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Implemented reflective example input file using Python API

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This commit is contained in:
Will Boyd 2014-10-13 09:19:55 -04:00
parent b0e5c88b57
commit 368184371e
5 changed files with 118 additions and 35 deletions
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92
examples/python/reflective/build-xml.py Normal file
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import openmc
###############################################################################
# Simulation Input File Parameters
###############################################################################
# OpenMC simulation parameters
batches = 500
inactive = 10
particles = 10000
###############################################################################
# Exporting to OpenMC materials.xml File
###############################################################################
# Instantiate a Nuclides
u235 = openmc.Nuclide('U-235')
# Instantiate a Material and register the Nuclide
fuel = openmc.Material(material_id=1, name='fuel')
fuel.setDensity('g/cc', 4.5)
fuel.addNuclide(u235, 1.)
# Instantiate a MaterialsFile, register Material, and export to XML
materials_file = openmc.MaterialsFile()
materials_file.setDefaultXS('71c')
materials_file.addMaterial(fuel)
materials_file.exportToXML()
###############################################################################
# Exporting to OpenMC geometry.xml File
###############################################################################
# Instantiate Surfaces
surf1 = openmc.XPlane(surface_id=1, x0=-1, name='surf 1')
surf2 = openmc.XPlane(surface_id=2, x0=+1, name='surf 2')
surf3 = openmc.YPlane(surface_id=3, y0=-1, name='surf 3')
surf4 = openmc.YPlane(surface_id=4, y0=+1, name='surf 4')
surf5 = openmc.ZPlane(surface_id=5, z0=-1, name='surf 5')
surf6 = openmc.ZPlane(surface_id=6, z0=+1, name='surf 6')
surf1.setBoundaryType('vacuum')
surf2.setBoundaryType('vacuum')
surf3.setBoundaryType('reflective')
surf4.setBoundaryType('reflective')
surf5.setBoundaryType('reflective')
surf6.setBoundaryType('reflective')
# Instantiate Cell
cell = openmc.Cell(cell_id=1, name='cell 1')
# Register Surfaces with Cell
cell.addSurface(surface=surf1, halfspace=+1)
cell.addSurface(surface=surf2, halfspace=-1)
cell.addSurface(surface=surf3, halfspace=+1)
cell.addSurface(surface=surf4, halfspace=-1)
cell.addSurface(surface=surf5, halfspace=+1)
cell.addSurface(surface=surf6, halfspace=-1)
# Register Material with Cell
cell.setFill(fuel)
# Instantiate Universes
root = openmc.Universe(universe_id=0, name='root universe')
# Register Cell with Universe
root.addCell(cell)
# Instantiate a Geometry and register the root Universe
geometry = openmc.Geometry()
geometry.setRootUniverse(root)
# Instantiate a GeometryFile, register Geometry, and export to XML
geometry_file = openmc.GeometryFile()
geometry_file.setGeometry(geometry)
geometry_file.exportToXML()
###############################################################################
# Exporting to OpenMC settings.xml File
###############################################################################
# Instantiate a SettingsFile, set all runtime parameters, and export to XML
settings_file = openmc.SettingsFile()
settings_file.setBatches(batches)
settings_file.setInactive(inactive)
settings_file.setParticles(particles)
settings_file.setSourceSpace('box', [-1, -1, -1, 1, 1, 1])
settings_file.exportToXML()

32
examples/python/reflective/geometry.xml
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<?xml version="1.0"?>
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<!-- Definition of Cells -->
<cell id="1">
<universe>0</universe>
<material>1</material>
<surfaces>1 -2 3 -4 5 -6</surfaces>
</cell>
<!-- Defition of Surfaces -->
<surface id="1" type="x-plane" coeffs="-1" boundary="vacuum" />
<surface id="2" type="x-plane" coeffs="1" boundary="vacuum" />
<surface id="3" type="y-plane" coeffs="-1" boundary="reflective" />
<surface id="4" type="y-plane" coeffs="1" boundary="reflective" />
<surface id="5" type="z-plane" coeffs="-1" boundary="reflective" />
<surface id="6" type="z-plane" coeffs="1" boundary="reflective" />
<!--cell 1-->
<cell id="1" material="1" surfaces="1 -2 3 -4 5 -6" universe="0" />
<!--surf 1-->
<surface boundary="vacuum" coeffs="-1" id="1" type="x-plane" />
<!--surf 2-->
<surface boundary="vacuum" coeffs="1" id="2" type="x-plane" />
<!--surf 3-->
<surface boundary="reflective" coeffs="-1" id="3" type="y-plane" />
<!--surf 4-->
<surface boundary="reflective" coeffs="1" id="4" type="y-plane" />
<!--surf 5-->
<surface boundary="reflective" coeffs="-1" id="5" type="z-plane" />
<!--surf 6-->
<surface boundary="reflective" coeffs="1" id="6" type="z-plane" />
</geometry>

12
examples/python/reflective/materials.xml
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<?xml version="1.0"?>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<default_xs>71c</default_xs>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" ao="1.0" />
<!--fuel-->
<material id="1">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U-235" />
</material>
</materials>

15
examples/python/reflective/settings.xml
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<?xml version="1.0"?>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<!-- Parameters for k-eigenvalue calculation -->
<eigenvalue>
<batches>500</batches>
<inactive>10</inactive>
<particles>10000</particles>
<batches>500</batches>
<inactive>10</inactive>
</eigenvalue>
<!-- Starting source -->
<source>
<source>
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
</source>
</settings>