crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-28 14:15:42 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions 5

Update example inputs and Jupyter notebooks

Browse source
This commit is contained in:
Paul Romano 2015-10-03 09:55:58 +07:00
parent 71dfde8d12
commit b9024f2d8e
11 changed files with 117 additions and 140 deletions
Download patch file Download diff file Expand all files Collapse all files

14
examples/python/lattice/hexagonal/build-xml.py
View file

@ -1,5 +1,4 @@
import openmc
from openmc.region import Intersection
###############################################################################
@ -68,13 +67,12 @@ cell4 = openmc.Cell(cell_id=500, name='cell 4')
cell5 = openmc.Cell(cell_id=600, name='cell 5')
cell6 = openmc.Cell(cell_id=601, name='cell 6')
# Register Surfaces with Cells
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
# Use surface half-spaces to define regions
cell1.region = +left & -right & +bottom & -top
cell2.region = -fuel_surf
cell3.region = +fuel_surf
cell5.region = -fuel_surf
cell6.region = +fuel_surf
# Register Materials with Cells
cell2.fill = fuel