crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-27 05:35:49 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions

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

11
examples/python/basic/build-xml.py
View file

@ -1,5 +1,4 @@
import openmc
from openmc.region import Intersection
###############################################################################
# Simulation Input File Parameters
@ -54,11 +53,11 @@ cell2 = openmc.Cell(cell_id=100, name='cell 2')
cell3 = openmc.Cell(cell_id=101, name='cell 3')
cell4 = openmc.Cell(cell_id=2, name='cell 4')
# Register Surfaces with Cells
cell1.region = surf2.negative
cell2.region = surf1.negative
cell3.region = surf1.positive
cell4.region = Intersection(surf2.positive, surf3.negative)
# Use surface half-spaces to define regions
cell1.region = -surf2
cell2.region = -surf1
cell3.region = +surf1
cell4.region = +surf2 & -surf3
# Register Materials with Cells
cell2.fill = fuel

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

21
examples/python/lattice/nested/build-xml.py
View file

@ -1,5 +1,4 @@
import openmc
from openmc.region import Intersection
###############################################################################
@ -67,17 +66,15 @@ cell6 = openmc.Cell(cell_id=202, name='cell 6')
cell7 = openmc.Cell(cell_id=301, name='cell 7')
cell8 = openmc.Cell(cell_id=302, name='cell 8')
# Register Surfaces with Cells
cell1.region = Intersection(left.positive, right.negative,
bottom.positive, top.negative)
cell2.region = Intersection(left.positive, right.negative,
bottom.positive, top.negative)
cell3.region = fuel1.negative
cell4.region = fuel1.positive
cell5.region = fuel2.negative
cell6.region = fuel2.positive
cell7.region = fuel3.negative
cell8.region = fuel3.positive
# Use surface half-space to define regions
cell1.region = +left & -right & +bottom & -top
cell2.region = +left & -right & +bottom & -top
cell3.region = -fuel1
cell4.region = +fuel1
cell5.region = -fuel2
cell6.region = +fuel2
cell7.region = -fuel3
cell8.region = +fuel3
# Register Materials with Cells
cell3.fill = fuel

18
examples/python/lattice/simple/build-xml.py
View file

@ -1,5 +1,4 @@
import openmc
from openmc.region import Intersection
###############################################################################
# Simulation Input File Parameters
@ -65,15 +64,14 @@ cell5 = openmc.Cell(cell_id=202, name='cell 5')
cell6 = openmc.Cell(cell_id=301, name='cell 6')
cell7 = openmc.Cell(cell_id=302, name='cell 7')
# Register Regions with Cells
cell1.region = Intersection(left.positive, right.negative,
bottom.positive, top.negative)
cell2.region = fuel1.negative
cell3.region = fuel1.positive
cell4.region = fuel2.negative
cell5.region = fuel2.positive
cell6.region = fuel3.negative
cell7.region = fuel3.positive
# Use surface half-spaces to define regions
cell1.region = +left & -right & +bottom & -top
cell2.region = -fuel1
cell3.region = +fuel1
cell4.region = -fuel2
cell5.region = +fuel2
cell6.region = -fuel3
cell7.region = +fuel3
# Register Materials with Cells
cell2.fill = fuel

12
examples/python/pincell/build-xml.py
View file

@ -1,5 +1,4 @@
import openmc
from openmc.region import Intersection
###############################################################################
# Simulation Input File Parameters
@ -132,12 +131,11 @@ gap = openmc.Cell(cell_id=2, name='cell 2')
clad = openmc.Cell(cell_id=3, name='cell 3')
water = openmc.Cell(cell_id=4, name='cell 4')
# Register Surfaces with Cells
fuel.region = fuel_or.negative
gap.region = Intersection(fuel_or.positive, clad_ir.negative)
clad.region = Intersection(clad_ir.positive, clad_or.negative)
water.region = Intersection(clad_or.positive, left.positive, right.negative,
bottom.positive, top.negative)
# Use surface half-spaces to define regions
fuel.region = -fuel_or
gap.region = +fuel_or & -clad_ir
clad.region = +clad_ir & -clad_or
water.region = +clad_or & +left & -right & +bottom & -top
# Register Materials with Cells
fuel.fill = uo2

7
examples/python/reflective/build-xml.py
View file

@ -1,5 +1,4 @@
import openmc
from openmc.region import Intersection
###############################################################################
# Simulation Input File Parameters
@ -52,10 +51,8 @@ surf6.boundary_type = 'reflective'
# Instantiate Cell
cell = openmc.Cell(cell_id=1, name='cell 1')
# Register Region with Cell
cell.region = Intersection(surf1.positive, surf2.negative,
surf3.positive, surf4.negative,
surf5.positive, surf6.negative)
# Use surface half-spaces to define region
cell.region = +surf1 & -surf2 & +surf3 & -surf4 & +surf5 & -surf6
# Register Material with Cell
cell.fill = fuel