||
root_univ = openmc.Universe(universe_id=0, cells=[c1])
|
||||
geometry = openmc.Geometry(root_univ)
|
||||
geometry.export_to_xml()
|
||||
|
||||
# Settings
|
||||
res_scatt_dbrc = openmc.ResonanceScattering(u238, 'DBRC', 1.0, 210.0)
|
||||
res_scatt_wcm = openmc.ResonanceScattering(u235, 'WCM', 1.0, 210.0)
|
||||
res_scatt_ares = openmc.ResonanceScattering(pu239, 'ARES', 1.0, 210.0)
|
||||
# Resonance elastic scattering settings
|
||||
res_scat_settings = {
|
||||
'enable': True,
|
||||
'energy_min': 1.0,
|
||||
'energy_max': 210.0,
|
||||
'method': 'ares',
|
||||
'nuclides': ['U238', 'U235', 'Pu239']
|
||||
}
|
||||
|
||||
sets_file = openmc.Settings()
|
||||
sets_file.batches = 10
|
||||
sets_file.inactive = 5
|
||||
sets_file.particles = 1000
|
||||
sets_file.source = openmc.source.Source(
|
||||
settings = openmc.Settings()
|
||||
settings.batches = 10
|
||||
settings.inactive = 5
|
||||
settings.particles = 1000
|
||||
settings.source = openmc.source.Source(
|
||||
space=openmc.stats.Box([-4, -4, -4], [4, 4, 4]))
|
||||
sets_file.resonance_scattering = [res_scatt_dbrc, res_scatt_wcm,
|
||||
res_scatt_ares]
|
||||
sets_file.export_to_xml()
|
||||
settings.resonance_scattering = res_scat_settings
|
||||
settings.export_to_xml()
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = ResonanceScatteringTestHarness('statepoint.10.*')
|
||||
harness = ResonanceScatteringTestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*')
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*')
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import HashedTestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = HashedTestHarness('statepoint.10.*', True)
|
||||
harness = HashedTestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*')
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -98,5 +98,5 @@ class SourceFileTestHarness(TestHarness):
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = SourceFileTestHarness('statepoint.10.*')
|
||||
harness = SourceFileTestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -5,7 +5,7 @@ import os
|
|||
import sys
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import TestHarness
|
||||
from openmc.statepoint import StatePoint
|
||||
from openmc import StatePoint
|
||||
|
||||
|
||||
class SourcepointTestHarness(TestHarness):
|
||||
|
|
@ -18,21 +18,20 @@ class SourcepointTestHarness(TestHarness):
|
|||
|
||||
def _get_results(self):
|
||||
"""Digest info in the statepoint and return as a string."""
|
||||
# Read the statepoint file.
|
||||
statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0]
|
||||
sp = StatePoint(statepoint)
|
||||
|
||||
# Get the eigenvalue information.
|
||||
outstr = TestHarness._get_results(self)
|
||||
|
||||
# Add the source information.
|
||||
xyz = sp.source[0]['xyz']
|
||||
outstr += ' '.join(['{0:12.6E}'.format(x) for x in xyz])
|
||||
outstr += "\n"
|
||||
# Read the statepoint file.
|
||||
statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0]
|
||||
with StatePoint(statepoint) as sp:
|
||||
# Add the source information.
|
||||
xyz = sp.source[0]['xyz']
|
||||
outstr += ' '.join(['{0:12.6E}'.format(x) for x in xyz])
|
||||
outstr += "\n"
|
||||
|
||||
return outstr
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = SourcepointTestHarness('statepoint.08.*')
|
||||
harness = SourcepointTestHarness('statepoint.08.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -18,5 +18,5 @@ class SourcepointTestHarness(TestHarness):
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*')
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*', True)
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -1,4 +1,4 @@
|
|||
#!/usr/bin/env python
|
||||
#!/usr/bin/env python
|
||||
|
||||
import os
|
||||
import sys
|
||||
|
|
@ -8,11 +8,11 @@ from testing_harness import TestHarness
|
|||
|
||||
class StatepointTestHarness(TestHarness):
|
||||
def __init__(self):
|
||||
super(StatepointTestHarness, self).__init__(None, False)
|
||||
super(StatepointTestHarness, self).__init__(None)
|
||||
|
||||
def _test_output_created(self):
|
||||
"""Make sure statepoint files have been created."""
|
||||
sps = ('statepoint.03.*', 'statepoint.06.*', 'statepoint.09.*')
|
||||
sps = ('statepoint.03.h5', 'statepoint.06.h5', 'statepoint.09.h5')
|
||||
for sp in sps:
|
||||
self._sp_name = sp
|
||||
TestHarness._test_output_created(self)
|
||||
|
|
|
|||
|
|
@ -9,9 +9,8 @@ import openmc
|
|||
|
||||
|
||||
class StatepointRestartTestHarness(TestHarness):
|
||||
def __init__(self, final_sp, restart_sp, tallies_present=False):
|
||||
super(StatepointRestartTestHarness, self).__init__(final_sp,
|
||||
tallies_present)
|
||||
def __init__(self, final_sp, restart_sp):
|
||||
super(StatepointRestartTestHarness, self).__init__(final_sp)
|
||||
self._restart_sp = restart_sp
|
||||
|
||||
def execute_test(self):
|
||||
|
|
@ -63,5 +62,5 @@ class StatepointRestartTestHarness(TestHarness):
|
|||
|
||||
if __name__ == '__main__':
|
||||
harness = StatepointRestartTestHarness('statepoint.10.h5',
|
||||
'statepoint.07.h5', True)
|
||||
'statepoint.07.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -26,5 +26,5 @@ class SourcepointTestHarness(TestHarness):
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = SourcepointTestHarness('statepoint.10.*')
|
||||
harness = SourcepointTestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*', True)
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -148,7 +148,7 @@
|
|||
</geometry>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<materials>
|
||||
<material id="1" name="Fuel">
|
||||
<material id="1" name="UOX fuel">
|
||||
<density units="g/cm3" value="10.062" />
|
||||
<nuclide ao="4.9476e-06" name="U234" />
|
||||
<nuclide ao="0.00048218" name="U235" />
|
||||
|
|
@ -197,7 +197,7 @@
|
|||
<nuclide name="Zr96" wo="0.0216912612" />
|
||||
<sab name="c_H_in_H2O" />
|
||||
</material>
|
||||
<material id="2" name="Cladding">
|
||||
<material id="2" name="Zircaloy">
|
||||
<density units="g/cm3" value="5.77" />
|
||||
<nuclide ao="0.5145" name="Zr90" />
|
||||
<nuclide ao="0.1122" name="Zr91" />
|
||||
|
|
@ -249,7 +249,7 @@
|
|||
<nuclide name="Cr52" wo="0.145407678031" />
|
||||
<sab name="c_H_in_H2O" />
|
||||
</material>
|
||||
<material id="7" name="Upper radial reflector /Top plate region">
|
||||
<material id="7" name="Upper radial reflector / Top plate region">
|
||||
<density units="g/cm3" value="4.28" />
|
||||
<nuclide name="H1" wo="0.0086117" />
|
||||
<nuclide name="O16" wo="0.0683369" />
|
||||
|
|
|
|||
|
|
@ -4,180 +4,179 @@ import os
|
|||
import sys
|
||||
sys.path.insert(0, os.pardir)
|
||||
|
||||
from testing_harness import PyAPITestHarness
|
||||
from testing_harness import HashedPyAPITestHarness
|
||||
from openmc.filter import *
|
||||
from openmc import Mesh, Tally, Tallies
|
||||
from openmc.source import Source
|
||||
from openmc.stats import Box
|
||||
|
||||
|
||||
class TalliesTestHarness(PyAPITestHarness):
|
||||
def _build_inputs(self):
|
||||
# Build default materials/geometry
|
||||
self._input_set.build_default_materials_and_geometry()
|
||||
|
||||
# Set settings explicitly
|
||||
self._input_set.settings.batches = 5
|
||||
self._input_set.settings.inactive = 0
|
||||
self._input_set.settings.particles = 400
|
||||
self._input_set.settings.source = Source(space=Box(
|
||||
[-160, -160, -183], [160, 160, 183]))
|
||||
|
||||
azimuthal_bins = (-3.14159, -1.8850, -0.6283, 0.6283, 1.8850, 3.14159)
|
||||
azimuthal_filter = AzimuthalFilter(azimuthal_bins)
|
||||
azimuthal_tally1 = Tally()
|
||||
azimuthal_tally1.filters = [azimuthal_filter]
|
||||
azimuthal_tally1.scores = ['flux']
|
||||
azimuthal_tally1.estimator = 'tracklength'
|
||||
|
||||
azimuthal_tally2 = Tally()
|
||||
azimuthal_tally2.filters = [azimuthal_filter]
|
||||
azimuthal_tally2.scores = ['flux']
|
||||
azimuthal_tally2.estimator = 'analog'
|
||||
|
||||
mesh_2x2 = Mesh(mesh_id=1)
|
||||
mesh_2x2.lower_left = [-182.07, -182.07]
|
||||
mesh_2x2.upper_right = [182.07, 182.07]
|
||||
mesh_2x2.dimension = [2, 2]
|
||||
mesh_filter = MeshFilter(mesh_2x2)
|
||||
azimuthal_tally3 = Tally()
|
||||
azimuthal_tally3.filters = [azimuthal_filter, mesh_filter]
|
||||
azimuthal_tally3.scores = ['flux']
|
||||
azimuthal_tally3.estimator = 'tracklength'
|
||||
|
||||
cellborn_tally = Tally()
|
||||
cellborn_tally.filters = [CellbornFilter((10, 21, 22, 23))]
|
||||
cellborn_tally.scores = ['total']
|
||||
|
||||
dg_tally = Tally()
|
||||
dg_tally.filters = [DelayedGroupFilter((1, 2, 3, 4, 5, 6))]
|
||||
dg_tally.scores = ['delayed-nu-fission']
|
||||
|
||||
four_groups = (0.0, 0.253, 1.0e3, 1.0e6, 20.0e6)
|
||||
energy_filter = EnergyFilter(four_groups)
|
||||
energy_tally = Tally()
|
||||
energy_tally.filters = [energy_filter]
|
||||
energy_tally.scores = ['total']
|
||||
|
||||
energyout_filter = EnergyoutFilter(four_groups)
|
||||
energyout_tally = Tally()
|
||||
energyout_tally.filters = [energyout_filter]
|
||||
energyout_tally.scores = ['scatter']
|
||||
|
||||
transfer_tally = Tally()
|
||||
transfer_tally.filters = [energy_filter, energyout_filter]
|
||||
transfer_tally.scores = ['scatter', 'nu-fission']
|
||||
|
||||
material_tally = Tally()
|
||||
material_tally.filters = [MaterialFilter((1, 2, 3, 4))]
|
||||
material_tally.scores = ['total']
|
||||
|
||||
mu_bins = (-1.0, -0.5, 0.0, 0.5, 1.0)
|
||||
mu_filter = MuFilter(mu_bins)
|
||||
mu_tally1 = Tally()
|
||||
mu_tally1.filters = [mu_filter]
|
||||
mu_tally1.scores = ['scatter', 'nu-scatter']
|
||||
|
||||
mu_tally2 = Tally()
|
||||
mu_tally2.filters = [mu_filter, mesh_filter]
|
||||
mu_tally2.scores = ['scatter', 'nu-scatter']
|
||||
|
||||
polar_bins = (0.0, 0.6283, 1.2566, 1.8850, 2.5132, 3.14159)
|
||||
polar_filter = PolarFilter(polar_bins)
|
||||
polar_tally1 = Tally()
|
||||
polar_tally1.filters = [polar_filter]
|
||||
polar_tally1.scores = ['flux']
|
||||
polar_tally1.estimator = 'tracklength'
|
||||
|
||||
polar_tally2 = Tally()
|
||||
polar_tally2.filters = [polar_filter]
|
||||
polar_tally2.scores = ['flux']
|
||||
polar_tally2.estimator = 'analog'
|
||||
|
||||
polar_tally3 = Tally()
|
||||
polar_tally3.filters = [polar_filter, mesh_filter]
|
||||
polar_tally3.scores = ['flux']
|
||||
polar_tally3.estimator = 'tracklength'
|
||||
|
||||
universe_tally = Tally()
|
||||
universe_tally.filters = [UniverseFilter((1, 2, 3, 4, 6, 8))]
|
||||
universe_tally.scores = ['total']
|
||||
|
||||
cell_filter = CellFilter((10, 21, 22, 23, 60))
|
||||
score_tallies = [Tally(), Tally(), Tally()]
|
||||
for t in score_tallies:
|
||||
t.filters = [cell_filter]
|
||||
t.scores = ['absorption', 'delayed-nu-fission', 'events', 'fission',
|
||||
'inverse-velocity', 'kappa-fission', '(n,2n)', '(n,n1)',
|
||||
'(n,gamma)', 'nu-fission', 'scatter', 'elastic',
|
||||
'total', 'prompt-nu-fission', 'fission-q-prompt',
|
||||
'fission-q-recoverable']
|
||||
score_tallies[0].estimator = 'tracklength'
|
||||
score_tallies[1].estimator = 'analog'
|
||||
score_tallies[2].estimator = 'collision'
|
||||
|
||||
cell_filter2 = CellFilter((21, 22, 23, 27, 28, 29, 60))
|
||||
flux_tallies = [Tally() for i in range(4)]
|
||||
for t in flux_tallies:
|
||||
t.filters = [cell_filter2]
|
||||
flux_tallies[0].scores = ['flux']
|
||||
for t in flux_tallies[1:]:
|
||||
t.scores = ['flux-y5']
|
||||
flux_tallies[1].estimator = 'tracklength'
|
||||
flux_tallies[2].estimator = 'analog'
|
||||
flux_tallies[3].estimator = 'collision'
|
||||
|
||||
scatter_tally1 = Tally()
|
||||
scatter_tally1.filters = [cell_filter]
|
||||
scatter_tally1.scores = ['scatter', 'scatter-1', 'scatter-2', 'scatter-3',
|
||||
'scatter-4', 'nu-scatter', 'nu-scatter-1',
|
||||
'nu-scatter-2', 'nu-scatter-3', 'nu-scatter-4']
|
||||
|
||||
scatter_tally2 = Tally()
|
||||
scatter_tally2.filters = [cell_filter]
|
||||
scatter_tally2.scores = ['scatter-p4', 'scatter-y4', 'nu-scatter-p4',
|
||||
'nu-scatter-y3']
|
||||
|
||||
total_tallies = [Tally() for i in range(4)]
|
||||
for t in total_tallies:
|
||||
t.filters = [cell_filter]
|
||||
total_tallies[0].scores = ['total']
|
||||
for t in total_tallies[1:]:
|
||||
t.scores = ['total-y4']
|
||||
t.nuclides = ['U235', 'total']
|
||||
total_tallies[1].estimator = 'tracklength'
|
||||
total_tallies[2].estimator = 'analog'
|
||||
total_tallies[3].estimator = 'collision'
|
||||
|
||||
all_nuclide_tallies = [Tally() for i in range(4)]
|
||||
for t in all_nuclide_tallies:
|
||||
t.filters = [cell_filter]
|
||||
t.estimator = 'tracklength'
|
||||
t.nuclides = ['all']
|
||||
t.scores = ['total']
|
||||
all_nuclide_tallies[1].estimator = 'collision'
|
||||
all_nuclide_tallies[2].filters = [mesh_filter]
|
||||
all_nuclide_tallies[3].filters = [mesh_filter]
|
||||
all_nuclide_tallies[3].nuclides = ['U235']
|
||||
|
||||
self._input_set.tallies = Tallies()
|
||||
self._input_set.tallies += (
|
||||
[azimuthal_tally1, azimuthal_tally2, azimuthal_tally3,
|
||||
cellborn_tally, dg_tally, energy_tally, energyout_tally,
|
||||
transfer_tally, material_tally, mu_tally1, mu_tally2,
|
||||
polar_tally1, polar_tally2, polar_tally3, universe_tally])
|
||||
self._input_set.tallies += score_tallies
|
||||
self._input_set.tallies += flux_tallies
|
||||
self._input_set.tallies += (scatter_tally1, scatter_tally2)
|
||||
self._input_set.tallies += total_tallies
|
||||
self._input_set.tallies += all_nuclide_tallies
|
||||
|
||||
self._input_set.export()
|
||||
|
||||
def _get_results(self):
|
||||
return super(TalliesTestHarness, self)._get_results(hash_output=True)
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TalliesTestHarness('statepoint.5.h5', True)
|
||||
harness = HashedPyAPITestHarness('statepoint.5.h5')
|
||||
model = harness._model
|
||||
|
||||
# Set settings explicitly
|
||||
model.settings.batches = 5
|
||||
model.settings.inactive = 0
|
||||
model.settings.particles = 400
|
||||
model.settings.source = openmc.Source(space=openmc.stats.Box(
|
||||
[-160, -160, -183], [160, 160, 183]))
|
||||
|
||||
azimuthal_bins = (-3.14159, -1.8850, -0.6283, 0.6283, 1.8850, 3.14159)
|
||||
azimuthal_filter = AzimuthalFilter(azimuthal_bins)
|
||||
azimuthal_tally1 = Tally()
|
||||
azimuthal_tally1.filters = [azimuthal_filter]
|
||||
azimuthal_tally1.scores = ['flux']
|
||||
azimuthal_tally1.estimator = 'tracklength'
|
||||
|
||||
azimuthal_tally2 = Tally()
|
||||
azimuthal_tally2.filters = [azimuthal_filter]
|
||||
azimuthal_tally2.scores = ['flux']
|
||||
azimuthal_tally2.estimator = 'analog'
|
||||
|
||||
mesh_2x2 = Mesh(mesh_id=1)
|
||||
mesh_2x2.lower_left = [-182.07, -182.07]
|
||||
mesh_2x2.upper_right = [182.07, 182.07]
|
||||
mesh_2x2.dimension = [2, 2]
|
||||
mesh_filter = MeshFilter(mesh_2x2)
|
||||
azimuthal_tally3 = Tally()
|
||||
azimuthal_tally3.filters = [azimuthal_filter, mesh_filter]
|
||||
azimuthal_tally3.scores = ['flux']
|
||||
azimuthal_tally3.estimator = 'tracklength'
|
||||
|
||||
cellborn_tally = Tally()
|
||||
cellborn_tally.filters = [
|
||||
CellbornFilter((model.geometry.get_all_cells()[10],
|
||||
model.geometry.get_all_cells()[21],
|
||||
22, 23))] # Test both Cell objects and ids
|
||||
cellborn_tally.scores = ['total']
|
||||
|
||||
dg_tally = Tally()
|
||||
dg_tally.filters = [DelayedGroupFilter((1, 2, 3, 4, 5, 6))]
|
||||
dg_tally.scores = ['delayed-nu-fission']
|
||||
|
||||
four_groups = (0.0, 0.253, 1.0e3, 1.0e6, 20.0e6)
|
||||
energy_filter = EnergyFilter(four_groups)
|
||||
energy_tally = Tally()
|
||||
energy_tally.filters = [energy_filter]
|
||||
energy_tally.scores = ['total']
|
||||
|
||||
energyout_filter = EnergyoutFilter(four_groups)
|
||||
energyout_tally = Tally()
|
||||
energyout_tally.filters = [energyout_filter]
|
||||
energyout_tally.scores = ['scatter']
|
||||
|
||||
transfer_tally = Tally()
|
||||
transfer_tally.filters = [energy_filter, energyout_filter]
|
||||
transfer_tally.scores = ['scatter', 'nu-fission']
|
||||
|
||||
material_tally = Tally()
|
||||
material_tally.filters = [
|
||||
MaterialFilter((model.geometry.get_materials_by_name('UOX fuel')[0],
|
||||
model.geometry.get_materials_by_name('Zircaloy')[0],
|
||||
3, 4))] # Test both Material objects and ids
|
||||
material_tally.scores = ['total']
|
||||
|
||||
mu_bins = (-1.0, -0.5, 0.0, 0.5, 1.0)
|
||||
mu_filter = MuFilter(mu_bins)
|
||||
mu_tally1 = Tally()
|
||||
mu_tally1.filters = [mu_filter]
|
||||
mu_tally1.scores = ['scatter', 'nu-scatter']
|
||||
|
||||
mu_tally2 = Tally()
|
||||
mu_tally2.filters = [mu_filter, mesh_filter]
|
||||
mu_tally2.scores = ['scatter', 'nu-scatter']
|
||||
|
||||
polar_bins = (0.0, 0.6283, 1.2566, 1.8850, 2.5132, 3.14159)
|
||||
polar_filter = PolarFilter(polar_bins)
|
||||
polar_tally1 = Tally()
|
||||
polar_tally1.filters = [polar_filter]
|
||||
polar_tally1.scores = ['flux']
|
||||
polar_tally1.estimator = 'tracklength'
|
||||
|
||||
polar_tally2 = Tally()
|
||||
polar_tally2.filters = [polar_filter]
|
||||
polar_tally2.scores = ['flux']
|
||||
polar_tally2.estimator = 'analog'
|
||||
|
||||
polar_tally3 = Tally()
|
||||
polar_tally3.filters = [polar_filter, mesh_filter]
|
||||
polar_tally3.scores = ['flux']
|
||||
polar_tally3.estimator = 'tracklength'
|
||||
|
||||
universe_tally = Tally()
|
||||
universe_tally.filters = [
|
||||
UniverseFilter((model.geometry.get_all_universes()[1],
|
||||
model.geometry.get_all_universes()[2],
|
||||
3, 4, 6, 8))] # Test both Universe objects and ids
|
||||
universe_tally.scores = ['total']
|
||||
|
||||
cell_filter = CellFilter((model.geometry.get_all_cells()[10],
|
||||
model.geometry.get_all_cells()[21],
|
||||
22, 23, 60)) # Test both Cell objects and ids
|
||||
score_tallies = [Tally(), Tally(), Tally()]
|
||||
for t in score_tallies:
|
||||
t.filters = [cell_filter]
|
||||
t.scores = ['absorption', 'delayed-nu-fission', 'events', 'fission',
|
||||
'inverse-velocity', 'kappa-fission', '(n,2n)', '(n,n1)',
|
||||
'(n,gamma)', 'nu-fission', 'scatter', 'elastic',
|
||||
'total', 'prompt-nu-fission', 'fission-q-prompt',
|
||||
'fission-q-recoverable']
|
||||
score_tallies[0].estimator = 'tracklength'
|
||||
score_tallies[1].estimator = 'analog'
|
||||
score_tallies[2].estimator = 'collision'
|
||||
|
||||
cell_filter2 = CellFilter((21, 22, 23, 27, 28, 29, 60))
|
||||
flux_tallies = [Tally() for i in range(4)]
|
||||
for t in flux_tallies:
|
||||
t.filters = [cell_filter2]
|
||||
flux_tallies[0].scores = ['flux']
|
||||
for t in flux_tallies[1:]:
|
||||
t.scores = ['flux-y5']
|
||||
flux_tallies[1].estimator = 'tracklength'
|
||||
flux_tallies[2].estimator = 'analog'
|
||||
flux_tallies[3].estimator = 'collision'
|
||||
|
||||
scatter_tally1 = Tally()
|
||||
scatter_tally1.filters = [cell_filter]
|
||||
scatter_tally1.scores = ['scatter', 'scatter-1', 'scatter-2', 'scatter-3',
|
||||
'scatter-4', 'nu-scatter', 'nu-scatter-1',
|
||||
'nu-scatter-2', 'nu-scatter-3', 'nu-scatter-4']
|
||||
|
||||
scatter_tally2 = Tally()
|
||||
scatter_tally2.filters = [cell_filter]
|
||||
scatter_tally2.scores = ['scatter-p4', 'scatter-y4', 'nu-scatter-p4',
|
||||
'nu-scatter-y3']
|
||||
|
||||
total_tallies = [Tally() for i in range(4)]
|
||||
for t in total_tallies:
|
||||
t.filters = [cell_filter]
|
||||
total_tallies[0].scores = ['total']
|
||||
for t in total_tallies[1:]:
|
||||
t.scores = ['total-y4']
|
||||
t.nuclides = ['U235', 'total']
|
||||
total_tallies[1].estimator = 'tracklength'
|
||||
total_tallies[2].estimator = 'analog'
|
||||
total_tallies[3].estimator = 'collision'
|
||||
|
||||
all_nuclide_tallies = [Tally() for i in range(4)]
|
||||
for t in all_nuclide_tallies:
|
||||
t.filters = [cell_filter]
|
||||
t.estimator = 'tracklength'
|
||||
t.nuclides = ['all']
|
||||
t.scores = ['total']
|
||||
all_nuclide_tallies[1].estimator = 'collision'
|
||||
all_nuclide_tallies[2].filters = [mesh_filter]
|
||||
all_nuclide_tallies[3].filters = [mesh_filter]
|
||||
all_nuclide_tallies[3].nuclides = ['U235']
|
||||
|
||||
model.tallies += [
|
||||
azimuthal_tally1, azimuthal_tally2, azimuthal_tally3,
|
||||
cellborn_tally, dg_tally, energy_tally, energyout_tally,
|
||||
transfer_tally, material_tally, mu_tally1, mu_tally2,
|
||||
polar_tally1, polar_tally2, polar_tally3, universe_tally]
|
||||
model.tallies += score_tallies
|
||||
model.tallies += flux_tallies
|
||||
model.tallies += (scatter_tally1, scatter_tally2)
|
||||
model.tallies += total_tallies
|
||||
model.tallies += all_nuclide_tallies
|
||||
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -148,7 +148,7 @@
|
|||
</geometry>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<materials>
|
||||
<material id="1" name="Fuel">
|
||||
<material id="1" name="UOX fuel">
|
||||
<density units="g/cm3" value="10.062" />
|
||||
<nuclide ao="4.9476e-06" name="U234" />
|
||||
<nuclide ao="0.00048218" name="U235" />
|
||||
|
|
@ -197,7 +197,7 @@
|
|||
<nuclide name="Zr96" wo="0.0216912612" />
|
||||
<sab name="c_H_in_H2O" />
|
||||
</material>
|
||||
<material id="2" name="Cladding">
|
||||
<material id="2" name="Zircaloy">
|
||||
<density units="g/cm3" value="5.77" />
|
||||
<nuclide ao="0.5145" name="Zr90" />
|
||||
<nuclide ao="0.1122" name="Zr91" />
|
||||
|
|
@ -249,7 +249,7 @@
|
|||
<nuclide name="Cr52" wo="0.145407678031" />
|
||||
<sab name="c_H_in_H2O" />
|
||||
</material>
|
||||
<material id="7" name="Upper radial reflector /Top plate region">
|
||||
<material id="7" name="Upper radial reflector / Top plate region">
|
||||
<density units="g/cm3" value="4.28" />
|
||||
<nuclide name="H1" wo="0.0086117" />
|
||||
<nuclide name="O16" wo="0.0683369" />
|
||||
|
|
@ -306,9 +306,6 @@
|
|||
<parameters>-160 -160 -183 160 160 183</parameters>
|
||||
</space>
|
||||
</source>
|
||||
<output>
|
||||
<summary>true</summary>
|
||||
</output>
|
||||
</settings>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<tallies>
|
||||
|
|
|
|||
|
|
@ -10,15 +10,8 @@ import openmc
|
|||
|
||||
|
||||
class TallyAggregationTestHarness(PyAPITestHarness):
|
||||
def _build_inputs(self):
|
||||
|
||||
# The summary.h5 file needs to be created to read in the tallies
|
||||
self._input_set.settings.output = {'summary': True}
|
||||
|
||||
# Initialize the nuclides
|
||||
u234 = openmc.Nuclide('U234')
|
||||
u235 = openmc.Nuclide('U235')
|
||||
u238 = openmc.Nuclide('U238')
|
||||
def __init__(self, *args, **kwargs):
|
||||
super(TallyAggregationTestHarness, self).__init__(*args, **kwargs)
|
||||
|
||||
# Initialize the filters
|
||||
energy_filter = openmc.EnergyFilter([0.0, 0.253, 1.0e3, 1.0e6, 20.0e6])
|
||||
|
|
@ -28,12 +21,8 @@ class TallyAggregationTestHarness(PyAPITestHarness):
|
|||
tally = openmc.Tally(name='distribcell tally')
|
||||
tally.filters = [energy_filter, distrib_filter]
|
||||
tally.scores = ['nu-fission', 'total']
|
||||
tally.nuclides = [u234, u235, u238]
|
||||
tallies_file = openmc.Tallies([tally])
|
||||
|
||||
# Export tallies to file
|
||||
self._input_set.tallies = tallies_file
|
||||
super(TallyAggregationTestHarness, self)._build_inputs()
|
||||
tally.nuclides = ['U234', 'U235', 'U238']
|
||||
self._model.tallies.append(tally)
|
||||
|
||||
def _get_results(self, hash_output=True):
|
||||
"""Digest info in the statepoint and return as a string."""
|
||||
|
|
@ -78,5 +67,5 @@ class TallyAggregationTestHarness(PyAPITestHarness):
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TallyAggregationTestHarness('statepoint.10.h5', True)
|
||||
harness = TallyAggregationTestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -148,7 +148,7 @@
|
|||
</geometry>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<materials>
|
||||
<material id="1" name="Fuel">
|
||||
<material id="1" name="UOX fuel">
|
||||
<density units="g/cm3" value="10.062" />
|
||||
<nuclide ao="4.9476e-06" name="U234" />
|
||||
<nuclide ao="0.00048218" name="U235" />
|
||||
|
|
@ -197,7 +197,7 @@
|
|||
<nuclide name="Zr96" wo="0.0216912612" />
|
||||
<sab name="c_H_in_H2O" />
|
||||
</material>
|
||||
<material id="2" name="Cladding">
|
||||
<material id="2" name="Zircaloy">
|
||||
<density units="g/cm3" value="5.77" />
|
||||
<nuclide ao="0.5145" name="Zr90" />
|
||||
<nuclide ao="0.1122" name="Zr91" />
|
||||
|
|
@ -249,7 +249,7 @@
|
|||
<nuclide name="Cr52" wo="0.145407678031" />
|
||||
<sab name="c_H_in_H2O" />
|
||||
</material>
|
||||
<material id="7" name="Upper radial reflector /Top plate region">
|
||||
<material id="7" name="Upper radial reflector / Top plate region">
|
||||
<density units="g/cm3" value="4.28" />
|
||||
<nuclide name="H1" wo="0.0086117" />
|
||||
<nuclide name="O16" wo="0.0683369" />
|
||||
|
|
@ -306,9 +306,6 @@
|
|||
<parameters>-160 -160 -183 160 160 183</parameters>
|
||||
</space>
|
||||
</source>
|
||||
<output>
|
||||
<summary>true</summary>
|
||||
</output>
|
||||
</settings>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<tallies>
|
||||
|
|
|
|||
|
|
@ -10,18 +10,8 @@ import openmc
|
|||
|
||||
|
||||
class TallyArithmeticTestHarness(PyAPITestHarness):
|
||||
def _build_inputs(self):
|
||||
|
||||
# The summary.h5 file needs to be created to read in the tallies
|
||||
self._input_set.settings.output = {'summary': True}
|
||||
|
||||
# Initialize the tallies file
|
||||
tallies_file = openmc.Tallies()
|
||||
|
||||
# Initialize the nuclides
|
||||
u234 = openmc.Nuclide('U234')
|
||||
u235 = openmc.Nuclide('U235')
|
||||
u238 = openmc.Nuclide('U238')
|
||||
def __init__(self, *args, **kwargs):
|
||||
super(TallyArithmeticTestHarness, self).__init__(*args, **kwargs)
|
||||
|
||||
# Initialize Mesh
|
||||
mesh = openmc.Mesh(mesh_id=1)
|
||||
|
|
@ -40,18 +30,14 @@ class TallyArithmeticTestHarness(PyAPITestHarness):
|
|||
tally = openmc.Tally(name='tally 1')
|
||||
tally.filters = [material_filter, energy_filter, distrib_filter]
|
||||
tally.scores = ['nu-fission', 'total']
|
||||
tally.nuclides = [u234, u235]
|
||||
tallies_file.append(tally)
|
||||
tally.nuclides = ['U234', 'U235']
|
||||
self._model.tallies.append(tally)
|
||||
|
||||
tally = openmc.Tally(name='tally 2')
|
||||
tally.filters = [energy_filter, mesh_filter]
|
||||
tally.scores = ['total', 'fission']
|
||||
tally.nuclides = [u238, u235]
|
||||
tallies_file.append(tally)
|
||||
|
||||
# Export tallies to file
|
||||
self._input_set.tallies = tallies_file
|
||||
super(TallyArithmeticTestHarness, self)._build_inputs()
|
||||
tally.nuclides = ['U238', 'U235']
|
||||
self._model.tallies.append(tally)
|
||||
|
||||
def _get_results(self, hash_output=False):
|
||||
"""Digest info in the statepoint and return as a string."""
|
||||
|
|
@ -95,5 +81,5 @@ class TallyArithmeticTestHarness(PyAPITestHarness):
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TallyArithmeticTestHarness('statepoint.10.h5', True)
|
||||
harness = TallyArithmeticTestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*', True)
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*', True)
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -148,7 +148,7 @@
|
|||
</geometry>
|
||||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<materials>
|
||||
<material id="1" name="Fuel">
|
||||
<material id="1" name="UOX fuel">
|
||||
<density units="g/cm3" value="10.062" />
|
||||
<nuclide ao="4.9476e-06" name="U234" />
|
||||
<nuclide ao="0.00048218" name="U235" />
|
||||
|
|
@ -197,7 +197,7 @@
|
|||
<nuclide name="Zr96" wo="0.0216912612" />
|
||||
<sab name="c_H_in_H2O" />
|
||||
</material>
|
||||
<material id="2" name="Cladding">
|
||||
<material id="2" name="Zircaloy">
|
||||
<density units="g/cm3" value="5.77" />
|
||||
<nuclide ao="0.5145" name="Zr90" />
|
||||
<nuclide ao="0.1122" name="Zr91" />
|
||||
|
|
@ -249,7 +249,7 @@
|
|||
<nuclide name="Cr52" wo="0.145407678031" />
|
||||
<sab name="c_H_in_H2O" />
|
||||
</material>
|
||||
<material id="7" name="Upper radial reflector /Top plate region">
|
||||
<material id="7" name="Upper radial reflector / Top plate region">
|
||||
<density units="g/cm3" value="4.28" />
|
||||
<nuclide name="H1" wo="0.0086117" />
|
||||
<nuclide name="O16" wo="0.0683369" />
|
||||
|
|
|
|||
|
|
@ -13,9 +13,8 @@ import openmc
|
|||
|
||||
|
||||
class TallySliceMergeTestHarness(PyAPITestHarness):
|
||||
def _build_inputs(self):
|
||||
# Initialize the tallies file
|
||||
tallies_file = openmc.Tallies()
|
||||
def __init__(self, *args, **kwargs):
|
||||
super(TallySliceMergeTestHarness, self).__init__(*args, **kwargs)
|
||||
|
||||
# Define nuclides and scores to add to both tallies
|
||||
self.nuclides = ['U235', 'U238']
|
||||
|
|
@ -49,10 +48,10 @@ class TallySliceMergeTestHarness(PyAPITestHarness):
|
|||
for score in self.scores:
|
||||
tally = openmc.Tally()
|
||||
tally.estimator = 'tracklength'
|
||||
tally.add_score(score)
|
||||
tally.add_nuclide(nuclide)
|
||||
tally.add_filter(cell_filter)
|
||||
tally.add_filter(energy_filter)
|
||||
tally.scores.append(score)
|
||||
tally.nuclides.append(nuclide)
|
||||
tally.filters.append(cell_filter)
|
||||
tally.filters.append(energy_filter)
|
||||
tallies.append(tally)
|
||||
|
||||
# Merge all cell tallies together
|
||||
|
|
@ -69,9 +68,9 @@ class TallySliceMergeTestHarness(PyAPITestHarness):
|
|||
distribcell_tally.estimator = 'tracklength'
|
||||
distribcell_tally.filters = [distribcell_filter, merged_energies]
|
||||
for score in self.scores:
|
||||
distribcell_tally.add_score(score)
|
||||
distribcell_tally.scores.append(score)
|
||||
for nuclide in self.nuclides:
|
||||
distribcell_tally.add_nuclide(nuclide)
|
||||
distribcell_tally.nuclides.append(nuclide)
|
||||
|
||||
mesh_tally = openmc.Tally(name='mesh tally')
|
||||
mesh_tally.estimator = 'tracklength'
|
||||
|
|
@ -80,12 +79,7 @@ class TallySliceMergeTestHarness(PyAPITestHarness):
|
|||
mesh_tally.nuclides = self.nuclides
|
||||
|
||||
# Add tallies to a Tallies object
|
||||
tallies_file = openmc.Tallies((tallies[0], distribcell_tally,
|
||||
mesh_tally))
|
||||
|
||||
# Export tallies to file
|
||||
self._input_set.tallies = tallies_file
|
||||
super(TallySliceMergeTestHarness, self)._build_inputs()
|
||||
self._model.tallies = [tallies[0], distribcell_tally, mesh_tally]
|
||||
|
||||
def _get_results(self, hash_output=False):
|
||||
"""Digest info in the statepoint and return as a string."""
|
||||
|
|
@ -178,5 +172,5 @@ class TallySliceMergeTestHarness(PyAPITestHarness):
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TallySliceMergeTestHarness('statepoint.10.h5', True)
|
||||
harness = TallySliceMergeTestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*')
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -14,32 +14,26 @@ class TrackTestHarness(TestHarness):
|
|||
"""Make sure statepoint.* and track* have been created."""
|
||||
TestHarness._test_output_created(self)
|
||||
|
||||
outputs = [glob.glob(''.join((os.getcwd(), '/track_1_1_1.*')))]
|
||||
outputs.append(glob.glob(''.join((os.getcwd(), '/track_1_1_2.*'))))
|
||||
for files in outputs:
|
||||
assert len(files) == 1, 'Multiple or no track files detected.'
|
||||
assert files[0].endswith('h5'),\
|
||||
'Track files are not HDF5 files'
|
||||
outputs = glob.glob('track_1_1_*.h5')
|
||||
assert len(outputs) == 2, 'Expected two track files.'
|
||||
|
||||
def _get_results(self):
|
||||
"""Digest info in the statepoint and return as a string."""
|
||||
# Run the track-to-vtk conversion script.
|
||||
call(['../../scripts/openmc-track-to-vtk', '-o', 'poly'] +
|
||||
glob.glob(''.join((os.getcwd(), '/track*'))))
|
||||
glob.glob('track_1_1_*.h5'))
|
||||
|
||||
# Make sure the vtk file was created then return it's contents.
|
||||
poly = os.path.join(os.getcwd(), 'poly.pvtp')
|
||||
assert os.path.isfile(poly), 'poly.pvtp file not found.'
|
||||
assert os.path.isfile('poly.pvtp'), 'poly.pvtp file not found.'
|
||||
|
||||
with open(poly) as fin:
|
||||
with open('poly.pvtp', 'r') as fin:
|
||||
outstr = fin.read()
|
||||
|
||||
return outstr
|
||||
|
||||
def _cleanup(self):
|
||||
TestHarness._cleanup(self)
|
||||
output = glob.glob(os.path.join(os.getcwd(), 'track*'))
|
||||
output += glob.glob(os.path.join(os.getcwd(), 'poly*'))
|
||||
output = glob.glob('track*') + glob.glob('poly*')
|
||||
for f in output:
|
||||
if os.path.exists(f):
|
||||
os.remove(f)
|
||||
|
|
@ -54,5 +48,5 @@ if __name__ == '__main__':
|
|||
print('----------------Skipping test-------------')
|
||||
shutil.copy('results_true.dat', 'results_test.dat')
|
||||
exit()
|
||||
harness = TrackTestHarness('statepoint.2.*')
|
||||
harness = TrackTestHarness('statepoint.2.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.10.*')
|
||||
harness = TestHarness('statepoint.10.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
|
|
@ -7,5 +7,5 @@ from testing_harness import TestHarness
|
|||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = TestHarness('statepoint.15.*', True)
|
||||
harness = TestHarness('statepoint.15.h5')
|
||||
harness.main()
|
||||
|
|
|
|||
Some files were not shown because too many files have changed in this diff Show more
Loading…
Add table
Add a link
Reference in a new issue