crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-27 13:45:36 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions

Resolved almost all of the comments from @paulromano, save for rejection sampling of the Legendre polynomial. also fixed @samuelshaner comment about the pincell_multigroup problem

Browse source
This commit is contained in:
Adam Nelson 2016-02-12 21:44:21 -05:00
parent 8a14d600b0
commit 8c43a32130
12 changed files with 400 additions and 323 deletions
Download patch file Download diff file Expand all files Collapse all files

15
examples/python/pincell_multigroup/build-xml.py
View file

@ -1,5 +1,7 @@
import openmc
import openmc.mgxs
from openmc.source import Source
from openmc.stats import Box
import numpy as np
###############################################################################
@ -20,7 +22,7 @@ groups = openmc.mgxs.EnergyGroups(group_edges=[1E-11, 0.0635E-6, 10.0E-6,
1.0E-4, 1.0E-3, 0.5, 1.0, 20.0])
# Instantiate the 7-group (C5G7) cross section data
uo2_xsdata = openmc.XSdata('UO2.300K', groups)
uo2_xsdata = openmc.XSdata('UO2.70m', groups)
uo2_xsdata.order = 0
uo2_xsdata.total = np.array([0.1779492, 0.3298048, 0.4803882, 0.5543674,
0.3118013, 0.3951678, 0.5644058])
@ -43,7 +45,7 @@ uo2_xsdata.nu_fission = np.array([2.005998E-02, 2.027303E-03, 1.570599E-02,
uo2_xsdata.chi = np.array([5.8791E-01, 4.1176E-01, 3.3906E-04, 1.1761E-07,
0.0000E+00, 0.0000E+00, 0.0000E+00])
h2o_xsdata = openmc.XSdata('LWTR.300K', groups)
h2o_xsdata = openmc.XSdata('LWTR.70m', groups)
h2o_xsdata.order = 0
h2o_xsdata.total = np.array([0.15920605, 0.412969593, 0.59030986, 0.58435,
0.718, 1.2544497, 2.650379])
@ -69,8 +71,8 @@ mg_cross_sections_file.export_to_xml()
###############################################################################
# Instantiate some Macroscopic Data
uo2_data = openmc.Macroscopic('UO2', '300K')
h2o_data = openmc.Macroscopic('LWTR', '300K')
uo2_data = openmc.Macroscopic('UO2', '70m')
h2o_data = openmc.Macroscopic('LWTR', '70m')
# Instantiate some Materials and register the appropriate Macroscopic objects
uo2 = openmc.Material(material_id=1, name='UO2 fuel')
@ -83,7 +85,7 @@ water.add_macroscopic(h2o_data)
# Instantiate a MaterialsFile, register all Materials, and export to XML
materials_file = openmc.MaterialsFile()
materials_file.default_xs = '300K'
materials_file.default_xs = '70m'
materials_file.add_materials([uo2, water])
materials_file.export_to_xml()
@ -143,8 +145,7 @@ settings_file.cross_sections = "./mg_cross_sections.xml"
settings_file.batches = batches
settings_file.inactive = inactive
settings_file.particles = particles
settings_file.set_source_space('box', [-0.63, -0.63, -1, \
0.63, 0.63, 1])
settings_file.source = Source(space=Box([-0.63, -0.63, -1.], [0.63, 0.63, 1.]))
###############################################################################
# Exporting to OpenMC tallies.xml File