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commented out import to neutronsmaterialmaker

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This commit is contained in:
church89 2022-08-05 15:48:03 +02:00
parent 9efbb40d15
commit b812fb5d7a
1 changed files with 10 additions and 10 deletions
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20
scripts/materials.py
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@ -1,10 +1,10 @@
import sys
sys.path.append('/opt/openmc/')
import openmc
import neutronsmaterialmaker as nmm
#import neutronsmaterialmaker as nmm
def define_materials():
# salt = openmc.Material(name="salt", temperature = 903)
#salt = openmc.Material(name="salt", temperature = 903)
# salt.add_nuclide('Li7', 10.9566, 'wo')
# salt.add_element('Be', 6.3492, 'wo')
# salt.add_element('Zr', 11.1013, 'wo')
@ -191,9 +191,9 @@ def define_materials():
bush.name='bush'
#Concrete block
concrete=nmm.Material.from_library('Concrete, Regular')
concrete=concrete.openmc_material
concrete.name="concrete"
#concrete=nmm.Material.from_library('Concrete, Regular')
#concrete=concrete.openmc_material
#concrete.name="concrete"
#Baryte block
baryte = openmc.Material(name="baryte", temperature = 903)
baryte.add_element('Ba',1)
@ -205,10 +205,10 @@ def define_materials():
water.add_element('H',2)
water.add_element('O',1)
water.set_density('g/cm3',0.997)
steel = nmm.Material.from_library('Steel, Carbon')
steel=steel.openmc_material
shield = openmc.Material.mix_materials([water,steel],[0.5,0.5],'wo')
shield.name='waterSteel'
#steel = nmm.Material.from_library('Steel, Carbon')
#steel=steel.openmc_material
#shield = openmc.Material.mix_materials([water,steel],[0.5,0.5],'wo')
#shield.name='waterSteel'
detector = openmc.Material(name = 'water')
detector.add_element('O',76.2,percent_type='wo')
@ -217,6 +217,6 @@ def define_materials():
detector.add_element('N',2.6,percent_type='wo')
detector.set_density('g/cm3',1.0)
mats = openmc.Materials([salt,graphite,inor,helium,inconel,bush,concrete,baryte,shield,detector])
mats = openmc.Materials([salt,graphite,inor,helium,inconel,bush])#,concrete,baryte,shield,detector])
mats.export_to_xml()
return mats