From b812fb5d7ab088792810d62f1bab62eaeef8b0b3 Mon Sep 17 00:00:00 2001 From: church89 Date: Fri, 5 Aug 2022 15:48:03 +0200 Subject: [PATCH] commented out import to neutronsmaterialmaker --- scripts/materials.py | 20 ++++++++++---------- 1 file changed, 10 insertions(+), 10 deletions(-) diff --git a/scripts/materials.py b/scripts/materials.py index f722638..aba1636 100644 --- a/scripts/materials.py +++ b/scripts/materials.py @@ -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