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fixed material definition

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This commit is contained in:
church89 2022-08-05 15:48:40 +02:00
parent b812fb5d7a
commit 66b7a1dd31
2 changed files with 9 additions and 5 deletions
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9
scripts/msre_geometry_plot.py
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@ -7,7 +7,7 @@ from materials import *
###############################################################################
#geometry
h5m_filepath = './h5m_files/msre.h5m'
h5m_filepath = '../h5m_files/msre_simp_cubit/msre_simp_1e-2.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)
@ -17,7 +17,8 @@ geometry=openmc.Geometry(root)
geometry.export_to_xml()
# materials
mats = openmc.Materials([salt,BeO,inconel,insulation,coolant,helium,stainless,boron])
mats = define_materials()
#mats = openmc.Materials([salt,BeO,inconel,insulation,coolant,helium,stainless,boron])
mats.export_to_xml()
#plotting geometry
@ -29,19 +30,21 @@ y_width = 300
#xy plot
p1 = openmc.Plot()
p1.width = (x_width,y_width)
p1.origin = (0,0,100)
p1.pixels = (1000, 1000)
p1.color_by = 'material'
#xz plot (split plane)
p2 = openmc.Plot()
p2.basis = 'xz'
#p2.origin = (0,5,0)
p2.origin = (0,0,130)
p2.width = (x_width,y_width)
p2.pixels = (1000, 1000)
p2.color_by = 'material'
p3 = openmc.Plot()
p3.basis = 'yz'
p3.origin = (0,0,130)
p3.width = (x_width,y_width)
p3.pixels = (1000, 1000)
p3.color_by = 'material'

5
scripts/msre_neutron_flux.py
View file

@ -7,7 +7,7 @@ from materials import *
###############################################################################
#Geometry
h5m_filepath = 'h5m_files/msre.h5m'
h5m_filepath = '../h5m_files/msre_simp_cubit/msre_simp_1e-2.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)
@ -17,7 +17,8 @@ geometry=openmc.Geometry(root)
geometry.export_to_xml()
#materials
mats = openmc.Materials([salt,BeO,inconel,insulation,coolant,helium,stainless,boron,blanket,shield])
mats=define_materials()
#mats = openmc.Materials([salt,BeO,inconel,insulation,coolant,helium,stainless,boron,blanket,shield])
mats.export_to_xml()
settings = openmc.Settings()