Created Python scripts to create reproducable AP1000 xml files
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AP1000/PWR 2.1/pwr_2-1.py
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AP1000/PWR 2.1/pwr_2-1.py
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"""
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====================================================
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Description: AP1000 PWR Assembly 17*17
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Case: Problem 2 (17*17 PWR Assembly)
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Written By: Ahmed K Madani
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Date: 02/03/2017
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====================================================
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"""
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import openmc
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################## MATERIALS ##################
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fuel_21 = openmc.Material()
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fuel_21.set_density("g/cc", 10.5)
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fuel_21.temperature = 600 # K (42c=300K, 50c=293.6, 53c=587.2, 66=293.6, 70c=293.6, 71c=600K, 72c=900K, 73c=1200K, 74c=2500K)
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fuel_21.add_element("U", 1, enrichment=2.1)
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fuel_21.add_nuclide("O16", 2, percent_type="ao")
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gap = openmc.Material()
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gap.set_density("atom/b-cm", 1.00000e-4)
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gap.temperature = 600 # K
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gap.add_nuclide("He4", 1, percent_type="ao")
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clad = openmc.Material()
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clad.set_density("g/cc", 6.55)
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clad.temperature = 600 # K
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clad.add_nuclide("O16", 0.00125, percent_type="wo")
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clad.add_element("Nb", 0.01, percent_type="wo")
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clad.add_element("Sn", 0.01, percent_type="wo")
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clad.add_element("Fe", 0.001, percent_type="wo")
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clad.add_element("Zr", 0.97775, percent_type="wo")
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water = openmc.Material()
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water.set_density("g/cc", 0.73)
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water.temperature = 600 # K
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water.add_nuclide("H1", 2, percent_type="ao")
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water.add_nuclide("O16", 1, percent_type="ao")
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water.add_s_alpha_beta(name='c_H_in_H2O')
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tube = openmc.Material()
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tube.set_density("g/cc", 7.92)
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tube.temperature = 600 # K
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tube.add_element("Ni", 0.0950095, percent_type="wo")
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tube.add_element("Fe", 0.69493745, percent_type="wo")
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tube.add_element("Mn", 0.02, percent_type="wo")
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tube.add_element("Cr", 0.19, percent_type="wo")
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materials_file = openmc.Materials([fuel_21, gap, clad, water, tube])
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materials_file.export_to_xml(path="problem/materials.xml")
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################## GEOMETRY ##################
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surf1 = openmc.XPlane(x0=-10.659, boundary_type="reflective")
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surf2 = openmc.XPlane(x0=10.659, boundary_type="reflective")
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surf3 = openmc.YPlane(y0=-10.659, boundary_type="reflective")
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surf4 = openmc.YPlane(y0=10.659, boundary_type="reflective")
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surf5 = openmc.ZCylinder(x0=0, y0=0, r=0.4095)
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surf6 = openmc.ZCylinder(x0=0, y0=0, r=0.4177)
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surf7 = openmc.ZCylinder(x0=0, y0=0, r=0.4749)
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surf8 = openmc.ZCylinder(x0=0, y0=0, r=0.5715)
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surf9 = openmc.ZCylinder(x0=0, y0=0, r=0.612)
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surf10 = openmc.ZPlane(z0=-182.9, boundary_type="reflective")
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surf11 = openmc.ZPlane(z0=182.9, boundary_type="reflective")
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univ1 = openmc.Universe()
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cell10 = openmc.Cell(cell_id=10, fill=fuel_21)
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cell10.region = -surf5
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cell20 = openmc.Cell(cell_id=20, fill=gap)
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cell20.region = +surf5 & -surf6
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cell30 = openmc.Cell(cell_id=30, fill=clad)
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cell30.region = +surf6 & -surf7
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univ2 = openmc.Universe()
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cell40 = openmc.Cell(cell_id=40, fill=water)
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cell40.region = +surf7
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cell50 = openmc.Cell(cell_id=50, fill=water)
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cell50.region = -surf8
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cell60 = openmc.Cell(cell_id=60, fill=tube)
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cell60.region = +surf8 & -surf9
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cell70 = openmc.Cell(cell_id=70, fill=water)
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cell70.region = +surf9
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univ1.add_cells([cell10, cell20, cell30, cell40])
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univ2.add_cells([cell50, cell60, cell70])
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lattice = openmc.RectLattice(lattice_id=5)
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lattice.pitch = [1.26, 1.26]
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lattice.lower_left = [-10.659, -10.659]
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lattice.universes = [[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ1, univ2, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ2, univ1, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ1, univ2, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ2, univ1, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1]
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]
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cell1 = openmc.Cell(fill=lattice)
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cell1.region = +surf1 & -surf2 & +surf3 & -surf4 & +surf10 & -surf11
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univ3 = openmc.Universe()
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univ3.add_cell(cell1)
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geometry_file = openmc.Geometry(univ3)
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geometry_file.export_to_xml(path="problem/geometry.xml")
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################## TALLIES ##################
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filter1 = openmc.CellFilter(filter_id=1, bins=1)
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filter8 = openmc.DelayedGroupFilter(filter_id=8, bins=[1, 2, 3, 4, 5, 6])
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tally1 = openmc.Tally()
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tally1.filters = [filter1]
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tally1.scores = ["flux"]
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tally2 = openmc.Tally()
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tally2.filters = [filter1]
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tally2.scores = ["nu-fission"]
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tally3 = openmc.Tally()
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tally3.filters = [filter1]
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tally3.scores = ["delayed-nu-fission"]
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tally4 = openmc.Tally()
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tally4.filters = [filter1]
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tally4.scores = ["fission"]
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tally5 = openmc.Tally()
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tally5.filters = [filter1]
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tally5.scores = ["absorption"]
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tally6 = openmc.Tally()
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tally6.filters = [filter1]
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tally6.scores = ["scatter"]
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tally7 = openmc.Tally()
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tally7.filters = [filter1]
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tally7.scores = ["total"]
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tally8 = openmc.Tally()
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tally8.filters = [filter8]
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tally8.scores = ["delayed-nu-fission"]
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tallies_file = openmc.Tallies([tally1, tally2, tally3, tally4, tally5, tally6, tally7, tally8])
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tallies_file.export_to_xml(path="problem/tallies.xml")
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################## PLOTS ##################
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plot = openmc.Plot()
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plot.pixels = (1000, 1000)
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plot.width = (25.50, 25.50)
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# plot._colors = (123, 123, 231)
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plot_file = openmc.Plots([plot])
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plot_file.export_to_xml(path="problem/plots.xml")
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################## SETTINGS ##################
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settings_file = openmc.Settings()
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settings_file.source = openmc.Source(space=openmc.stats.Box((-10.659, -10.659, -182.9),
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(10.659, 10.659, 182.9)))
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settings_file.batches = 600
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settings_file.inactive = 50
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settings_file.particles = 10000
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settings_file.export_to_xml(path="problem/settings.xml")
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openmc.run(cwd='problem')
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176
AP1000/PWR 2.6/pwr_2-6.py
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AP1000/PWR 2.6/pwr_2-6.py
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import openmc
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################## MATERIALS ##################
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fuel_26 = openmc.Material()
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fuel_26.set_density("g/cc", 10.5)
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fuel_26.temperature = 600 # K
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fuel_26.add_element("U", 1, enrichment=2.6)
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fuel_26.add_nuclide("O16", 2, percent_type="ao")
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gap = openmc.Material()
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gap.set_density("atom/b-cm", 1.00000e-4)
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gap.temperature = 600 # K
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gap.add_nuclide("He4", 1, percent_type="ao")
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clad = openmc.Material()
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clad.set_density("g/cc", 6.55)
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clad.temperature = 600 # K
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clad.add_nuclide("O16", 0.00125, percent_type="wo")
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clad.add_element("Nb", 0.01, percent_type="wo")
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clad.add_element("Sn", 0.01, percent_type="wo")
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clad.add_element("Fe", 0.001, percent_type="wo")
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clad.add_element("Zr", 0.97775, percent_type="wo")
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water = openmc.Material()
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water.set_density("g/cc", 0.73)
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water.temperature = 600 # K
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water.add_nuclide("H1", 2, percent_type="ao")
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water.add_nuclide("O16", 1, percent_type="ao")
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water.add_s_alpha_beta(name='c_H_in_H2O')
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tube = openmc.Material()
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tube.set_density("g/cc", 7.92)
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tube.temperature = 600 # K
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tube.add_element("Ni", 0.0950095, percent_type="wo")
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tube.add_element("Fe", 0.69493745, percent_type="wo")
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tube.add_element("Mn", 0.02, percent_type="wo")
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tube.add_element("Cr", 0.19, percent_type="wo")
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materials_file = openmc.Materials([fuel_26, gap, clad, water, tube])
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materials_file.export_to_xml(path="problem/materials.xml")
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################## GEOMETRY ##################
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surf1 = openmc.XPlane(x0=-10.659, boundary_type="reflective")
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surf2 = openmc.XPlane(x0=10.659, boundary_type="reflective")
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surf3 = openmc.YPlane(y0=-10.659, boundary_type="reflective")
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surf4 = openmc.YPlane(y0=10.659, boundary_type="reflective")
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surf5 = openmc.ZCylinder(x0=0, y0=0, r=0.4095)
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surf6 = openmc.ZCylinder(x0=0, y0=0, r=0.4177)
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surf7 = openmc.ZCylinder(x0=0, y0=0, r=0.4749)
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surf8 = openmc.ZCylinder(x0=0, y0=0, r=0.5715)
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surf9 = openmc.ZCylinder(x0=0, y0=0, r=0.612)
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surf10 = openmc.ZPlane(z0=-182.9, boundary_type="reflective")
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surf11 = openmc.ZPlane(z0=182.9, boundary_type="reflective")
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univ1 = openmc.Universe()
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cell10 = openmc.Cell(cell_id=10, fill=fuel_26)
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cell10.region = -surf5
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cell20 = openmc.Cell(cell_id=20, fill=gap)
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cell20.region = +surf5 & -surf6
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cell30 = openmc.Cell(cell_id=30, fill=clad)
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cell30.region = +surf6 & -surf7
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univ2 = openmc.Universe()
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cell40 = openmc.Cell(cell_id=40, fill=water)
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cell40.region = +surf7
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cell50 = openmc.Cell(cell_id=50, fill=water)
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cell50.region = -surf8
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cell60 = openmc.Cell(cell_id=60, fill=tube)
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cell60.region = +surf8 & -surf9
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cell70 = openmc.Cell(cell_id=70, fill=water)
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cell70.region = +surf9
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univ1.add_cells([cell10, cell20, cell30, cell40])
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univ2.add_cells([cell50, cell60, cell70])
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lattice = openmc.RectLattice(lattice_id=5)
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lattice.pitch = [1.26, 1.26]
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lattice.lower_left = [-10.659, -10.659]
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lattice.universes = [[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ1, univ2, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ2, univ1, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ1, univ2, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ2, univ1, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
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[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1]
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]
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cell1 = openmc.Cell(fill=lattice)
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cell1.region = +surf1 & -surf2 & +surf3 & -surf4 & +surf10 & -surf11
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univ3 = openmc.Universe()
|
||||
univ3.add_cell(cell1)
|
||||
|
||||
geometry_file = openmc.Geometry(univ3)
|
||||
geometry_file.export_to_xml(path="problem/geometry.xml")
|
||||
|
||||
################## TALLIES ##################
|
||||
|
||||
filter1 = openmc.CellFilter(filter_id=1, bins=1)
|
||||
filter8 = openmc.DelayedGroupFilter(filter_id=8, bins=[1, 2, 3, 4, 5, 6])
|
||||
|
||||
tally1 = openmc.Tally()
|
||||
tally1.filters = [filter1]
|
||||
tally1.scores = ["flux"]
|
||||
|
||||
tally2 = openmc.Tally()
|
||||
tally2.filters = [filter1]
|
||||
tally2.scores = ["nu-fission"]
|
||||
|
||||
tally3 = openmc.Tally()
|
||||
tally3.filters = [filter1]
|
||||
tally3.scores = ["delayed-nu-fission"]
|
||||
|
||||
tally4 = openmc.Tally()
|
||||
tally4.filters = [filter1]
|
||||
tally4.scores = ["fission"]
|
||||
|
||||
tally5 = openmc.Tally()
|
||||
tally5.filters = [filter1]
|
||||
tally5.scores = ["absorption"]
|
||||
|
||||
tally6 = openmc.Tally()
|
||||
tally6.filters = [filter1]
|
||||
tally6.scores = ["scatter"]
|
||||
|
||||
tally7 = openmc.Tally()
|
||||
tally7.filters = [filter1]
|
||||
tally7.scores = ["total"]
|
||||
|
||||
tally8 = openmc.Tally()
|
||||
tally8.filters = [filter8]
|
||||
tally8.scores = ["delayed-nu-fission"]
|
||||
|
||||
tallies_file = openmc.Tallies([tally1, tally2, tally3, tally4, tally5, tally6, tally7, tally8])
|
||||
tallies_file.export_to_xml(path="problem/tallies.xml")
|
||||
|
||||
################## PLOTS ##################
|
||||
|
||||
plot = openmc.Plot()
|
||||
plot.pixels = (1000, 1000)
|
||||
plot.width = (25.50, 25.50)
|
||||
# plot._colors = (123, 123, 231)
|
||||
|
||||
plot_file = openmc.Plots([plot])
|
||||
plot_file.export_to_xml(path="problem/plots.xml")
|
||||
|
||||
################## SETTINGS ##################
|
||||
|
||||
settings_file = openmc.Settings()
|
||||
settings_file.source = openmc.Source(space=openmc.stats.Box((-10.659, -10.659, -182.9),
|
||||
(10.659, 10.659, 182.9)))
|
||||
settings_file.batches = 600
|
||||
settings_file.inactive = 50
|
||||
settings_file.particles = 10000
|
||||
|
||||
settings_file.export_to_xml(path="problem/settings.xml")
|
||||
|
||||
openmc.run(cwd='problem')
|
||||
176
AP1000/PWR 3.10/pwr_3-1.py
Normal file
176
AP1000/PWR 3.10/pwr_3-1.py
Normal file
|
|
@ -0,0 +1,176 @@
|
|||
import openmc
|
||||
|
||||
################## MATERIALS ##################
|
||||
|
||||
fuel_31 = openmc.Material()
|
||||
fuel_31.set_density("g/cc", 10.5)
|
||||
fuel_31.temperature = 600 # K
|
||||
fuel_31.add_element("U", 1, enrichment=3.1)
|
||||
fuel_31.add_nuclide("O16", 2, percent_type="ao")
|
||||
|
||||
gap = openmc.Material()
|
||||
gap.set_density("atom/b-cm", 1.00000e-4)
|
||||
gap.temperature = 600 # K
|
||||
gap.add_nuclide("He4", 1, percent_type="ao")
|
||||
|
||||
clad = openmc.Material()
|
||||
clad.set_density("g/cc", 6.55)
|
||||
clad.temperature = 600 # K
|
||||
clad.add_nuclide("O16", 0.00125, percent_type="wo")
|
||||
clad.add_element("Nb", 0.01, percent_type="wo")
|
||||
clad.add_element("Sn", 0.01, percent_type="wo")
|
||||
clad.add_element("Fe", 0.001, percent_type="wo")
|
||||
clad.add_element("Zr", 0.97775, percent_type="wo")
|
||||
|
||||
water = openmc.Material()
|
||||
water.set_density("g/cc", 0.73)
|
||||
water.temperature = 600 # K
|
||||
water.add_nuclide("H1", 2, percent_type="ao")
|
||||
water.add_nuclide("O16", 1, percent_type="ao")
|
||||
water.add_s_alpha_beta(name='c_H_in_H2O')
|
||||
|
||||
tube = openmc.Material()
|
||||
tube.set_density("g/cc", 7.92)
|
||||
tube.temperature = 600 # K
|
||||
tube.add_element("Ni", 0.0950095, percent_type="wo")
|
||||
tube.add_element("Fe", 0.69493745, percent_type="wo")
|
||||
tube.add_element("Mn", 0.02, percent_type="wo")
|
||||
tube.add_element("Cr", 0.19, percent_type="wo")
|
||||
|
||||
materials_file = openmc.Materials([fuel_31, gap, clad, water, tube])
|
||||
materials_file.export_to_xml(path="problem/materials.xml")
|
||||
|
||||
################## GEOMETRY ##################
|
||||
|
||||
surf1 = openmc.XPlane(x0=-10.659, boundary_type="reflective")
|
||||
surf2 = openmc.XPlane(x0=10.659, boundary_type="reflective")
|
||||
surf3 = openmc.YPlane(y0=-10.659, boundary_type="reflective")
|
||||
surf4 = openmc.YPlane(y0=10.659, boundary_type="reflective")
|
||||
|
||||
surf5 = openmc.ZCylinder(x0=0, y0=0, r=0.4095)
|
||||
surf6 = openmc.ZCylinder(x0=0, y0=0, r=0.4177)
|
||||
surf7 = openmc.ZCylinder(x0=0, y0=0, r=0.4749)
|
||||
surf8 = openmc.ZCylinder(x0=0, y0=0, r=0.5715)
|
||||
surf9 = openmc.ZCylinder(x0=0, y0=0, r=0.612)
|
||||
|
||||
surf10 = openmc.ZPlane(z0=-182.9, boundary_type="reflective")
|
||||
surf11 = openmc.ZPlane(z0=182.9, boundary_type="reflective")
|
||||
|
||||
univ1 = openmc.Universe()
|
||||
cell10 = openmc.Cell(cell_id=10, fill=fuel_31)
|
||||
cell10.region = -surf5
|
||||
|
||||
cell20 = openmc.Cell(cell_id=20, fill=gap)
|
||||
cell20.region = +surf5 & -surf6
|
||||
|
||||
cell30 = openmc.Cell(cell_id=30, fill=clad)
|
||||
cell30.region = +surf6 & -surf7
|
||||
|
||||
univ2 = openmc.Universe()
|
||||
cell40 = openmc.Cell(cell_id=40, fill=water)
|
||||
cell40.region = +surf7
|
||||
|
||||
cell50 = openmc.Cell(cell_id=50, fill=water)
|
||||
cell50.region = -surf8
|
||||
|
||||
cell60 = openmc.Cell(cell_id=60, fill=tube)
|
||||
cell60.region = +surf8 & -surf9
|
||||
|
||||
cell70 = openmc.Cell(cell_id=70, fill=water)
|
||||
cell70.region = +surf9
|
||||
|
||||
univ1.add_cells([cell10, cell20, cell30, cell40])
|
||||
univ2.add_cells([cell50, cell60, cell70])
|
||||
|
||||
lattice = openmc.RectLattice(lattice_id=5)
|
||||
lattice.pitch = [1.26, 1.26]
|
||||
lattice.lower_left = [-10.659, -10.659]
|
||||
lattice.universes = [[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
|
||||
[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
|
||||
[univ1, univ1, univ1, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ1, univ1, univ1],
|
||||
[univ1, univ1, univ1, univ2, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ2, univ1, univ1, univ1],
|
||||
[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
|
||||
[univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1],
|
||||
[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
|
||||
[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
|
||||
[univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1],
|
||||
[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
|
||||
[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
|
||||
[univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1],
|
||||
[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
|
||||
[univ1, univ1, univ1, univ2, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ2, univ1, univ1, univ1],
|
||||
[univ1, univ1, univ1, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ2, univ1, univ1, univ1, univ1, univ1],
|
||||
[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1],
|
||||
[univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1, univ1]
|
||||
]
|
||||
cell1 = openmc.Cell(fill=lattice)
|
||||
cell1.region = +surf1 & -surf2 & +surf3 & -surf4 & +surf10 & -surf11
|
||||
|
||||
univ3 = openmc.Universe()
|
||||
univ3.add_cell(cell1)
|
||||
|
||||
geometry_file = openmc.Geometry(univ3)
|
||||
geometry_file.export_to_xml(path="problem/geometry.xml")
|
||||
|
||||
################## TALLIES ##################
|
||||
|
||||
filter1 = openmc.CellFilter(filter_id=1, bins=1)
|
||||
filter8 = openmc.DelayedGroupFilter(filter_id=8, bins=[1, 2, 3, 4, 5, 6])
|
||||
|
||||
tally1 = openmc.Tally()
|
||||
tally1.filters = [filter1]
|
||||
tally1.scores = ["flux"]
|
||||
|
||||
tally2 = openmc.Tally()
|
||||
tally2.filters = [filter1]
|
||||
tally2.scores = ["nu-fission"]
|
||||
|
||||
tally3 = openmc.Tally()
|
||||
tally3.filters = [filter1]
|
||||
tally3.scores = ["delayed-nu-fission"]
|
||||
|
||||
tally4 = openmc.Tally()
|
||||
tally4.filters = [filter1]
|
||||
tally4.scores = ["fission"]
|
||||
|
||||
tally5 = openmc.Tally()
|
||||
tally5.filters = [filter1]
|
||||
tally5.scores = ["absorption"]
|
||||
|
||||
tally6 = openmc.Tally()
|
||||
tally6.filters = [filter1]
|
||||
tally6.scores = ["scatter"]
|
||||
|
||||
tally7 = openmc.Tally()
|
||||
tally7.filters = [filter1]
|
||||
tally7.scores = ["total"]
|
||||
|
||||
tally8 = openmc.Tally()
|
||||
tally8.filters = [filter8]
|
||||
tally8.scores = ["delayed-nu-fission"]
|
||||
|
||||
tallies_file = openmc.Tallies([tally1, tally2, tally3, tally4, tally5, tally6, tally7, tally8])
|
||||
tallies_file.export_to_xml(path="problem/tallies.xml")
|
||||
|
||||
################## PLOTS ##################
|
||||
|
||||
plot = openmc.Plot()
|
||||
plot.pixels = (1000, 1000)
|
||||
plot.width = (25.50, 25.50)
|
||||
# plot._colors = (123, 123, 231)
|
||||
|
||||
plot_file = openmc.Plots([plot])
|
||||
plot_file.export_to_xml(path="problem/plots.xml")
|
||||
|
||||
################## SETTINGS ##################
|
||||
|
||||
settings_file = openmc.Settings()
|
||||
settings_file.source = openmc.Source(space=openmc.stats.Box((-10.659, -10.659, -182.9),
|
||||
(10.659, 10.659, 182.9)))
|
||||
settings_file.batches = 600
|
||||
settings_file.inactive = 50
|
||||
settings_file.particles = 10000
|
||||
|
||||
settings_file.export_to_xml(path="problem/settings.xml")
|
||||
|
||||
openmc.run(cwd='problem')
|
||||
Loading…
Add table
Add a link
Reference in a new issue