crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-26 21:25:36 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions

Reduced Python API module imports

Browse source
This commit is contained in:
Will Boyd 2016-04-08 12:26:02 -04:00
parent 9a6ecd7259
commit ddfb01b3fe
14 changed files with 1563 additions and 1585 deletions
Download patch file Download diff file Expand all files Collapse all files

10
examples/python/pincell/build-xml.py
View file

@ -1,6 +1,4 @@
import openmc
from openmc.source import Source
from openmc.stats import Box
###############################################################################
# Simulation Input File Parameters
@ -170,8 +168,12 @@ settings_file = openmc.SettingsFile()
settings_file.batches = batches
settings_file.inactive = inactive
settings_file.particles = particles
settings_file.source = Source(space=Box(
[-0.62992, -0.62992, -1], [0.62992, 0.62992, 1]))
# Create an initial uniform spatial source distribution over fissionable zones
bounds = [-0.62992, -0.62992, -1, 0.62992, 0.62992, 1]
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
settings_file.source = openmc.source.Source(space=uniform_dist)
settings_file.entropy_lower_left = [-0.39218, -0.39218, -1.e50]
settings_file.entropy_upper_right = [0.39218, 0.39218, 1.e50]
settings_file.entropy_dimension = [10, 10, 1]