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Merge remote-tracking branch 'sterling/multipole' into multipole-final

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Colin Josey 2016-02-04 20:17:44 -05:00
commit 1b96075cbb
18 changed files with 394 additions and 60 deletions
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9
docs/source/usersguide/input.rst
View file

@ -987,6 +987,15 @@ Each ``<cell>`` element can have the following attributes or sub-elements:
*Default*: A region filling all space.
:temperature:
The temperature of the cell in Kelvin. If windowed-multipole data is
avalable, this temperature will be used to Doppler broaden some cross
sections in the resolved resonance region. A list of temperatures can be
specified for the "distributed temperature" feature. This will give each
unique instance of the cell its own temperature.
*Default*: The temperature of the coldest nuclide in the cell's material(s)
:rotation:
If the cell is filled with a universe, this element specifies the angles in
degrees about the x, y, and z axes that the filled universe should be

4
docs/source/usersguide/output/summary.rst
View file

@ -98,6 +98,10 @@ The current revision of the summary file format is 1.
material. The data is an array if the cell uses distributed materials,
otherwise it is a scalar.
**/geometry/cells/cell <uid>/temperature** (*double[]*)
Temperature of the cell in Kelvin.
**/geometry/cells/cell <uid>/offset** (*int[]*)
Offsets used for distribcell tally filter. This dataset is present only if

3
openmc/summary.py
View file

@ -264,6 +264,9 @@ class Summary(object):
self._f['geometry/cells'][key]['rotation'][...]
rotation = np.asarray(rotation, dtype=np.int)
cell.rotation = rotation
elif fill_type == 'normal':
cell.temperature = \
self._f['geometry/cells'][key]['temperature'][...]
# Store Cell fill information for after Universe/Lattice creation
self._cell_fills[index] = (fill_type, fill)

37
openmc/universe.py
View file

@ -51,9 +51,13 @@ class Cell(object):
name : str
Name of the cell
fill : Material or Universe or Lattice or 'void' or iterable of Material
Indicates what the region of space is filled with
Indicates what the region of space is filled with. Multiple materials
can be given to give each distributed cell instance a unique material.
region : openmc.region.Region
Region of space that is assigned to the cell.
temperature : float or iterable of float
Temperature of the cell in Kelvin. Multiple temperatures can be given
to give each distributed cell instance a unique temperature.
rotation : ndarray
If the cell is filled with a universe, this array specifies the angles
in degrees about the x, y, and z axes that the filled universe should be
@ -75,6 +79,7 @@ class Cell(object):
self._fill = None
self._type = None
self._region = None
self._temperature = None
self._rotation = None
self._translation = None
self._offsets = None
@ -91,6 +96,8 @@ class Cell(object):
return False
elif self.region != other.region:
return False
elif self.temperature != other.temperature:
return False
elif self.rotation != other.rotation:
return False
elif self.translation != other.translation:
@ -126,6 +133,10 @@ class Cell(object):
string += '{0: <16}{1}{2}\n'.format('\tRegion', '=\t', self._region)
if self.fill_type == 'material':
string += '\t{0: <15}=\t{1}\n'.format('Temperature',
self.temperature)
string += '{0: <16}{1}{2}\n'.format('\tRotation', '=\t',
self._rotation)
string += '{0: <16}{1}{2}\n'.format('\tTranslation', '=\t',
@ -150,7 +161,7 @@ class Cell(object):
@property
def fill_type(self):
if isinstance(self.fill, openmc.Material):
if isinstance(self.fill, (openmc.Material, Iterable)):
return 'material'
elif isinstance(self.fill, openmc.Universe):
return 'universe'
@ -163,6 +174,10 @@ class Cell(object):
def region(self):
return self._region
@property
def temperature(self):
return self._temperature
@property
def rotation(self):
return self._rotation
@ -251,6 +266,17 @@ class Cell(object):
cv.check_type('cell region', region, Region)
self._region = region
@temperature.setter
def temperature(self, temperature):
cv.check_type('cell temperature', temperature, (Iterable, Real))
if isinstance(temperature, Iterable):
cv.check_type('cell temperature', temperature, Iterable, Real)
for T in temperature:
cv.check_greater_than('cell temperature', T, 0.0, True)
else:
cv.check_greater_than('cell temperature', temperature, 0.0, True)
self._temperature = temperature
@distribcell_index.setter
def distribcell_index(self, ind):
cv.check_type('distribcell index', ind, Integral)
@ -445,6 +471,13 @@ class Cell(object):
# Call the recursive function from the top node
create_surface_elements(self.region, xml_element)
if self.temperature is not None:
if isinstance(self.temperature, Iterable):
element.set("temperature", ' '.join(
[str(t) for t in self.temperature]))
else:
element.set("temperature", str(self.temperature))
if self.translation is not None:
element.set("translation", ' '.join(map(str, self.translation)))

36
src/cross_section.F90
View file

@ -105,10 +105,13 @@ contains
i_nuclide = mat % nuclide(i)
! Calculate microscopic cross section for this nuclide
if (p % E /= micro_xs(i_nuclide) % last_E .or. mat % sqrtkT /= micro_xs(i_nuclide) % last_sqrtkT) then
call calculate_nuclide_xs(i_nuclide, i_sab, p % E, p % material, i, i_grid, mat % sqrtkT)
if (p % E /= micro_xs(i_nuclide) % last_E &
.or. p % sqrtkT /= micro_xs(i_nuclide) % last_sqrtkT) then
call calculate_nuclide_xs(i_nuclide, i_sab, p % E, p % material, i, &
i_grid, p % sqrtkT)
else if (i_sab /= micro_xs(i_nuclide) % last_index_sab) then
call calculate_nuclide_xs(i_nuclide, i_sab, p % E, p % material, i, i_grid, mat % sqrtkT)
call calculate_nuclide_xs(i_nuclide, i_sab, p % E, p % material, i, &
i_grid, p % sqrtkT)
end if
! ========================================================================
@ -145,7 +148,8 @@ contains
! given index in the nuclides array at the energy of the given particle
!===============================================================================
subroutine calculate_nuclide_xs(i_nuclide, i_sab, E, i_mat, i_nuc_mat, i_log_union, sqrtkT)
subroutine calculate_nuclide_xs(i_nuclide, i_sab, E, i_mat, i_nuc_mat, &
i_log_union, sqrtkT)
integer, intent(in) :: i_nuclide ! index into nuclides array
integer, intent(in) :: i_sab ! index into sab_tables array
real(8), intent(in) :: E ! energy
@ -590,14 +594,20 @@ contains
! sections in the resolved resonance regions
!===============================================================================
subroutine multipole_eval(multipole, Emev, sqrtkT, sigT, sigA, sigF)
type(MultipoleArray), intent(in) :: multipole ! The windowed multipole object to process.
real(8), intent(in) :: Emev ! The energy at which to evaluate the cross section in MeV
real(8), intent(in) :: sqrtkT ! The temperature in the form sqrt(kT (in eV)), at which to evaluate the cross section.
real(8), intent(out) :: sigT ! Total cross section
real(8), intent(out) :: sigA ! Absorption cross section
real(8), intent(out) :: sigF ! Fission cross section
complex(8) :: psi_ki ! The value of the psi-ki function for the asymptotic form
subroutine multipole_eval(multipole, Emev, sqrtkT_, sigT, sigA, sigF)
type(MultipoleArray), intent(in) :: multipole ! The windowed multipole
! object to process.
real(8), intent(in) :: Emev ! The energy at which to
! evaluate the cross section
! in MeV
real(8), intent(in) :: sqrtkT_ ! The temperature in the form
! sqrt(kT (in MeV)), at which
! to evaluate the XS.
real(8), intent(out) :: sigT ! Total cross section
real(8), intent(out) :: sigA ! Absorption cross section
real(8), intent(out) :: sigF ! Fission cross section
complex(8) :: psi_ki ! The value of the psi-ki function for the asymptotic
! form
complex(8) :: c_temp ! complex temporary variable
complex(8) :: w_val ! The faddeeva function evaluated at Z
complex(8) :: Z ! sqrt(atomic weight ratio / kT) * (sqrt(E) - pole)
@ -607,6 +617,7 @@ contains
real(8) :: dopp_ecoef ! sqrt(atomic weight ratio * pi / kT) / E
real(8) :: temp ! real temporary value
real(8) :: E ! energy, eV
real(8) :: sqrtkT ! sqrt(kT (in eV))
integer :: iP ! index of pole
integer :: iC ! index of curvefit
integer :: iW ! index of window
@ -617,6 +628,7 @@ contains
! Convert to eV
E = Emev * 1.0e6_8
sqrtkT = sqrtkT_ * 1.0e3_8
sqrtE = sqrt(E)
invE = ONE/E

30
src/geometry.F90
View file

@ -279,6 +279,36 @@ contains
p % material = c % material(offset + 1)
end if
! Set the particle temperature
if (size(c % sqrtkT) == 1) then
! Only one temperature for this cell; assign that one to the particle.
p % sqrtkT = c % sqrtkT(1)
else
! Distributed instances of this cell have different temperatures.
! Determine which instance this is and assign the matching temp.
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 % sqrtkT = c % sqrtkT(offset + 1)
end if
elseif (c % type == CELL_FILL) then CELL_TYPE
! ======================================================================
! CELL CONTAINS LOWER UNIVERSE, RECURSIVELY FIND CELL

3
src/geometry_header.F90
View file

@ -139,6 +139,9 @@ module geometry_header
! only)
integer :: distribcell_index ! Index corresponding to this cell in
! distribcell arrays
real(8), allocatable :: sqrtkT(:) ! Square root of k_Boltzmann *
! temperature in MeV. Multiple for
! distribcell
! Rotation matrix and translation vector
real(8), allocatable :: translation(:)

78
src/initialize.F90
View file

@ -120,6 +120,9 @@ contains
! Create linked lists for multiple instances of the same nuclide
call same_nuclide_list()
! Set undefined cell temperatures to match the material data.
call lookup_material_temperatures()
! Construct unionized or log energy grid for cross-sections
select case (grid_method)
case (GRID_NUCLIDE)
@ -967,10 +970,11 @@ contains
end do
end do
! We also need distribcell if any distributed materials are present.
! We also need distribcell if any distributed materials or distributed
! temperatues are present.
if (.not. distribcell_active) then
do i = 1, n_cells
if (size(cells(i) % material) > 1) then
if (size(cells(i) % material) > 1 .or. size(cells(i) % sqrtkT) > 1) then
distribcell_active = .true.
exit
end if
@ -995,8 +999,8 @@ contains
end do
end do
! Make sure the number of materials matches the number of cell instances for
! distributed materials.
! Make sure the number of materials and temperatures matches the number of
! cell instances.
do i = 1, n_cells
associate (c => cells(i))
if (size(c % material) > 1) then
@ -1008,6 +1012,15 @@ contains
&equal one or the number of instances.")
end if
end if
if (size(c % sqrtkT) > 1) then
if (size(c % sqrtkT) /= c % instances) then
call fatal_error("Cell " // trim(to_str(c % id)) // " was &
&specified with " // trim(to_str(size(c % sqrtkT))) &
// " temperatures but has " // trim(to_str(c % instances)) &
// " distributed instances. The number of temperatures must &
&equal one or the number of instances.")
end if
end if
end associate
end do
@ -1049,9 +1062,9 @@ contains
end do
end do
! List all cells with multiple (distributed) materials.
! List all cells with multiple (distributed) materials or temperatures.
do i = 1, n_cells
if (size(cells(i) % material) > 1) then
if (size(cells(i) % material) > 1 .or. size(cells(i) % sqrtkT) > 1) then
call cell_list % add(i)
end if
end do
@ -1120,4 +1133,57 @@ contains
end subroutine allocate_offsets
!===============================================================================
! LOOKUP_MATERIAL_TEMPERATURES If any cells have undefined temperatures, try to
! find their temperatures from material data.
!===============================================================================
subroutine lookup_material_temperatures()
integer :: i, j, k
real(8) :: min_temp
logical :: warning_given
warning_given = .false.
do i = 1, n_cells
! Ignore non-normal cells and cells with defined temperature.
if (cells(i) % type /= CELL_NORMAL) cycle
if (cells(i) % sqrtkT(1) /= ERROR_REAL) cycle
! Set the number of temperatures equal to the number of materials.
deallocate(cells(i) % sqrtkT)
allocate(cells(i) % sqrtkT(size(cells(i) % material)))
! Check each of the cell materials for temperature data.
do j = 1, size(cells(i) % material)
! Arbitrarily set void regions to 0K.
if (cells(i) % material(j) == MATERIAL_VOID) then
cells(i) % sqrtkT(j) = ZERO
cycle
end if
associate (mat => materials(cells(i) % material(j)))
! Find the temperature of the coldest nuclide.
min_temp = nuclides(mat % nuclide(1)) % kT
do k = 2, mat % n_nuclides
! Warn the user if the nuclides don't have identical temperatues.
if (nuclides(mat % nuclide(k)) % kT /= min_temp &
.and. .not. warning_given) then
call warning("OpenMC cannot &
&identify the temperature of at least one cell. For the &
&purposes of multipole cross section evaluations, all cells &
&with unknown temperature will be set to the coldest &
&temperature found in the nuclear data for that cell's &
&material")
warning_given = .true.
end if
min_temp = min(min_temp, nuclides(mat % nuclide(k)) % kT)
end do
! Set the temperature for this cell instance.
cells(i) % sqrtkT(j) = sqrt(min_temp)
end associate
end do
end do
end subroutine lookup_material_temperatures
end module initialize

72
src/input_xml.F90
View file

@ -1297,6 +1297,40 @@ contains
call get_node_array(node_cell, "translation", c % translation)
end if
! Read cell temperatures. If the temperature is not specified, set it to
! ERROR_REAL for now. During initialization we'll replace ERROR_REAL with
! the temperature from the material data.
if (check_for_node(node_cell, "temperature")) then
n = get_arraysize_double(node_cell, "temperature")
if (n > 0) then
! Make sure this is a "normal" cell.
if (c % material(1) == NONE) call fatal_error("Cell " &
// trim(to_str(c % id)) // " was specified with a temperature &
&but no material. Temperature specification is only valid for &
&cells filled with a material.")
! Copy in temperatures
allocate(c % sqrtkT(n))
call get_node_array(node_cell, "temperature", c % sqrtkT)
! Make sure all temperatues are positive
do j = 1, size(c % sqrtkT)
if (c % sqrtkT(j) < ZERO) call fatal_error("Cell " &
// trim(to_str(c % id)) // " was specified with a negative &
&temperature. All cell temperatures must be non-negative.")
end do
! Convert to sqrt(kT)
c % sqrtkT(:) = sqrt(K_BOLTZMANN * c % sqrtkT(:))
else
allocate(c % sqrtkT(1))
c % sqrtkT(1) = ERROR_REAL
end if
else
allocate(c % sqrtkT(1))
c % sqrtkT = ERROR_REAL
end if
! Add cell to dictionary
call cell_dict % add_key(c % id, i)
@ -1854,7 +1888,6 @@ contains
real(8) :: temp_dble ! temporary double prec. real
logical :: file_exists ! does materials.xml exist?
logical :: sum_density ! density is taken to be sum of nuclide densities
logical :: temp_known ! Has the temperature yet been defined?
character(12) :: name ! name of isotope, e.g. 92235.03c
character(12) :: alias ! alias of nuclide, e.g. U-235.03c
character(MAX_WORD_LEN) :: units ! units on density
@ -1938,17 +1971,6 @@ contains
cycle
end if
! =======================================================================
! READ AND PARSE <temperature> TAG
if (check_for_node(node_mat, "temperature")) then
call get_node_ptr(node_mat, "temperature", node_temp)
call get_node_value(node_temp, "value", temp_dble)
mat % sqrtkT = sqrt(temp_dble * K_BOLTZMANN * 1.0D6)
temp_known = .true.
else
temp_known = .false.
end if
! =======================================================================
! READ AND PARSE <density> TAG
@ -2055,16 +2077,6 @@ contains
call get_node_value(node_nuc, "xs", name)
name = trim(temp_str) // "." // trim(name)
! If needed, look up temperature
if (.not. temp_known) then
! Find xs_listing and set the name/alias according to the listing
index_list = xs_listing_dict % get_key(to_lower(name))
if(xs_listings(index_list) % kT /= 0.0_8) then
mat % sqrtkT = sqrt(xs_listings(index_list) % kT * 1.0D6)
temp_known = .true.
end if
end if
! save name and density to list
call list_names % append(name)
@ -2153,16 +2165,6 @@ contains
temp_str = "data"
end if
! If still needed, look up temperature
if (.not. temp_known) then
! Find xs_listing and set kT
index_list = xs_listing_dict % get_key(to_lower(list_names % tail % data))
if(xs_listings(index_list) % kT /= 0.0_8) then
mat % sqrtkT = sqrt(xs_listings(index_list) % kT * 1.0D6)
temp_known = .true.
end if
end if
! Set ace or iso-in-lab scattering for each nuclide in element
do k = 1, n_nuc_ele
if (adjustl(to_lower(temp_str)) == "iso-in-lab") then
@ -2177,12 +2179,6 @@ contains
end do NATURAL_ELEMENTS
! If still undefined, set the temperature to zero
if (.not. temp_known) then
mat % sqrtkT = 0.0_8
temp_known = .true.
end if
! ========================================================================
! COPY NUCLIDES TO ARRAYS IN MATERIAL

1
src/material_header.F90
View file

@ -13,7 +13,6 @@ module material_header
integer, allocatable :: nuclide(:) ! index in nuclides array
real(8) :: density ! total atom density in atom/b-cm
real(8), allocatable :: atom_density(:) ! nuclide atom density in atom/b-cm
real(8) :: sqrtkT ! sqrt(kT), kT in eV
! Energy grid information
integer :: n_grid ! # of union material grid points

6
src/particle_header.F90
View file

@ -2,7 +2,7 @@ module particle_header
use bank_header, only: Bank
use constants, only: NEUTRON, ONE, NONE, ZERO, MAX_SECONDARY, &
MAX_DELAYED_GROUPS
MAX_DELAYED_GROUPS, ERROR_REAL
use error, only: fatal_error
use geometry_header, only: BASE_UNIVERSE
@ -79,6 +79,9 @@ module particle_header
integer :: material ! index for current material
integer :: last_material ! index for last material
! Temperature of the current cell
real(8) :: sqrtkT ! sqrt(k_Boltzmann * temperature) in MeV
! Statistical data
integer :: n_collision ! # of collisions
@ -124,6 +127,7 @@ contains
this % absorb_wgt = ZERO
this % n_bank = 0
this % wgt_bank = ZERO
this % sqrtkT = ERROR_REAL
this % n_collision = 0
this % fission = .false.
this % delayed_group = 0

2
src/relaxng/geometry.rnc
View file

@ -9,6 +9,8 @@ element geometry {
(element material { ( xsd:int | "void" )+ } |
attribute material { ( xsd:int | "void" )+ })
) &
(element temperature { list { xsd:double+ } } |
attribute temperature { list { xsd:double+ } } )? &
(element region { xsd:string } | attribute region { xsd:string })? &
(element rotation { list { xsd:double+ } } | attribute rotation { list { xsd:double+ } })? &
(element translation { list { xsd:double+ } } | attribute translation { list { xsd:double+ } })?

18
src/relaxng/geometry.rng
View file

@ -64,6 +64,24 @@
</attribute>
</choice>
</choice>
<optional>
<choice>
<element name="temperature">
<list>
<oneOrMore>
<data type="double"/>
</oneOrMore>
</list>
</element>
<attribute name="temperature">
<list>
<oneOrMore>
<data type="double"/>
</oneOrMore>
</list>
</attribute>
</choice>
</optional>
<optional>
<choice>
<element name="region">

8
src/summary.F90
View file

@ -108,6 +108,7 @@ contains
integer :: i, j, k, m
integer, allocatable :: lattice_universes(:,:,:)
integer, allocatable :: cell_materials(:)
real(8), allocatable :: cell_temperatures(:)
integer(HID_T) :: geom_group
integer(HID_T) :: cells_group, cell_group
integer(HID_T) :: surfaces_group, surface_group
@ -151,6 +152,7 @@ contains
select case (c%type)
case (CELL_NORMAL)
call write_dataset(cell_group, "fill_type", "normal")
if (size(c % material) == 1) then
if (c % material(1) == MATERIAL_VOID) then
call write_dataset(cell_group, "material", MATERIAL_VOID)
@ -171,6 +173,12 @@ contains
deallocate(cell_materials)
end if
allocate(cell_temperatures(size(c % sqrtkT)))
cell_temperatures(:) = c % sqrtkT(:)
cell_temperatures(:) = cell_temperatures(:)**2 / K_BOLTZMANN
call write_dataset(cell_group, "temperature", cell_temperatures)
deallocate(cell_temperatures)
case (CELL_FILL)
call write_dataset(cell_group, "fill_type", "universe")
call write_dataset(cell_group, "fill", universes(c%fill)%id)

1
tests/test_distribmat/results_true.dat
View file

@ -5,6 +5,7 @@ Cell
Name =
Material = [2, 3, void, 2]
Region = -10000
Temperature = [ 293.60594237 293.60594237 0. 293.60594237]
Rotation = None
Translation = None
Offset = None

1
tests/test_multipole/inputs_true.dat Normal file
View file

@ -0,0 +1 @@
5c1cec635da5c4c869bdf58f62924a4cb1648e4ddecf0ce71b823cf45178767ba7f2e089b76d36e8616b1b21ffa43b32ab1b17d20bb74120f900b9e3e9ab9bcc

12
tests/test_multipole/results_true.dat Normal file
View file

@ -0,0 +1,12 @@
k-combined:
1.445285E+00 9.521660E-03
Cell
ID = 11
Name =
Material = 2
Region = -10000
Temperature = [ 500. 0. 700. 800.]
Rotation = None
Translation = None
Offset = None
Distribcell index= 1

133
tests/test_multipole/test_multipole.py Normal file
View file

@ -0,0 +1,133 @@
#!/usr/bin/env python
import os
import sys
sys.path.insert(0, os.pardir)
from testing_harness import TestHarness, PyAPITestHarness
import openmc
from openmc.stats import Box
from openmc.source import Source
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)
mats_file = openmc.MaterialsFile()
mats_file.default_xs = '71c'
mats_file.add_materials([moderator, dense_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
c11.temperature = [500, 0, 700, 800]
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.source = 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()