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Geometric intrinsics now use property setter/getter decorators

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This commit is contained in:
Will Boyd 2015-04-22 00:50:03 -05:00
parent 9cada4df0e
commit 5dac75297d
14 changed files with 1014 additions and 466 deletions
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68
examples/python/lattice/hexagonal/build-xml.py
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@ -38,7 +38,7 @@ iron.add_nuclide(fe56, 1.)
# Instantiate a MaterialsFile, register all Materials, and export to XML
materials_file = openmc.MaterialsFile()
materials_file.set_default_xs('71c')
materials_file.default_xs = '71c'
materials_file.add_materials([moderator, fuel, iron])
materials_file.export_to_xml()
@ -54,10 +54,10 @@ bottom = openmc.YPlane(surface_id=3, y0=-4, name='bottom')
top = openmc.YPlane(surface_id=4, y0=4, name='top')
fuel_surf = openmc.ZCylinder(surface_id=5, x0=0, y0=0, R=0.4)
left.set_boundary_type('vacuum')
right.set_boundary_type('vacuum')
top.set_boundary_type('vacuum')
bottom.set_boundary_type('vacuum')
left.boundary_type = 'vacuum'
right.boundary_type = 'vacuum'
top.boundary_type = 'vacuum'
bottom.boundary_type = 'vacuum'
# Instantiate Cells
cell1 = openmc.Cell(cell_id=1, name='Cell 1')
@ -78,11 +78,11 @@ cell5.add_surface(fuel_surf, halfspace=-1)
cell6.add_surface(fuel_surf, halfspace=+1)
# Register Materials with Cells
cell2.set_fill(fuel)
cell3.set_fill(moderator)
cell4.set_fill(moderator)
cell5.set_fill(iron)
cell6.set_fill(moderator)
cell2.fill = fuel
cell3.fill = moderator
cell4.fill = moderator
cell5.fill = iron
cell6.fill = moderator
# Instantiate Universe
univ1 = openmc.Universe(universe_id=1)
@ -98,24 +98,24 @@ root.add_cell(cell1)
# Instantiate a Lattice
lattice = openmc.HexLattice(lattice_id=5)
lattice.set_center([0., 0., 0.])
lattice.set_pitch([1., 2.])
lattice.set_universes([
[ [univ2] + [univ3]*11, [univ2] + [univ3]*5, [univ3] ],
[ [univ2] + [univ1]*11, [univ2] + [univ1]*5, [univ1] ],
[ [univ2] + [univ3]*11, [univ2] + [univ3]*5, [univ3] ]])
lattice.set_outer(univ2)
lattice.center = [0., 0., 0.]
lattice.pitch = [1., 2.]
lattice.universes = \
[ [ [univ2] + [univ3]*11, [univ2] + [univ3]*5, [univ3] ],
[ [univ2] + [univ1]*11, [univ2] + [univ1]*5, [univ1] ],
[ [univ2] + [univ3]*11, [univ2] + [univ3]*5, [univ3] ] ]
lattice.outer = univ2
# Fill Cell with the Lattice
cell1.set_fill(lattice)
cell1.fill = lattice
# Instantiate a Geometry and register the root Universe
geometry = openmc.Geometry()
geometry.set_root_universe(root)
geometry.root_universe = root
# Instantiate a GeometryFile, register Geometry, and export to XML
geometry_file = openmc.GeometryFile()
geometry_file.set_geometry(geometry)
geometry_file.geometry = geometry
geometry_file.export_to_xml()
@ -125,9 +125,9 @@ geometry_file.export_to_xml()
# Instantiate a SettingsFile, set all runtime parameters, and export to XML
settings_file = openmc.SettingsFile()
settings_file.set_batches(batches)
settings_file.set_inactive(inactive)
settings_file.set_particles(particles)
settings_file.batches = batches
settings_file.inactive = inactive
settings_file.particles = particles
settings_file.set_source_space('box', [-1, -1, -1, 1, 1, 1])
settings_file.export_to_xml()
@ -137,19 +137,19 @@ settings_file.export_to_xml()
###############################################################################
plot_xy = openmc.Plot(plot_id=1)
plot_xy.set_filename('plot_xy')
plot_xy.set_origin([0, 0, 0])
plot_xy.set_width([6, 6])
plot_xy.set_pixels([400, 400])
plot_xy.set_color('mat')
plot_xy.filename = 'plot_xy'
plot_xy.origin = [0, 0, 0]
plot_xy.width = [6, 6]
plot_xy.pixels = [400, 400]
plot_xy.color = 'mat'
plot_yz = openmc.Plot(plot_id=2)
plot_yz.set_filename('plot_yz')
plot_yz.set_basis('yz')
plot_yz.set_origin([0, 0, 0])
plot_yz.set_width([8, 8])
plot_yz.set_pixels([400, 400])
plot_yz.set_color('mat')
plot_yz.filename = 'plot_yz'
plot_yz.basis = 'yz'
plot_yz.origin = [0, 0, 0]
plot_yz.width = [8, 8]
plot_yz.pixels = [400, 400]
plot_yz.color = 'mat'
# Instantiate a PlotsFile, add Plot, and export to XML
plot_file = openmc.PlotsFile()