upload pincell.py

misc/openmc/pincell.py

@@ -0,0 +1,84 @@
+import openmc
+
+## ================================ materials
+uo2 = openmc.Material(1, "uo2")
+uo2.add_nuclide('U235', 0.03)
+uo2.add_nuclide('U238', 0.97)
+uo2.add_nuclide('O16', 2.0)
+uo2.set_density('g/cm3', 10.0)
+
+zirconium = openmc.Material(name="zirconium")
+zirconium.add_element('Zr', 1.0)
+zirconium.set_density('g/cm3', 6.6)
+
+water = openmc.Material(name="h2o")
+water.add_nuclide('H1', 2.0)
+water.add_nuclide('O16', 1.0)
+water.set_density('g/cm3', 1.0)
+water.add_s_alpha_beta('c_H_in_H2O')
+
+materials = openmc.Materials([uo2, zirconium, water])
+materials.export_to_xml()
+
+
+## ================================ geometry
+fuel_outer_radius = openmc.ZCylinder(r=0.39)
+clad_inner_radius = openmc.ZCylinder(r=0.40)
+clad_outer_radius = openmc.ZCylinder(r=0.46)
+
+fuel_region = -fuel_outer_radius
+gap_region = +fuel_outer_radius & -clad_inner_radius
+clad_region = +clad_inner_radius & -clad_outer_radius
+
+fuel_cell = openmc.Cell(name='fuel', fill=uo2, region=fuel_region)
+gap_cell = openmc.Cell(name='air gap', region=gap_region) #fill void by default
+clad_cell = openmc.Cell(name='clad', fill=zirconium, region=clad_region)
+
+pitch = 1.26
+left = openmc.XPlane(-pitch/2, boundary_type='reflective')
+right = openmc.XPlane(pitch/2, boundary_type='reflective')
+bottom = openmc.YPlane(-pitch/2, boundary_type='reflective')
+top = openmc.YPlane(pitch/2, boundary_type='reflective')
+water_region = +left & -right & +bottom & -top & +clad_outer_radius
+
+moderator_cell = openmc.Cell(name='moderator', fill=water, region=water_region)
+
+root_universe = openmc.Universe(cells=(fuel_cell, gap_cell, clad_cell, moderator_cell))
+geometry = openmc.Geometry(root_universe)
+geometry.export_to_xml()
+
+## ================================ plotting
+matcolors = {
+    uo2 :      (0xE3,0xE3,0x00),   # yellow (E3E300)
+    zirconium: (0x23,0x23,0x23),   # grey   (232323)
+    water:     (0x00,0x00,0xFF),   # blue   (0000FF)
+}
+plot = openmc.Plot()
+plot.filename = 'img'
+plot.basis = 'xy'
+plot.width = (pitch, pitch)
+plot.pixels = (500, 500)
+plot.origin = (0,0,0)
+plot.color_by = 'material'
+plot.colors = matcolors
+plot.show_overlaps = True
+
+plots = openmc.Plots([plot])
+plots.export_to_xml()
+openmc.plot_geometry()
+
+
+## ================================ settings
+point = openmc.stats.Point((0, 0, 0))
+source = openmc.Source(space=point)
+
+settings = openmc.Settings()
+settings.source = source
+settings.batches = 100
+settings.inactive = 10
+settings.particles = 1000
+
+settings.export_to_xml()
+
+## ================================ running
+openmc.run()