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Reduced Python API module imports

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This commit is contained in:
Will Boyd 2016-04-08 12:26:02 -04:00
parent 9a6ecd7259
commit ddfb01b3fe
14 changed files with 1563 additions and 1585 deletions
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12
examples/python/pincell_multigroup/build-xml.py
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@ -1,8 +1,6 @@
import numpy as np
import openmc
import openmc.mgxs
from openmc.source import Source
from openmc.stats import Box
import numpy as np
###############################################################################
# Simulation Input File Parameters
@ -145,7 +143,13 @@ settings_file.cross_sections = "./mg_cross_sections.xml"
settings_file.batches = batches
settings_file.inactive = inactive
settings_file.particles = particles
settings_file.source = Source(space=Box([-0.63, -0.63, -1.], [0.63, 0.63, 1.]))
# Create an initial uniform spatial source distribution over fissionable zones
bounds = [-0.63, -0.63, -1, 0.63, 0.63, 1]
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:])
settings_file.source = openmc.source.Source(space=uniform_dist)
settings_file.export_to_xml()
###############################################################################
# Exporting to OpenMC tallies.xml File