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Merge branch 'develop' into source-improvements

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Paul Romano 2016-01-13 21:47:00 -06:00
commit d833f90720
17 changed files with 415 additions and 176 deletions
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4
docs/source/usersguide/input.rst
View file

@ -955,7 +955,9 @@ Each ``<cell>`` element can have the following attributes or sub-elements:
:material:
The ``id`` of the material that this cell contains. If the cell should
contain no material, this can also be set to "void".
contain no material, this can also be set to "void". A list of materials
can be specified for the "distributed material" feature. This will give each
unique instance of the cell its own material.
.. note:: If a material is specified, no fill should be given.

8
docs/source/usersguide/output/summary.rst
View file

@ -91,10 +91,12 @@ The current revision of the summary file format is 1.
Type of fill for the cell. Can be 'normal', 'universe', or 'lattice'.
**/geometry/cells/cell <uid>/material** (*int*)
**/geometry/cells/cell <uid>/material** (*int* or *int[]*)
Unique ID of the material assigned to the cell. This dataset is present only
if fill_type is set to 'normal'.
Unique ID of the material(s) assigned to the cell. This dataset is present
only if fill_type is set to 'normal'. The value '-1' signifies void
material. The data is an array if the cell uses distributed materials,
otherwise it is a scalar.
**/geometry/cells/cell <uid>/offset** (*int[]*)

7
openmc/geometry.py
View file

@ -1,4 +1,4 @@
from collections import OrderedDict
from collections import Iterable, OrderedDict
from xml.etree import ElementTree as ET
import openmc
@ -140,7 +140,10 @@ class Geometry(object):
materials = set()
for cell in material_cells:
materials.add(cell._fill)
if isinstance(cell.fill, Iterable):
for m in cell.fill: materials.add(m)
else:
materials.add(cell.fill)
materials = list(materials)
materials.sort(key=lambda x: x.id)

11
openmc/summary.py
View file

@ -1,3 +1,4 @@
from collections import Iterable
import numpy as np
import re
@ -477,10 +478,14 @@ class Summary(object):
# Retrieve the object corresponding to the fill type and ID
if fill_type == 'normal':
if fill_id > 0:
fill = self.get_material_by_id(fill_id)
if isinstance(fill_id, Iterable):
fill = [self.get_material_by_id(mat) if mat > 0 else 'void'
for mat in fill_id]
else:
fill = 'void'
if fill_id > 0:
fill = self.get_material_by_id(fill_id)
else:
fill = 'void'
elif fill_type == 'universe':
fill = self.get_universe_by_id(fill_id)
else:

17
openmc/universe.py
View file

@ -50,7 +50,7 @@ class Cell(object):
Unique identifier for the cell
name : str
Name of the cell
fill : Material or Universe or Lattice or 'void'
fill : Material or Universe or Lattice or 'void' or iterable of Material
Indicates what the region of space is filled with
region : openmc.region.Region
Region of space that is assigned to the cell.
@ -112,6 +112,12 @@ class Cell(object):
if isinstance(self._fill, openmc.Material):
string += '{0: <16}{1}{2}\n'.format('\tMaterial', '=\t',
self._fill._id)
elif isinstance(self._fill, Iterable):
string += '{0: <16}{1}'.format('\tMaterial', '=\t')
string += '['
string += ', '.join(['void' if m == 'void' else str(m.id)
for m in self.fill])
string += ']\n'
elif isinstance(self._fill, (Universe, Lattice)):
string += '{0: <16}{1}{2}\n'.format('\tFill', '=\t',
self._fill._id)
@ -205,6 +211,11 @@ class Cell(object):
elif isinstance(fill, openmc.Material):
self._type = 'normal'
elif isinstance(fill, Iterable):
cv.check_type('cell.fill', fill, Iterable,
(openmc.Material, basestring))
self._type = 'normal'
elif isinstance(fill, Universe):
self._type = 'fill'
@ -394,6 +405,10 @@ class Cell(object):
if isinstance(self._fill, openmc.Material):
element.set("material", str(self._fill._id))
elif isinstance(self._fill, Iterable):
element.set("material", ' '.join([m if m == 'void' else str(m.id)
for m in self.fill]))
elif isinstance(self._fill, (Universe, Lattice)):
element.set("fill", str(self._fill._id))
self._fill.create_xml_subelement(xml_element)

3
src/constants.F90
View file

@ -139,6 +139,9 @@ module constants
! Maximum number of lost particles
integer, parameter :: MAX_LOST_PARTICLES = 10
! Maximum number of lost particles, relative to the total number of particles
real(8), parameter :: REL_MAX_LOST_PARTICLES = 1e-6_8
! ============================================================================
! CROSS SECTION RELATED CONSTANTS

43
src/geometry.F90
View file

@ -193,7 +193,9 @@ contains
logical, intent(inout) :: found
integer, optional :: search_cells(:)
integer :: i ! index over cells
integer :: j ! coordinate level index
integer :: j, k ! coordinate level index
integer :: offset ! instance # of a distributed cell
integer :: distribcell_index
integer :: i_xyz(3) ! indices in lattice
integer :: n ! number of cells to search
integer :: index_cell ! index in cells array
@ -246,9 +248,36 @@ contains
! ======================================================================
! AT LOWEST UNIVERSE, TERMINATE SEARCH
! set material
! Set the particle material
p % last_material = p % material
p % material = c % material
if (size(c % material) == 1) then
! Only one material for this cell; assign that one to the particle.
p % material = c % material(1)
else
! Distributed instances of this cell have different materials.
! Determine which instance this is and assign the matching material.
distribcell_index = c % distribcell_index
offset = 0
do k = 1, p % n_coord
if (cells(p % coord(k) % cell) % type == CELL_FILL) then
offset = offset + cells(p % coord(k) % cell) % &
offset(distribcell_index)
elseif (cells(p % coord(k) % cell) % type == CELL_LATTICE) then
if (lattices(p % coord(k + 1) % lattice) % obj &
% are_valid_indices([&
p % coord(k + 1) % lattice_x, &
p % coord(k + 1) % lattice_y, &
p % coord(k + 1) % lattice_z])) then
offset = offset + lattices(p % coord(k + 1) % lattice) % obj % &
offset(distribcell_index, &
p % coord(k + 1) % lattice_x, &
p % coord(k + 1) % lattice_y, &
p % coord(k + 1) % lattice_z)
end if
end if
end do
p % material = c % material(offset + 1)
end if
elseif (c % type == CELL_FILL) then CELL_TYPE
! ======================================================================
@ -950,6 +979,8 @@ contains
type(Particle), intent(inout) :: p
character(*) :: message
integer(8) :: tot_n_particles
! Print warning and write lost particle file
call warning(message)
call write_particle_restart(p)
@ -959,9 +990,13 @@ contains
!$omp atomic
n_lost_particles = n_lost_particles + 1
! Count the total number of simulated particles (on this processor)
tot_n_particles = n_batches * gen_per_batch * work
! Abort the simulation if the maximum number of lost particles has been
! reached
if (n_lost_particles == MAX_LOST_PARTICLES) then
if (n_lost_particles >= MAX_LOST_PARTICLES .and. &
n_lost_particles >= REL_MAX_LOST_PARTICLES * tot_n_particles) then
call fatal_error("Maximum number of lost particles has been reached.")
end if

7
src/geometry_header.F90
View file

@ -126,9 +126,10 @@ module geometry_header
integer :: fill ! universe # filling this cell
integer :: instances ! number of instances of this cell in
! the geom
integer :: material ! Material within cell (0 for
! universe)
integer, allocatable :: offset (:) ! Distribcell offset for tally
integer, allocatable :: material(:) ! Material within cell. Multiple
! materials for distribcell
! instances. 0 signifies a universe
integer, allocatable :: offset(:) ! Distribcell offset for tally
! counter
integer, allocatable :: region(:) ! Definition of spatial region as
! Boolean expression of half-spaces

230
src/initialize.F90
View file

@ -614,31 +614,33 @@ contains
! =======================================================================
! ADJUST MATERIAL/FILL POINTERS FOR EACH CELL
id = c%material
if (id == MATERIAL_VOID) then
c%type = CELL_NORMAL
elseif (id /= 0) then
if (material_dict%has_key(id)) then
c%type = CELL_NORMAL
c%material = material_dict%get_key(id)
else
call fatal_error("Could not find material " // trim(to_str(id)) &
&// " specified on cell " // trim(to_str(c%id)))
end if
else
id = c%fill
if (universe_dict%has_key(id)) then
c%type = CELL_FILL
c%fill = universe_dict%get_key(id)
elseif (lattice_dict%has_key(id)) then
lid = lattice_dict%get_key(id)
c%type = CELL_LATTICE
c%fill = lid
if (c % material(1) == NONE) then
id = c % fill
if (universe_dict % has_key(id)) then
c % type = CELL_FILL
c % fill = universe_dict % get_key(id)
elseif (lattice_dict % has_key(id)) then
lid = lattice_dict % get_key(id)
c % type = CELL_LATTICE
c % fill = lid
else
call fatal_error("Specified fill " // trim(to_str(id)) // " on cell "&
&// trim(to_str(c%id)) // " is neither a universe nor a &
// trim(to_str(c % id)) // " is neither a universe nor a &
&lattice.")
end if
else
do j = 1, size(c % material)
id = c % material(j)
if (id == MATERIAL_VOID) then
c % type = CELL_NORMAL
else if (material_dict % has_key(id)) then
c % type = CELL_NORMAL
c % material(j) = material_dict % get_key(id)
else
call fatal_error("Could not find material " // trim(to_str(id)) &
// " specified on cell " // trim(to_str(c % id)))
end if
end do
end if
end do
@ -943,86 +945,82 @@ contains
subroutine prepare_distribcell()
integer :: i, j ! Tally, filter loop counters
integer :: n_filt ! Number of filters originally in tally
logical :: count_all ! Count all cells
type(TallyObject), pointer :: t ! Current tally
type(Universe), pointer :: univ ! Pointer to universe
type(Cell), pointer :: c ! Pointer to cell
integer :: i, j ! Tally, filter loop counters
logical :: distribcell_active ! Does simulation use distribcell?
integer, allocatable :: univ_list(:) ! Target offsets
integer, allocatable :: counts(:,:) ! Target count
logical, allocatable :: found(:,:) ! Target found
count_all = .false.
! Assume distribcell is not needed until proven otherwise.
distribcell_active = .false.
! Loop over tallies
! We need distribcell if any tallies have distribcell filters.
do i = 1, n_tallies
! Get pointer to tally
t => tallies(i)
n_filt = t%n_filters
! Loop over the filters to determine how many additional filters
! need to be added to this tally
do j = 1, t%n_filters
! Determine type of filter
if (t%filters(j)%type == FILTER_DISTRIBCELL) then
count_all = .true.
if (size(t%filters(j)%int_bins) > 1) then
do j = 1, tallies(i) % n_filters
if (tallies(i) % filters(j) % type == FILTER_DISTRIBCELL) then
distribcell_active = .true.
if (size(tallies(i) % filters(j) % int_bins) > 1) then
call fatal_error("A distribcell filter was specified with &
&multiple bins. This feature is not supported.")
end if
end if
end do
end do
if (count_all) then
univ => universes(BASE_UNIVERSE)
! sum the number of occurrences of all cells
call count_instance(univ)
! Loop over tallies
do i = 1, n_tallies
! Get pointer to tally
t => tallies(i)
! Initialize the filters
do j = 1, t%n_filters
! Set the number of bins to the number of instances of the cell
if (t%filters(j)%type == FILTER_DISTRIBCELL) then
c => cells(t%filters(j)%int_bins(1))
t%filters(j)%n_bins = c%instances
end if
end do
! We also need distribcell if any distributed materials are present.
if (.not. distribcell_active) then
do i = 1, n_cells
if (size(cells(i) % material) > 1) then
distribcell_active = .true.
exit
end if
end do
end if
! If distribcell isn't used in this simulation then no more work left to do.
if (.not. distribcell_active) return
! Count the number of instances of each cell.
call count_instance(universes(BASE_UNIVERSE))
! Set the number of bins in all distribcell filters.
do i = 1, n_tallies
do j = 1, tallies(i) % n_filters
associate (filt => tallies(i) % filters(j))
if (filt % type == FILTER_DISTRIBCELL) then
! Set the number of bins to the number of instances of the cell.
filt % n_bins = cells(filt % int_bins(1)) % instances
end if
end associate
end do
end do
! Make sure the number of materials matches the number of cell instances for
! distributed materials.
do i = 1, n_cells
associate (c => cells(i))
if (size(c % material) > 1) then
if (size(c % material) /= c % instances) then
call fatal_error("Cell " // trim(to_str(c % id)) // " was &
&specified with " // trim(to_str(size(c % material))) &
// " materials but has " // trim(to_str(c % instances)) &
// " distributed instances. The number of materials must &
&equal one or the number of instances.")
end if
end if
end associate
end do
! Allocate offset maps at each level in the geometry
call allocate_offsets(univ_list, counts, found)
! Calculate offsets for each target distribcell
do i = 1, n_maps
do j = 1, n_universes
univ => universes(j)
call calc_offsets(univ_list(i), i, univ, counts, found)
call calc_offsets(univ_list(i), i, universes(j), counts, found)
end do
end do
! Deallocate temporary target variable arrays
deallocate(counts)
deallocate(found)
deallocate(univ_list)
end subroutine prepare_distribcell
!===============================================================================
@ -1036,38 +1034,33 @@ contains
integer, intent(out), allocatable :: counts(:,:) ! Target count
logical, intent(out), allocatable :: found(:,:) ! Target found
integer :: i, j, k, l, m ! Loop counters
type(SetInt) :: cell_list ! distribells to track
type(Universe), pointer :: univ ! pointer to universe
class(Lattice), pointer :: lat ! pointer to lattice
type(TallyObject), pointer :: t ! pointer to tally
type(TallyFilter), pointer :: filter ! pointer to filter
integer :: i, j, k ! Loop counters
type(SetInt) :: cell_list ! distribells to track
! Begin gathering list of cells in distribcell tallies
n_maps = 0
! Populate list of distribcells to track
! List all cells referenced in distribcell filters.
do i = 1, n_tallies
t => tallies(i)
do j = 1, t % n_filters
filter => t % filters(j)
if (filter % type == FILTER_DISTRIBCELL) then
if (.not. cell_list % contains(filter % int_bins(1))) then
call cell_list % add(filter % int_bins(1))
end if
do j = 1, tallies(i) % n_filters
if (tallies(i) % filters(j) % type == FILTER_DISTRIBCELL) then
call cell_list % add(tallies(i) % filters(j) % int_bins(1))
end if
end do
end do
! List all cells with multiple (distributed) materials.
do i = 1, n_cells
if (size(cells(i) % material) > 1) then
call cell_list % add(i)
end if
end do
! Compute the number of unique universes containing these distribcells
! to determine the number of offset tables to allocate
do i = 1, n_universes
univ => universes(i)
do j = 1, univ % n_cells
if (cell_list % contains(univ % cells(j))) then
do j = 1, universes(i) % n_cells
if (cell_list % contains(universes(i) % cells(j))) then
n_maps = n_maps + 1
end if
end do
@ -1076,24 +1069,23 @@ contains
! Allocate the list of offset tables for each unique universe
allocate(univ_list(n_maps))
! Allocate list to accumulate target distribccell counts in each universe
! Allocate list to accumulate target distribcell counts in each universe
allocate(counts(n_universes, n_maps))
counts(:,:) = 0
! Allocate list to track if target distribcells are found in each universe
allocate(found(n_universes, n_maps))
counts(:,:) = 0
found(:,:) = .false.
k = 1
! Search through universes for distributed cells and assign each one a
! unique distribcell array index.
k = 1
do i = 1, n_universes
univ => universes(i)
do j = 1, univ % n_cells
if (cell_list % contains(univ % cells(j))) then
cells(univ % cells(j)) % distribcell_index = k
univ_list(k) = univ % id
do j = 1, universes(i) % n_cells
if (cell_list % contains(universes(i) % cells(j))) then
cells(universes(i) % cells(j)) % distribcell_index = k
univ_list(k) = universes(i) % id
k = k + 1
end if
end do
@ -1101,29 +1093,31 @@ contains
! Allocate the offset tables for lattices
do i = 1, n_lattices
lat => lattices(i) % obj
associate(lat => lattices(i) % obj)
select type(lat)
select type(lat)
type is (RectLattice)
allocate(lat % offset(n_maps, lat % n_cells(1), lat % n_cells(2), &
lat % n_cells(3)))
type is (HexLattice)
allocate(lat % offset(n_maps, 2 * lat % n_rings - 1, &
2 * lat % n_rings - 1, lat % n_axial))
end select
lat % offset(:, :, :, :) = 0
type is (RectLattice)
allocate(lat % offset(n_maps, lat % n_cells(1), lat % n_cells(2), &
lat % n_cells(3)))
type is (HexLattice)
allocate(lat % offset(n_maps, 2 * lat % n_rings - 1, &
2 * lat % n_rings - 1, lat % n_axial))
end select
lat % offset(:, :, :, :) = 0
end associate
end do
! Allocate offset table for fill cells
do i = 1, n_cells
if (cells(i) % material == NONE) then
if (cells(i) % type /= CELL_NORMAL) then
allocate(cells(i) % offset(n_maps))
end if
end do
! Free up memory
call cell_list % clear()
end subroutine allocate_offsets
end module initialize

56
src/input_xml.F90
View file

@ -1059,8 +1059,7 @@ contains
subroutine read_geometry_xml()
integer :: i, j, k, m, i_x, i_a, input_index
integer :: n
integer :: n_x, n_y, n_z, n_rings, n_rlats, n_hlats
integer :: n, n_mats, n_x, n_y, n_z, n_rings, n_rlats, n_hlats
integer :: universe_num
integer :: n_cells_in_univ
integer :: coeffs_reqd
@ -1071,6 +1070,7 @@ contains
logical :: boundary_exists
character(MAX_LINE_LEN) :: filename
character(MAX_WORD_LEN) :: word
character(MAX_WORD_LEN), allocatable :: sarray(:)
character(REGION_SPEC_LEN) :: region_spec
type(Cell), pointer :: c
class(Surface), pointer :: s
@ -1163,36 +1163,50 @@ contains
end if
! Read material
word = ''
if (check_for_node(node_cell, "material")) &
call get_node_value(node_cell, "material", word)
select case(to_lower(word))
case ('void')
c % material = MATERIAL_VOID
if (check_for_node(node_cell, "material")) then
n_mats = get_arraysize_string(node_cell, "material")
case ('')
! This case is called if no material was specified
c % material = NONE
if (n_mats > 0) then
allocate(sarray(n_mats))
call get_node_array(node_cell, "material", sarray)
case default
c % material = int(str_to_int(word), 4)
allocate(c % material(n_mats))
do j = 1, n_mats
select case(trim(to_lower(sarray(j))))
case ('void')
c % material(j) = MATERIAL_VOID
case default
c % material(j) = int(str_to_int(sarray(j)), 4)
! Check for error
if (c % material == ERROR_INT) then
call fatal_error("Invalid material specified on cell " &
&// to_str(c % id))
! Check for error
if (c % material(j) == ERROR_INT) then
call fatal_error("Invalid material specified on cell " &
// to_str(c % id))
end if
end select
end do
deallocate(sarray)
else
allocate(c % material(1))
c % material(1) = NONE
end if
end select
else
allocate(c % material(1))
c % material(1) = NONE
end if
! Check to make sure that either material or fill was specified
if (c % material == NONE .and. c % fill == NONE) then
if (c % material(1) == NONE .and. c % fill == NONE) then
call fatal_error("Neither material nor fill was specified for cell " &
&// trim(to_str(c % id)))
// trim(to_str(c % id)))
end if
! Check to make sure that both material and fill haven't been
! specified simultaneously
if (c % material /= NONE .and. c % fill /= NONE) then
if (c % material(1) /= NONE .and. c % fill /= NONE) then
call fatal_error("Cannot specify material and fill simultaneously")
end if

14
src/plot.F90
View file

@ -82,17 +82,17 @@ contains
if (pl % color_by == PLOT_COLOR_MATS) then
! Assign color based on material
c => cells(p % coord(j) % cell)
if (c % material == MATERIAL_VOID) then
! By default, color void cells white
rgb = 255
id = -1
else if (c % type == CELL_FILL) then
if (c % type == CELL_FILL) then
! If we stopped on a middle universe level, treat as if not found
rgb = pl % not_found % rgb
id = -1
else if (p % material == MATERIAL_VOID) then
! By default, color void cells white
rgb = 255
id = -1
else
rgb = pl % colors(c % material) % rgb
id = materials(c % material) % id
rgb = pl % colors(p % material) % rgb
id = materials(p % material) % id
end if
else if (pl % color_by == PLOT_COLOR_CELLS) then
! Assign color based on cell

4
src/relaxng/geometry.rnc
View file

@ -6,8 +6,8 @@ element geometry {
(element universe { xsd:int } | attribute universe { xsd:int })? &
(
(element fill { xsd:int } | attribute fill { xsd:int }) |
(element material { ( xsd:int | "void" ) } |
attribute material { ( xsd:int | "void" ) })
(element material { ( xsd:int | "void" )+ } |
attribute material { ( xsd:int | "void" )+ })
) &
(element region { xsd:string } | attribute region { xsd:string })? &
(element rotation { list { xsd:double+ } } | attribute rotation { list { xsd:double+ } })? &

20
src/relaxng/geometry.rng
View file

@ -47,16 +47,20 @@
</choice>
<choice>
<element name="material">
<choice>
<data type="int"/>
<value>void</value>
</choice>
<oneOrMore>
<choice>
<data type="int"/>
<value>void</value>
</choice>
</oneOrMore>
</element>
<attribute name="material">
<choice>
<data type="int"/>
<value>void</value>
</choice>
<oneOrMore>
<choice>
<data type="int"/>
<value>void</value>
</choice>
</oneOrMore>
</attribute>
</choice>
</choice>

21
src/summary.F90
View file

@ -107,6 +107,7 @@ contains
integer :: i, j, k, m
integer, allocatable :: lattice_universes(:,:,:)
integer, allocatable :: cell_materials(:)
integer(HID_T) :: geom_group
integer(HID_T) :: cells_group, cell_group
integer(HID_T) :: surfaces_group, surface_group
@ -150,10 +151,24 @@ contains
select case (c%type)
case (CELL_NORMAL)
call write_dataset(cell_group, "fill_type", "normal")
if (c%material == MATERIAL_VOID) then
call write_dataset(cell_group, "material", -1)
if (size(c % material) == 1) then
if (c % material(1) == MATERIAL_VOID) then
call write_dataset(cell_group, "material", MATERIAL_VOID)
else
call write_dataset(cell_group, "material", &
materials(c % material(1)) % id)
end if
else
call write_dataset(cell_group, "material", materials(c%material)%id)
allocate(cell_materials(size(c % material)))
do j = 1, size(c % material)
if (c % material(j) == MATERIAL_VOID) then
cell_materials(j) = MATERIAL_VOID
else
cell_materials(j) = materials(c % material(j)) % id
end if
end do
call write_dataset(cell_group, "material", cell_materials)
deallocate(cell_materials)
end if
case (CELL_FILL)

1
tests/test_distribmat/inputs_true.dat Normal file
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@ -0,0 +1 @@
83a9f1412b1ddfdd8b9fa8c7e8b44be8137dc6aa785d44c3eea9f0928242475aea4ba73ba4eef01afdf63bd1bff18116e40b798eeafab50c856186de4c68d5a6

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tests/test_distribmat/results_true.dat Normal file
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k-combined:
1.309285E+00 1.263629E-02
Cell
ID = 11
Name =
Material = [2, 3, void, 2]
Region = -10000
Rotation = None
Translation = None
Offset = None
Distribcell index= 1

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tests/test_distribmat/test_distribmat.py Normal file
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#!/usr/bin/env python
import os
import sys
sys.path.insert(0, os.pardir)
from testing_harness import TestHarness, PyAPITestHarness
import openmc
class DistribmatTestHarness(PyAPITestHarness):
def _build_inputs(self):
####################
# Materials
####################
moderator = openmc.Material(material_id=1)
moderator.set_density('g/cc', 1.0)
moderator.add_nuclide('H-1', 2.0)
moderator.add_nuclide('O-16', 1.0)
dense_fuel = openmc.Material(material_id=2)
dense_fuel.set_density('g/cc', 4.5)
dense_fuel.add_nuclide('U-235', 1.0)
light_fuel = openmc.Material(material_id=3)
light_fuel.set_density('g/cc', 2.0)
light_fuel.add_nuclide('U-235', 1.0)
mats_file = openmc.MaterialsFile()
mats_file.default_xs = '71c'
mats_file.add_materials([moderator, dense_fuel, light_fuel])
mats_file.export_to_xml()
####################
# Geometry
####################
c1 = openmc.Cell(cell_id=1)
c1.fill = moderator
mod_univ = openmc.Universe(universe_id=1)
mod_univ.add_cell(c1)
r0 = openmc.ZCylinder(R=0.3)
c11 = openmc.Cell(cell_id=11)
c11.region = -r0
c11.fill = [dense_fuel, light_fuel, 'void', dense_fuel]
c12 = openmc.Cell(cell_id=12)
c12.region = +r0
c12.fill = moderator
fuel_univ = openmc.Universe(universe_id=11)
fuel_univ.add_cells((c11, c12))
lat = openmc.RectLattice(lattice_id=101)
lat.dimension = [2, 2]
lat.lower_left = [-2.0, -2.0]
lat.pitch = [2.0, 2.0]
lat.universes = [[fuel_univ]*2]*2
lat.outer = mod_univ
x0 = openmc.XPlane(x0=-3.0)
x1 = openmc.XPlane(x0=3.0)
y0 = openmc.YPlane(y0=-3.0)
y1 = openmc.YPlane(y0=3.0)
for s in [x0, x1, y0, y1]:
s.boundary_type = 'reflective'
c101 = openmc.Cell(cell_id=101)
c101.region = +x0 & -x1 & +y0 & -y1
c101.fill = lat
root_univ = openmc.Universe(universe_id=0)
root_univ.add_cell(c101)
geometry = openmc.Geometry()
geometry.root_universe = root_univ
geo_file = openmc.GeometryFile()
geo_file.geometry = geometry
geo_file.export_to_xml()
####################
# Settings
####################
sets_file = openmc.SettingsFile()
sets_file.batches = 5
sets_file.inactive = 0
sets_file.particles = 1000
sets_file.set_source_space('box', [-1, -1, -1, 1, 1, 1])
sets_file.output = {'summary': True}
sets_file.export_to_xml()
####################
# Plots
####################
plots_file = openmc.PlotsFile()
plot = openmc.Plot(plot_id=1)
plot.basis = 'xy'
plot.color = 'cell'
plot.filename = 'cellplot'
plot.origin = (0, 0, 0)
plot.width = (7, 7)
plot.pixels = (400, 400)
plots_file.add_plot(plot)
plot = openmc.Plot(plot_id=2)
plot.basis = 'xy'
plot.color = 'mat'
plot.filename = 'matplot'
plot.origin = (0, 0, 0)
plot.width = (7, 7)
plot.pixels = (400, 400)
plots_file.add_plot(plot)
plots_file.export_to_xml()
def _get_results(self):
outstr = super(DistribmatTestHarness, self)._get_results()
su = openmc.Summary('summary.h5')
outstr += str(su.get_cell_by_id(11))
return outstr
def _cleanup(self):
f = os.path.join(os.getcwd(), 'plots.xml')
if os.path.exists(f):
os.remove(f)
super(DistribmatTestHarness, self)._cleanup()
if __name__ == '__main__':
harness = DistribmatTestHarness('statepoint.5.*')
harness.main()