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

Update example Python inputs, fix exporting to XML for <cell>

Browse source
This commit is contained in:
Paul Romano 2015-09-28 16:53:27 +07:00
parent 6beee729cb
commit f093429ced
7 changed files with 46 additions and 61 deletions
Download patch file Download diff file Expand all files Collapse all files

15
examples/python/lattice/hexagonal/build-xml.py
View file

@ -1,4 +1,5 @@
import openmc
from openmc.region import Intersection
###############################################################################
@ -68,14 +69,12 @@ cell5 = openmc.Cell(cell_id=600, name='cell 5')
cell6 = openmc.Cell(cell_id=601, name='cell 6')
# Register Surfaces with Cells
cell1.add_surface(left, halfspace=+1)
cell1.add_surface(right, halfspace=-1)
cell1.add_surface(bottom, halfspace=+1)
cell1.add_surface(top, halfspace=-1)
cell2.add_surface(fuel_surf, halfspace=-1)
cell3.add_surface(fuel_surf, halfspace=+1)
cell5.add_surface(fuel_surf, halfspace=-1)
cell6.add_surface(fuel_surf, halfspace=+1)
cell1.region = Intersection(left.positive, right.negative,
bottom.positive, top.negative)
cell2.region = fuel_surf.negative
cell3.region = fuel_surf.positive
cell5.region = fuel_surf.negative
cell6.region = fuel_surf.positive
# Register Materials with Cells
cell2.fill = fuel