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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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10
examples/python/basic/build-xml.py
View file

@ -1,6 +1,5 @@
import openmc
from openmc.source import Source
from openmc.stats import Box
###############################################################################
# Simulation Input File Parameters
@ -94,7 +93,12 @@ settings_file = openmc.SettingsFile()
settings_file.batches = batches
settings_file.inactive = inactive
settings_file.particles = particles
settings_file.source = Source(space=Box([-4, -4, -4], [4, 4, 4]))
# Create an initial uniform spatial source distribution over fissionable zones
bounds = [-4., -4., -4., 4., 4., 4.]
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
settings_file.source = openmc.source.Source(space=uniform_dist)
settings_file.export_to_xml()

9
examples/python/boxes/build-xml.py
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@ -1,8 +1,5 @@
import numpy as np
import openmc
from openmc.source import Source
from openmc.stats import Box
###############################################################################
# Simulation Input File Parameters
@ -119,7 +116,11 @@ settings_file = openmc.SettingsFile()
settings_file.batches = batches
settings_file.inactive = inactive
settings_file.particles = particles
settings_file.source = Source(space=Box(*outer_cube.bounding_box))
# Create an initial uniform spatial source distribution over fissionable zones
uniform_dist = openmc.stats.Box(*outer_cube.bounding_box, only_fissionable=True)
settings_file.source = openmc.source.Source(space=uniform_dist)
settings_file.export_to_xml()
###############################################################################

10
examples/python/lattice/hexagonal/build-xml.py
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@ -1,6 +1,4 @@
import openmc
from openmc.source import Source
from openmc.stats import Box
###############################################################################
# Simulation Input File Parameters
@ -126,8 +124,12 @@ settings_file = openmc.SettingsFile()
settings_file.batches = batches
settings_file.inactive = inactive
settings_file.particles = particles
settings_file.source = Source(space=Box(
[-1, -1, -1], [1, 1, 1]))
# Create an initial uniform spatial source distribution over fissionable zones
bounds = [-1, -1, -1, 1, 1, 1]
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
settings_file.source = openmc.source.Source(space=uniform_dist)
settings_file.keff_trigger = {'type' : 'std_dev', 'threshold' : 5E-4}
settings_file.trigger_active = True
settings_file.trigger_max_batches = 100

10
examples/python/lattice/nested/build-xml.py
View file

@ -1,6 +1,4 @@
import openmc
from openmc.source import Source
from openmc.stats import Box
###############################################################################
# Simulation Input File Parameters
@ -137,8 +135,12 @@ settings_file = openmc.SettingsFile()
settings_file.batches = batches
settings_file.inactive = inactive
settings_file.particles = particles
settings_file.source = Source(space=Box(
[-1, -1, -1], [1, 1, 1]))
# Create an initial uniform spatial source distribution over fissionable zones
bounds = [-1, -1, -1, 1, 1, 1]
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
settings_file.source = openmc.source.Source(space=uniform_dist)
settings_file.export_to_xml()

10
examples/python/lattice/simple/build-xml.py
View file

@ -1,6 +1,4 @@
import openmc
from openmc.source import Source
from openmc.stats import Box
###############################################################################
# Simulation Input File Parameters
@ -127,8 +125,12 @@ settings_file = openmc.SettingsFile()
settings_file.batches = batches
settings_file.inactive = inactive
settings_file.particles = particles
settings_file.source = Source(space=Box(
[-1, -1, -1], [1, 1, 1]))
# Create an initial uniform spatial source distribution over fissionable zones
bounds = [-1, -1, -1, 1, 1, 1]
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
settings_file.source = openmc.source.Source(space=uniform_dist)
settings_file.trigger_active = True
settings_file.trigger_max_batches = 100
settings_file.export_to_xml()

10
examples/python/pincell/build-xml.py
View file

@ -1,6 +1,4 @@
import openmc
from openmc.source import Source
from openmc.stats import Box
###############################################################################
# Simulation Input File Parameters
@ -170,8 +168,12 @@ settings_file = openmc.SettingsFile()
settings_file.batches = batches
settings_file.inactive = inactive
settings_file.particles = particles
settings_file.source = Source(space=Box(
[-0.62992, -0.62992, -1], [0.62992, 0.62992, 1]))
# Create an initial uniform spatial source distribution over fissionable zones
bounds = [-0.62992, -0.62992, -1, 0.62992, 0.62992, 1]
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
settings_file.source = openmc.source.Source(space=uniform_dist)
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]

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

10
examples/python/reflective/build-xml.py
View file

@ -1,8 +1,5 @@
import numpy as np
import openmc
from openmc.stats import Box
from openmc.source import Source
###############################################################################
# Simulation Input File Parameters
@ -86,5 +83,10 @@ settings_file = openmc.SettingsFile()
settings_file.batches = batches
settings_file.inactive = inactive
settings_file.particles = particles
settings_file.source = Source(space=Box(*cell.region.bounding_box))
# Create an initial uniform spatial source distribution over fissionable zones
uniform_dist = openmc.stats.Box(*cell.region.bounding_box,
only_fissionable=True)
settings_file.source = openmc.source.Source(space=uniform_dist)
settings_file.export_to_xml()