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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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44
examples/python/pincell/build-xml.py
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@ -103,7 +103,7 @@ borated_water.add_s_alpha_beta('HH2O', '71t')
# 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([uo2, helium, zircaloy, borated_water])
materials_file.export_to_xml()
@ -121,10 +121,10 @@ right = openmc.XPlane(surface_id=5, x0=0.62992, name='right')
bottom = openmc.YPlane(surface_id=6, y0=-0.62992, name='bottom')
top = openmc.YPlane(surface_id=7, y0=0.62992, name='top')
left.set_boundary_type('reflective')
right.set_boundary_type('reflective')
top.set_boundary_type('reflective')
bottom.set_boundary_type('reflective')
left.boundary_type = 'reflective'
right.boundary_type = 'reflective'
top.boundary_type = 'reflective'
bottom.boundary_type = 'reflective'
# Instantiate Cells
fuel = openmc.Cell(cell_id=1, name='cell 1')
@ -145,10 +145,10 @@ water.add_surface(bottom, halfspace=+1)
water.add_surface(top, halfspace=-1)
# Register Materials with Cells
fuel.set_fill(uo2)
gap.set_fill(helium)
clad.set_fill(zircaloy)
water.set_fill(borated_water)
fuel.fill = uo2
gap.fill = helium
clad.fill = zircaloy
water.fill = borated_water
# Instantiate Universe
root = openmc.Universe(universe_id=0, name='root universe')
@ -158,11 +158,11 @@ root.add_cells([fuel, gap, clad, water])
# 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()
@ -172,14 +172,14 @@ 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', [-0.62992, -0.62992, -1, \
0.62992, 0.62992, 1])
settings_file.set_entropy_lower_left([-0.39218, -0.39218, -1.e50])
settings_file.set_entropy_upper_right([0.39218, 0.39218, 1.e50])
settings_file.set_entropy_dimension([10, 10, 1])
settings_file.entropy_lower_left = [-0.39218, -0.39218, -1.e50]
settings_file.entropy_upper_right = [0.39218, 0.39218, 1.e50]
settings_file.entropy_dimension = [10, 10, 1]
settings_file.export_to_xml()
@ -189,15 +189,15 @@ settings_file.export_to_xml()
# Instantiate a tally mesh
mesh = openmc.Mesh(mesh_id=1)
mesh.set_type('rectangular')
mesh.set_dimension([100, 100, 1])
mesh.set_lower_left([-0.62992, -0.62992, -1.e50])
mesh.set_upper_right([0.62992, 0.62992, 1.e50])
mesh.type = 'rectangular'
mesh.dimension = [100, 100, 1]
mesh.lower_left = [-0.62992, -0.62992, -1.e50]
mesh.upper_right = [0.62992, 0.62992, 1.e50]
# Instantiate some tally Filters
energy_filter = openmc.Filter(type='energy', bins=[0., 4.e-6, 20.])
mesh_filter = openmc.Filter()
mesh_filter.set_mesh(mesh)
mesh_filter.mesh = mesh
# Instantiate the Tally
tally = openmc.Tally(tally_id=1)