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cleanup

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This commit is contained in:
LukeLabrie 2022-07-28 11:10:29 +02:00
parent cd0806aa90
commit 9efbb40d15
4 changed files with 25 additions and 22 deletions
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12
scripts/msre_geometry_plot.py
View file

@ -6,16 +6,20 @@ from materials import *
#generate geometry plot of are (all safety rods fully inserted)
###############################################################################
#geometry
h5m_filepath = './h5m_files/msre.h5m'
graveyard = openmc.Sphere(r=10000,boundary_type='vacuum')
cad_univ = openmc.DAGMCUniverse(filename=h5m_filepath,auto_geom_ids=True)
cad_cell = openmc.Cell(region=-graveyard,fill=cad_univ)
root=openmc.Universe()
root.add_cells([cad_cell])
geometry=openmc.Geometry(root)
geometry.export_to_xml()
# materials
mats = openmc.Materials([salt,BeO,inconel,insulation,coolant,helium,stainless,boron])
mats.export_to_xml()
dag_univ = openmc.DAGMCUniverse(h5m_filepath)
geom = openmc.Geometry(root=dag_univ)
geom.export_to_xml()
#plotting geometry
plots = openmc.Plots()

21
scripts/msre_neutron_flux.py
View file

@ -8,6 +8,13 @@ from materials import *
#Geometry
h5m_filepath = 'h5m_files/msre.h5m'
graveyard = openmc.Sphere(r=10000,boundary_type='vacuum')
cad_univ = openmc.DAGMCUniverse(filename=h5m_filepath,auto_geom_ids=True)
cad_cell = openmc.Cell(region=-graveyard,fill=cad_univ)
root=openmc.Universe()
root.add_cells([cad_cell])
geometry=openmc.Geometry(root)
geometry.export_to_xml()
#materials
mats = openmc.Materials([salt,BeO,inconel,insulation,coolant,helium,stainless,boron,blanket,shield])
@ -23,19 +30,7 @@ source_area = openmc.stats.Box([-200., -200., -200.],[ 200., 200., 200.],only_
settings.source = openmc.Source(space=source_area)
settings.export_to_xml()
#geometry
graveyard=openmc.Sphere(r=10000,boundary_type='vacuum')
cad_univ = openmc.DAGMCUniverse(filename=h5m_filepath,auto_geom_ids=True,universe_id=996 )
cad_cell = openmc.Cell(cell_id=997 , region= -graveyard, fill= cad_univ)
root = openmc.Universe(universe_id=998)
root.add_cells([cad_cell])
geometry = openmc.Geometry(root)
geometry.export_to_xml()
#tallies
tallies = openmc.Tallies()
mesh = openmc.RegularMesh()

12
scripts/msre_photon_flux.py
View file

@ -8,6 +8,13 @@ from materials import *
#Geometry
h5m_filepath = 'h5m_files/ARE.h5m'
graveyard = openmc.Sphere(r=10000,boundary_type='vacuum')
cad_univ = openmc.DAGMCUniverse(filename=h5m_filepath,auto_geom_ids=True)
cad_cell = openmc.Cell(region=-graveyard,fill=cad_univ)
root=openmc.Universe()
root.add_cells([cad_cell])
geometry=openmc.Geometry(root)
geometry.export_to_xml()
#materials
mats = openmc.Materials([salt,BeO,inconel,insulation,coolant,helium,stainless,boron,blanket,shield])
@ -23,10 +30,7 @@ source_area = openmc.stats.Box([-200., -200., -200.],[ 200., 200., 200.],only_
settings.source = openmc.Source(space=source_area)
settings.export_to_xml()
dag_univ = openmc.DAGMCUniverse(h5m_filepath)
geom = openmc.Geometry(root=dag_univ)
geom.export_to_xml()
#tallies
tallies = openmc.Tallies()
# sets up filters for the tallies

2
scripts/step_to_h5m.py
View file

@ -14,7 +14,7 @@ h5m_out_filepath = os.getcwd() + '/h5m_files/msre.h5m'
# mesher config
ab.mesher_config['min_mesh_size'] = 0.2
ab.mesher_config['mesh_algorithm'] = 3
ab.mesher_config['mesh_algorithm'] = 4
ab.mesher_config['threads'] = 6
#ab.mesher_config['max_mesh_size'] = 1000
#ab.mesher_config['curve_samples'] = 100