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Merge pull request #770 from paulromano/minor-improvements

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Minor improvements in Python API and testing
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Will Boyd 2016-12-15 13:20:51 -05:00 • committed by GitHub
commit 9b94c4dbec
76 changed files with 10708 additions and 933 deletions
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40
docs/source/methods/physics.rst
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@ -576,12 +576,12 @@ resulting energies would violate laws governing the kinematics, i.e., the
outgoing energy may be outside the range of available energy in the reaction.
To avoid this situation, the accepted practice is to use a process known as
scaled interpolation [Doyas]_. First, we find the tabulated incident energies
which bound the actual incoming energy of the particle, i.e., find :math:`i`
such that :math:`E_i < E < E_{i+1}` and calculate the interpolation factor
:math:`f` via :eq:`interpolation-factor`. Then, we interpolate between the
minimum and maximum energies of the outgoing energy distributions corresponding
to :math:`E_i` and :math:`E_{i+1}`:
`scaled interpolation`_. First, we find the tabulated incident energies which
bound the actual incoming energy of the particle, i.e., find :math:`i` such that
:math:`E_i < E < E_{i+1}` and calculate the interpolation factor :math:`f` via
:eq:`interpolation-factor`. Then, we interpolate between the minimum and maximum
energies of the outgoing energy distributions corresponding to :math:`E_i` and
:math:`E_{i+1}`:
.. math::
:label: continuous-minmax
@ -721,7 +721,7 @@ higher rejection efficiency than the standard technique, i.e. rule C45 in the
Energy-Dependent Watt Spectrum
^^^^^^^^^^^^^^^^^^^^^^^^^^^^^^
The probability distribution for a [Watt]_ fission spectrum can be written in
The probability distribution for a `Watt fission spectrum`_ can be written in
the form
.. math::
@ -1007,7 +1007,7 @@ well as secondary angle and energy distributions. For integrated cross sections,
it is possible to calculate thermally-averaged cross sections by applying a
kernel Doppler broadening algorithm to data at 0 K (or some temperature lower
than the desired temperature). The most ubiquitous algorithm for this purpose is
the [SIGMA1]_ method developed by Red Cullen and subsequently refined by
the `SIGMA1 method`_ developed by Red Cullen and subsequently refined by
others. This method is used in the NJOY_ and PREPRO_ data processing codes.
The effect of thermal motion on secondary angle and energy distributions can be
@ -1507,7 +1507,7 @@ continuous-energy transport.
In the unresolved resonance energy range, resonances may be so closely spaced
that it is not possible for experimental measurements to resolve all
resonances. To properly account for self-shielding in this energy range, OpenMC
uses the probability table method [Levitt]_. For most thermal reactors, the use
uses the `probability table method`_. For most thermal reactors, the use
of probability tables will not significantly affect problem results. However,
for some fast reactors and other problems with an appreciable flux spectrum in
the unresolved resonance range, not using probability tables may lead to
@ -1633,32 +1633,26 @@ another.
.. rubric:: References
.. [Doyas] Richard J. Doyas and Sterrett T. Perkins, "Interpolation of Tabular
Secondary Neutron and Photon Energy Distributions," *Nucl. Sci. Eng.*,
**50**, 390-392 (1972).
.. [Gelbard] Ely M. Gelbard, "Epithermal Scattering in VIM," FRA-TM-123, Argonne
National Laboratory (1979).
.. [Levitt] Leo B. Levitt, "The Probability Table Method for Treating Unresolved
Neutron Resonances in Monte Carlo Calculations," *Nucl. Sci. Eng.*, **49**,
pp. 450-457 (1972).
.. [SIGMA1] Dermett E. Cullen and Charles R. Weisbin, "Exact Doppler Broadening
of Tabulated Cross Sections," *Nucl. Sci. Eng.*, **60**, pp. 199-229 (1976).
.. [Squires] G. L. Squires, *Introduction to the Theory of Thermal Neutron
Scattering*, Cambridge University Press (1978).
.. [Watt] B. E. Watt, "Energy Spectrum of Neutrons from Thermal Fission of
U235," *Phys. Rev.*, **87** (6), 1037-1041 (1952).
.. [Williams] M. M. R. Williams, *The Slowing Down and Thermalization of
Neutrons*, North-Holland Publishing Co., Amsterdam (1966). **Note:** This
book can be obtained for free from the OECD_.
.. |sab| replace:: S(:math:`\alpha,\beta,T`)
.. _SIGMA1 method: http://dx.doi.org/10.13182/NSE76-1
.. _scaled interpolation: http://www.ans.org/pubs/journals/nse/a_26575
.. _probability table method: http://dx.doi.org/10.13182/NSE72-3
.. _Watt fission spectrum: http://dx.doi.org/10.1103/PhysRev.87.1037
.. _Foderaro: http://hdl.handle.net/1721.1/1716
.. _OECD: http://www.oecd-nea.org/dbprog/MMRW-BOOKS.html

6
docs/source/methods/random_numbers.rst
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@ -38,7 +38,7 @@ Typically, :math:`M` is chosen to be a power of two as this enables :math:`x
\mod M` to be performed using the bitwise AND operator with a bit mask. The
constants for the linear congruential generator used by default in OpenMC are
:math:`g = 2806196910506780709`, :math:`c = 1`, and :math:`M = 2^{63}` (see
[LEcuyer]_).
`L'Ecuyer`_).
Skip-ahead Capability
---------------------
@ -66,9 +66,7 @@ the idea is to determine the new multiplicative and additive constants in
.. rubric:: References
.. [LEcuyer] P. L’Ecuyer, "Tables of Linear Congruential Generators of
Different Sizes and Good Lattice Structures," *Math. Comput.*, **68**, 249
(1999).
.. _L'Ecuyer: http://dx.doi.org/10.1090/S0025-5718-99-00996-5
.. _Brown: https://laws.lanl.gov/vhosts/mcnp.lanl.gov/pdf_files/anl-rn-arb-stride.pdf
.. _linear congruential generator: http://en.wikipedia.org/wiki/Linear_congruential_generator

7
docs/source/methods/tallies.rst
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@ -465,8 +465,7 @@ For degrees of freedom greater than two, it is not possible to obtain an
analytical formula for the inverse of the cumulative distribution function. We
must resort to either numerically solving for the inverse or to an
approximation. Approximations for percentiles of the t-distribution have been
found with high levels of accuracy. OpenMC uses the approximation from
[George]_:
found with high levels of accuracy. OpenMC uses the `following approximation`_:
.. math::
:label: percentile-n
@ -485,9 +484,7 @@ improve the estimate of the percentile.
.. rubric:: References
.. [George] E. E. Olusegun George and Meenakshi Sivaram, "A modification of the
Fisher-Cornish approximation for the student t percentiles," Communication
in Statistics - Simulation and Computation, 16 (4), pp. 1123-1132 (1987).
.. _following approximation: http://dx.doi.org/10.1080/03610918708812641
.. _Bessel's correction: http://en.wikipedia.org/wiki/Bessel's_correction

16
docs/source/usersguide/input.rst
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@ -605,13 +605,6 @@ following attributes/sub-elements:
*Default*: Last batch only
:interval:
A single integer :math:`n` indicating that a state point should be written
every :math:`n` batches. This option can be given in lieu of listing
batches explicitly.
*Default*: None
``<source_point>`` Element
--------------------------
@ -628,15 +621,6 @@ attributes/sub-elements:
*Default*: Last batch only
:interval:
A single integer :math:`n` indicating that a state point should be written
every :math:`n` batches. This option can be given in lieu of listing batches
explicitly. It should be noted that if the ``separate`` attribute is not set
to "true", this value should produce a list of batches that is a subset of
state point batches.
*Default*: None
:separate:
If this element is set to "true", a separate binary source point file will
be written. Otherwise, the source sites will be written in the state point

97
docs/source/usersguide/install.rst
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@ -275,6 +275,8 @@ can typically be set for a single command, i.e.
HDF5_ROOT=/opt/hdf5/1.8.15 cmake /path/to/openmc
.. _compile_linux:
Compiling on Linux and Mac OS X
-------------------------------
@ -299,80 +301,28 @@ OpenMC locally by specifying an install prefix when running cmake:
The ``CMAKE_INSTALL_PREFIX`` variable can be changed to any path for which you
have write-access.
Compiling on Windows
--------------------
Compiling on Windows 10
-----------------------
Using Cygwin
++++++++++++
One option for compiling OpenMC on a Windows operating system is to use Cygwin_,
a Linux-like environment for Windows. You will need to first `install
Cygwin`_. When you are asked to select packages, make sure the following are
selected:
* Devel: gcc-core
* Devel: gcc-fortran
* Devel: make
* Devel: cmake
If you plan on obtaining the source code directly using git, select the
following packages:
* Devel: git
* Devel: git-completion (Optional)
* Devel: gitk (Optional)
In order to use the Python scripts provided with OpenMC, you will also need to
install Python. This can be done within Cygwin or directly in Windows. To
install within Cygwin, select the following packages:
* Python: python (Version > 2.7 recommended)
Once you have obtained the source code, run the following commands from within
the source code root directory:
.. code-block:: sh
mkdir build && cd build
cmake ..
make
This will build an executable named ``openmc``.
.. _Cygwin: http://cygwin.com/
.. _install Cygwin: http://cygwin.com/setup.exe
Using MinGW
+++++++++++
An alternate option for installing OpenMC on Windows is using MinGW_, which
stands for Minimalist GNU for Windows. An executable for installing the MinGW
distribution is available on SourceForge_. When installing MinGW, make sure the
following components are selected:
* MinGW Compiler Suite: Fortran Compiler
* MSYS Basic System
Once MinGW is installed, copy the OpenMC source distribution to your MinGW home
directory (usually C:\\MinGW\\msys\\1.0\\home\\YourUsername). Once you have
the source code in place, run the following commands from within the MinGW shell
in the root directory of the OpenMC distribution:
.. code-block:: sh
make
This will build an executable named ``openmc``.
.. _MinGW: http://www.mingw.org
.. _SourceForge: http://sourceforge.net/projects/mingw
Recent versions of Windows 10 include a subsystem for Linux that allows one to
run Bash within Ubuntu running in Windows. First, follow the installation guide
`here <https://msdn.microsoft.com/en-us/commandline/wsl/install_guide>`_ to get
Bash on Ubuntu on Windows setup. Once you are within bash, obtain the necessary
:ref:`prerequisites <prerequisites>` via ``apt-get``. Finally, follow the
:ref:`instructions for compiling on linux <compile_linux>`.
Compiling for the Intel Xeon Phi
--------------------------------
In order to build OpenMC for the Intel Xeon Phi using the Intel Fortran
compiler, it is necessary to specify that all objects be compiled with the
``-mmic`` flag as follows:
For the second generation Knights Landing architecture, nothing special is
required to compile OpenMC. You may wish to experiment with compiler flags that
control generation of vector instructions to see what configuration gives
optimal performance for your target problem.
For the first generation Knights Corner architecture, it is necessary to
cross-compile OpenMC. If you are using the Intel Fortran compiler, it is
necessary to specify that all objects be compiled with the ``-mmic`` flag as
follows:
.. code-block:: sh
@ -380,9 +330,10 @@ compiler, it is necessary to specify that all objects be compiled with the
FC=ifort CC=icc FFLAGS=-mmic cmake -Dopenmp=on ..
make
Note that unless an HDF5 build for the Intel Xeon Phi is already on your target
machine, you will need to cross-compile HDF5 for the Xeon Phi. An `example
script`_ to build zlib and HDF5 provides several necessary workarounds.
Note that unless an HDF5 build for the Intel Xeon Phi (Knights Corner) is
already on your target machine, you will need to cross-compile HDF5 for the Xeon
Phi. An `example script`_ to build zlib and HDF5 provides several necessary
workarounds.
.. _example script: https://github.com/paulromano/install-scripts/blob/master/install-hdf5-mic
@ -497,7 +448,7 @@ that are to be converted:
1. List each ACE library as a positional argument. This is very useful in
conjunction with the usual shell utilities (ls, find, etc.).
2. Use the ``--xml`` option to specify a pre-v0.9 cross_sections.xml file.
3. Use the ``--xsdir` option to specify a MCNP xsdir file.
3. Use the ``--xsdir`` option to specify a MCNP xsdir file.
4. Use the ``--xsdata`` option to specify a Serpent xsdata file.
The script does not use any extra information from cross_sections.xml/ xsdir/

8
examples/python/pincell/build-xml.py
View file

@ -163,9 +163,11 @@ bounds = [-0.62992, -0.62992, -1, 0.62992, 0.62992, 1]
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
settings_file.source = openmc.source.Source(space=uniform_dist)
settings_file.entropy_lower_left = [-0.39218, -0.39218, -1.e50]
settings_file.entropy_upper_right = [0.39218, 0.39218, 1.e50]
settings_file.entropy_dimension = [10, 10, 1]
entropy_mesh = openmc.Mesh()
entropy_mesh.lower_left = [-0.39218, -0.39218, -1.e50]
entropy_mesh.upper_right = [0.39218, 0.39218, 1.e50]
entropy_mesh.dimension = [10, 10, 1]
settings_file.entropy_mesh = entropy_mesh
settings_file.export_to_xml()

2
openmc/__init__.py
View file

@ -1,5 +1,6 @@
from openmc.arithmetic import *
from openmc.cell import *
from openmc.mesh import *
from openmc.lattice import *
from openmc.element import *
from openmc.geometry import *
@ -13,7 +14,6 @@ from openmc.source import *
from openmc.settings import *
from openmc.surface import *
from openmc.universe import *
from openmc.mesh import *
from openmc.filter import *
from openmc.trigger import *
from openmc.tally_derivative import *

11
openmc/cell.py
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@ -547,7 +547,11 @@ class Cell(object):
if self.region is not None:
# Set the region attribute with the region specification
element.set("region", str(self.region))
region = str(self.region)
if region.startswith('('):
region = region[1:-1]
if len(region) > 0:
element.set("region", region)
# Only surfaces that appear in a region are added to the geometry
# file, so the appropriate check is performed here. First we create
@ -557,10 +561,9 @@ class Cell(object):
# thus far.
def create_surface_elements(node, element):
if isinstance(node, Halfspace):
path = './surface[@id=\'{0}\']'.format(node.surface.id)
path = "./surface[@id='{}']".format(node.surface.id)
if xml_element.find(path) is None:
surface_subelement = node.surface.create_xml_subelement()
xml_element.append(surface_subelement)
xml_element.append(node.surface.create_xml_subelement())
elif isinstance(node, Complement):
create_surface_elements(node.node, element)
else:

2
openmc/data/reaction.py
View file

@ -86,7 +86,7 @@ def _get_products(ev, mt):
# Read HEAD record
items = get_head_record(file_obj)
reference_frame = {1: 'laboratory', 2: 'center-of-mass',
3: 'light-heavy'}[items[3]]
3: 'light-heavy', 4: 'breakup'}[items[3]]
n_products = items[4]
products = []

13
openmc/geometry.py
View file

@ -73,19 +73,16 @@ class Geometry(object):
Path to file to write. Defaults to 'geometry.xml'.
"""
# Clear OpenMC written IDs used to optimize XML generation
openmc.universe.WRITTEN_IDS = {}
# Create XML representation
geometry_file = ET.Element("geometry")
self.root_universe.create_xml_subelement(geometry_file)
root_element = ET.Element("geometry")
self.root_universe.create_xml_subelement(root_element)
# Clean the indentation in the file to be user-readable
sort_xml_elements(geometry_file)
clean_xml_indentation(geometry_file)
sort_xml_elements(root_element)
clean_xml_indentation(root_element)
# Write the XML Tree to the geometry.xml file
tree = ET.ElementTree(geometry_file)
tree = ET.ElementTree(root_element)
tree.write(path, xml_declaration=True, encoding='utf-8', method="xml")
def find(self, point):

50
openmc/material.py
View file

@ -734,9 +734,14 @@ class Material(object):
return xml_elements
def get_material_xml(self, cross_sections):
def to_xml_element(self, cross_sections=None):
"""Return XML representation of the material
Parameters
----------
cross_sections : str
Path to an XML cross sections listing file
Returns
-------
element : xml.etree.ElementTree.Element
@ -757,10 +762,14 @@ class Material(object):
subelement.text = str(self.temperature)
# Create density XML subelement
subelement = ET.SubElement(element, "density")
if self._density_units is not 'sum':
subelement.set("value", str(self._density))
subelement.set("units", self._density_units)
if self._density is not None:
subelement = ET.SubElement(element, "density")
if self._density_units is not 'sum':
subelement.set("value", str(self._density))
subelement.set("units", self._density_units)
else:
raise ValueError('Density has not been set for material {}!'
.format(self.id))
if not self._convert_to_distrib_comps:
if self._macroscopic is None:
@ -865,8 +874,6 @@ class Materials(cv.CheckedList):
def __init__(self, materials=None):
super(Materials, self).__init__(Material, 'materials collection')
self._materials_file = ET.Element("materials")
self._cross_sections = None
self._multipole_library = None
@ -971,19 +978,18 @@ class Materials(cv.CheckedList):
for material in self:
material.make_isotropic_in_lab()
def _create_material_subelements(self):
def _create_material_subelements(self, root_element):
for material in self:
xml_element = material.get_material_xml(self.cross_sections)
self._materials_file.append(xml_element)
root_element.append(material.to_xml_element(self.cross_sections))
def _create_cross_sections_subelement(self):
def _create_cross_sections_subelement(self, root_element):
if self._cross_sections is not None:
element = ET.SubElement(self._materials_file, "cross_sections")
element = ET.SubElement(root_element, "cross_sections")
element.text = str(self._cross_sections)
def _create_multipole_library_subelement(self):
def _create_multipole_library_subelement(self, root_element):
if self._multipole_library is not None:
element = ET.SubElement(self._materials_file, "multipole_library")
element = ET.SubElement(root_element, "multipole_library")
element.text = str(self._multipole_library)
def export_to_xml(self, path='materials.xml'):
@ -996,17 +1002,15 @@ class Materials(cv.CheckedList):
"""
# Reset xml element tree
self._materials_file.clear()
self._create_material_subelements()
self._create_cross_sections_subelement()
self._create_multipole_library_subelement()
root_element = ET.Element("materials")
self._create_material_subelements(root_element)
self._create_cross_sections_subelement(root_element)
self._create_multipole_library_subelement(root_element)
# Clean the indentation in the file to be user-readable
sort_xml_elements(self._materials_file)
clean_xml_indentation(self._materials_file)
sort_xml_elements(root_element)
clean_xml_indentation(root_element)
# Write the XML Tree to the materials.xml file
tree = ET.ElementTree(self._materials_file)
tree = ET.ElementTree(root_element)
tree.write(path, xml_declaration=True, encoding='utf-8', method="xml")

2
openmc/mesh.py
View file

@ -215,7 +215,7 @@ class Mesh(object):
for z in range(self.dimension[2]):
yield [x + 1, y + 1, z + 1]
def get_mesh_xml(self):
def to_xml_element(self):
"""Return XML representation of the mesh
Returns

4
openmc/mgxs_library.py
View file

@ -2135,18 +2135,20 @@ class MGXSLibrary(object):
@classmethod
def from_hdf5(cls, filename=None):
"""Generate an MGXS Library from an HDF5 group or file
Parameters
----------
filename : str, optional
Name of HDF5 file containing MGXS data. Default is None.
If not provided, the value of the OPENMC_MG_CROSS_SECTIONS
environmental variable will be used
Returns
-------
openmc.MGXSLibrary
Multi-group cross section data object.
"""
"""
# If filename is None, get the cross sections from the
# OPENMC_CROSS_SECTIONS environment variable
if filename is None:

10
openmc/region.py
View file

@ -232,6 +232,11 @@ class Intersection(Region):
def __init__(self, *nodes):
self.nodes = list(nodes)
def __and__(self, other):
new = Intersection(*self.nodes)
new.nodes.append(other)
return new
def __iter__(self):
for n in self.nodes:
yield n
@ -304,6 +309,11 @@ class Union(Region):
def __init__(self, *nodes):
self.nodes = list(nodes)
def __or__(self, other):
new = Union(*self.nodes)
new.nodes.append(other)
return new
def __iter__(self):
for n in self.nodes:
yield n

709
openmc/settings.py
View file

@ -9,7 +9,7 @@ import numpy as np
from openmc.clean_xml import clean_xml_indentation
import openmc.checkvalue as cv
from openmc import Nuclide, VolumeCalculation, Source
from openmc import Nuclide, VolumeCalculation, Source, Mesh
class Settings(object):
@ -17,52 +17,15 @@ class Settings(object):
Attributes
----------
run_mode : {'eigenvalue' or 'fixed source'}
The type of calculation to perform (default is 'eigenvalue')
batches : int
Number of batches to simulate
generations_per_batch : int
Number of generations per batch
inactive : int
Number of inactive batches
particles : int
Number of particles per generation
keff_trigger : dict
Dictionary defining a trigger on eigenvalue. The dictionary must have
two keys, 'type' and 'threshold'. Acceptable values corresponding to
type are 'variance', 'std_dev', and 'rel_err'. The threshold value
should be a float indicating the variance, standard deviation, or
relative error used.
source : Iterable of openmc.Source
Distribution of source sites in space, angle, and energy
output : dict
Dictionary indicating what files to output. Valid keys are 'summary',
'cross_sections', 'tallies', and 'distribmats'. Values corresponding to
each key should be given as a boolean value.
output_path : str
Path to write output to
verbosity : int
Verbosity during simulation between 1 and 10
statepoint_batches : Iterable of int
List of batches at which to write statepoint files
statepoint_interval : int
Number of batches after which a new statepoint file should be written
sourcepoint_batches : Iterable of int
List of batches at which to write source files
sourcepoint_interval : int
Number of batches after which a new source file should be written
sourcepoint_separate : bool
Indicate whether the souce should be written as part of the statepoint
file or on its own
sourcepoint_write : bool
Indicate whether the source should be written at all
sourcepoint_overwrite : bool
Indicate whether to
confidence_intervals : bool
If True, uncertainties on tally results will be reported as the
half-width of the 95% two-sided confidence interval. If False,
uncertainties on tally results will be reported as the sample standard
deviation.
create_fission_neutrons : bool
Indicate whether fission neutrons should be created or not.
cross_sections : str
Indicates the path to an XML cross section listing file (usually named
cross_sections.xml). If it is not set, the
@ -70,23 +33,6 @@ class Settings(object):
continuous-energy calculations and
:envvar:`OPENMC_MG_CROSS_SECTIONS` will be used for multi-group
calculations to find the path to the XML cross section file.
multipole_library : str
Indicates the path to a directory containing a windowed multipole
cross section library. If it is not set, the
:envvar:`OPENMC_MULTIPOLE_LIBRARY` environment variable will be used. A
multipole library is optional.
energy_mode : {'continuous-energy', 'multi-group'}
Set whether the calculation should be continuous-energy or multi-group.
max_order : int
Maximum scattering order to apply globally when in multi-group mode.
ptables : bool
Determine whether probability tables are used.
run_cmfd : bool
Indicate if coarse mesh finite difference acceleration is to be used
seed : int
Seed for the linear congruential pseudorandom number generator
survival_biasing : bool
Indicate whether survival biasing is to be used
cutoff : dict
Dictionary defining weight cutoff and energy cutoff. The dictionary may
have three keys, 'weight', 'weight_avg' and 'energy'. Value for 'weight'
@ -95,13 +41,66 @@ class Settings(object):
weight assigned to particles that are not killed after Russian
roulette. Value of energy should be a float indicating energy in eV
below which particle will be killed.
entropy_dimension : tuple or list
Number of Shannon entropy mesh cells in the x, y, and z directions,
respectively
entropy_lower_left : tuple or list
Coordinates of the lower-left point of the Shannon entropy mesh
entropy_upper_right : tuple or list
Coordinates of the upper-right point of the Shannon entropy mesh
energy_mode : {'continuous-energy', 'multi-group'}
Set whether the calculation should be continuous-energy or multi-group.
entropy_mesh : openmc.Mesh
Mesh to be used to calculate Shannon entropy. If the mesh dimensions are
not specified. OpenMC assigns a mesh such that 20 source sites per mesh
cell are to be expected on average.
generations_per_batch : int
Number of generations per batch
inactive : int
Number of inactive batches
keff_trigger : dict
Dictionary defining a trigger on eigenvalue. The dictionary must have
two keys, 'type' and 'threshold'. Acceptable values corresponding to
type are 'variance', 'std_dev', and 'rel_err'. The threshold value
should be a float indicating the variance, standard deviation, or
relative error used.
max_order : int
Maximum scattering order to apply globally when in multi-group mode.
multipole_library : str
Indicates the path to a directory containing a windowed multipole
cross section library. If it is not set, the
:envvar:`OPENMC_MULTIPOLE_LIBRARY` environment variable will be used. A
multipole library is optional.
no_reduce : bool
Indicate that all user-defined and global tallies should not be reduced
across processes in a parallel calculation.
output : dict
Dictionary indicating what files to output. Valid keys are 'summary',
'cross_sections', 'tallies', and 'distribmats'. Values corresponding to
each key should be given as a boolean value.
output_path : str
Path to write output to
particles : int
Number of particles per generation
ptables : bool
Determine whether probability tables are used.
resonance_scattering : ResonanceScattering or iterable of ResonanceScattering
The elastic scattering model to use for resonant isotopes
run_cmfd : bool
Indicate if coarse mesh finite difference acceleration is to be used
run_mode : {'eigenvalue' or 'fixed source'}
The type of calculation to perform (default is 'eigenvalue')
seed : int
Seed for the linear congruential pseudorandom number generator
source : Iterable of openmc.Source
Distribution of source sites in space, angle, and energy
sourcepoint : dict
Options for writing source points. Acceptable keys are:
:batches: list of batches at which to write source
:overwrite: bool indicating whether to overwrite
:separate: bool indicating whether the source should be written as a
separate file
:write: bool indicating whether or not to write the source
statepoint : dict
Options for writing state points. Acceptable keys are:
:batches: list of batches at which to write source
survival_biasing : bool
Indicate whether survival biasing is to be used
tabular_legendre : dict
Determines if a multi-group scattering moment kernel expanded via
Legendre polynomials is to be converted to a tabular distribution or
@ -119,17 +118,6 @@ class Settings(object):
within which cross sections may be used. 'multipole' is a boolean
indicating whether or not the windowed multipole method should be used
to evaluate resolved resonance cross sections.
trigger_active : bool
Indicate whether tally triggers are used
trigger_max_batches : int
Maximum number of batches simulated. If this is set, the number of
batches specified via ``batches`` is interpreted as the minimum number
of batches
trigger_batch_interval : int
Number of batches in between convergence checks
no_reduce : bool
Indicate that all user-defined and global tallies should not be reduced
across processes in a parallel calculation.
threads : int
Number of OpenMP threads
trace : tuple or list
@ -139,19 +127,21 @@ class Settings(object):
Specify particles for which track files should be written. Each particle
is identified by a triplet with the batch number, generation number, and
particle number.
ufs_dimension : tuple or list
Number of uniform fission site (UFS) mesh cells in the x, y, and z
directions, respectively
ufs_lower_left : tuple or list
Coordinates of the lower-left point of the UFS mesh
ufs_upper_right : tuple or list
Coordinates of the upper-right point of the UFS mesh
resonance_scattering : ResonanceScattering or iterable of ResonanceScattering
The elastic scattering model to use for resonant isotopes
trigger_active : bool
Indicate whether tally triggers are used
trigger_batch_interval : int
Number of batches in between convergence checks
trigger_max_batches : int
Maximum number of batches simulated. If this is set, the number of
batches specified via ``batches`` is interpreted as the minimum number
of batches
ufs_mesh : openmc.Mesh
Mesh to be used for redistributing source sites via the uniform fision
site (UFS) method.
verbosity : int
Verbosity during simulation between 1 and 10
volume_calculations : VolumeCalculation or iterable of VolumeCalculation
Stochastic volume calculation specifications
create_fission_neutrons : bool
Indicate whether fission neutrons should be created or not.
"""
@ -180,13 +170,10 @@ class Settings(object):
self._seed = None
self._survival_biasing = None
# Entropy subelement
self._entropy_dimension = None
self._entropy_lower_left = None
self._entropy_upper_right = None
# Shannon entropy mesh
self._entropy_mesh = None
# Trigger subelement
self._trigger_subelement = None
self._trigger_active = None
self._trigger_max_batches = None
self._trigger_batch_interval = None
@ -194,14 +181,9 @@ class Settings(object):
self._output = None
self._output_path = None
# Statepoint subelement
self._statepoint_batches = None
self._statepoint_interval = None
self._sourcepoint_batches = None
self._sourcepoint_interval = None
self._sourcepoint_separate = None
self._sourcepoint_write = None
self._sourcepoint_overwrite = None
# Output options
self._statepoint = {}
self._sourcepoint = {}
self._threads = None
self._no_reduce = None
@ -219,9 +201,7 @@ class Settings(object):
self._cutoff = None
# Uniform fission source subelement
self._ufs_dimension = 1
self._ufs_lower_left = None
self._ufs_upper_right = None
self._ufs_mesh = None
# Domain decomposition subelement
self._dd_mesh_dimension = None
@ -231,9 +211,6 @@ class Settings(object):
self._dd_allow_leakage = False
self._dd_count_interactions = False
self._settings_file = ET.Element("settings")
self._run_mode_subelement = None
self._resonance_scattering = cv.CheckedList(
ResonanceScattering, 'resonance scattering models')
self._volume_calculations = cv.CheckedList(
@ -306,16 +283,8 @@ class Settings(object):
return self._survival_biasing
@property
def entropy_dimension(self):
return self._entropy_dimension
@property
def entropy_lower_left(self):
return self._entropy_lower_left
@property
def entropy_upper_right(self):
return self._entropy_upper_right
def entropy_mesh(self):
return self._entropy_mesh
@property
def trigger_active(self):
@ -338,32 +307,12 @@ class Settings(object):
return self._output_path
@property
def statepoint_batches(self):
return self._statepoint_batches
def sourcepoint(self):
return self._sourcepoint
@property
def statepoint_interval(self):
return self._statepoint_interval
@property
def sourcepoint_batches(self):
return self._sourcepoint_interval
@property
def sourcepoint_interval(self):
return self._sourcepoint_interval
@property
def sourcepoint_separate(self):
return self._sourcepoint_separate
@property
def sourcepoint_write(self):
return self._sourcepoint_write
@property
def sourcepoint_overwrite(self):
return self._sourcepoint_overwrite
def statepoint(self):
return self._statepoint
@property
def threads(self):
@ -398,16 +347,8 @@ class Settings(object):
return self._cutoff
@property
def ufs_dimension(self):
return self._ufs_dimension
@property
def ufs_lower_left(self):
return self._ufs_lower_left
@property
def ufs_upper_right(self):
return self._ufs_upper_right
def ufs_mesh(self):
return self._ufs_mesh
@property
def dd_mesh_dimension(self):
@ -557,44 +498,37 @@ class Settings(object):
cv.check_less_than('verbosity', verbosity, 10, True)
self._verbosity = verbosity
@statepoint_batches.setter
def statepoint_batches(self, batches):
cv.check_type('statepoint batches', batches, Iterable, Integral)
for batch in batches:
cv.check_greater_than('statepoint batch', batch, 0)
self._statepoint_batches = batches
@sourcepoint.setter
def sourcepoint(self, sourcepoint):
cv.check_type('sourcepoint options', sourcepoint, Mapping)
for key, value in sourcepoint.items():
if key == 'batches':
cv.check_type('sourcepoint batches', value, Iterable, Integral)
for batch in value:
cv.check_greater_than('sourcepoint batch', batch, 0)
elif key == 'separate':
cv.check_type('sourcepoint separate', value, bool)
elif key == 'write':
cv.check_type('sourcepoint write', value, bool)
elif key == 'overwrite':
cv.check_type('sourcepoint overwrite', value, bool)
else:
raise ValueError("Unknown key '{}' encountered when setting "
"sourcepoint options.".format(key))
self._sourcepoint = sourcepoint
@statepoint_interval.setter
def statepoint_interval(self, interval):
cv.check_type('statepoint interval', interval, Integral)
self._statepoint_interval = interval
@sourcepoint_batches.setter
def sourcepoint_batches(self, batches):
cv.check_type('sourcepoint batches', batches, Iterable, Integral)
for batch in batches:
cv.check_greater_than('sourcepoint batch', batch, 0)
self._sourcepoint_batches = batches
@sourcepoint_interval.setter
def sourcepoint_interval(self, interval):
cv.check_type('sourcepoint interval', interval, Integral)
self._sourcepoint_interval = interval
@sourcepoint_separate.setter
def sourcepoint_separate(self, source_separate):
cv.check_type('sourcepoint separate', source_separate, bool)
self._sourcepoint_separate = source_separate
@sourcepoint_write.setter
def sourcepoint_write(self, source_write):
cv.check_type('sourcepoint write', source_write, bool)
self._sourcepoint_write = source_write
@sourcepoint_overwrite.setter
def sourcepoint_overwrite(self, source_overwrite):
cv.check_type('sourcepoint overwrite', source_overwrite, bool)
self._sourcepoint_overwrite = source_overwrite
@statepoint.setter
def statepoint(self, statepoint):
cv.check_type('statepoint options', statepoint, Mapping)
for key, value in statepoint.items():
if key == 'batches':
cv.check_type('statepoint batches', value, Iterable, Integral)
for batch in value:
cv.check_greater_than('statepoint batch', batch, 0)
else:
raise ValueError("Unknown key '{}' encountered when setting "
"statepoint options.".format(key))
self._statepoint = statepoint
@confidence_intervals.setter
def confidence_intervals(self, confidence_intervals):
@ -663,25 +597,13 @@ class Settings(object):
self._cutoff = cutoff
@entropy_dimension.setter
def entropy_dimension(self, dimension):
cv.check_type('entropy mesh dimension', dimension, Iterable, Integral)
cv.check_length('entropy mesh dimension', dimension, 3)
self._entropy_dimension = dimension
@entropy_lower_left.setter
def entropy_lower_left(self, lower_left):
cv.check_type('entropy mesh lower left corner', lower_left,
Iterable, Real)
cv.check_length('entropy mesh lower left corner', lower_left, 3)
self._entropy_lower_left = lower_left
@entropy_upper_right.setter
def entropy_upper_right(self, upper_right):
cv.check_type('entropy mesh upper right corner', upper_right,
Iterable, Real)
cv.check_length('entropy mesh upper right corner', upper_right, 3)
self._entropy_upper_right = upper_right
@entropy_mesh.setter
def entropy_mesh(self, entropy):
cv.check_type('entropy mesh', entropy, Mesh)
cv.check_length('entropy mesh dimension', entropy.dimension, 3)
cv.check_length('entropy mesh lower-left corner', entropy.lower_left, 3)
cv.check_length('entropy mesh upper-right corner', entropy.upper_right, 3)
self._entropy_mesh = entropy
@trigger_active.setter
def trigger_active(self, trigger_active):
@ -764,25 +686,13 @@ class Settings(object):
cv.check_greater_than('track particle', t[0], 0)
self._track = track
@ufs_dimension.setter
def ufs_dimension(self, dimension):
cv.check_type('UFS mesh dimension', dimension, Iterable, Integral)
cv.check_length('UFS mesh dimension', dimension, 3)
for dim in dimension:
cv.check_greater_than('UFS mesh dimension', dim, 1, True)
self._ufs_dimension = dimension
@ufs_lower_left.setter
def ufs_lower_left(self, lower_left):
cv.check_type('UFS mesh lower left corner', lower_left, Iterable, Real)
cv.check_length('UFS mesh lower left corner', lower_left, 3)
self._ufs_lower_left = lower_left
@ufs_upper_right.setter
def ufs_upper_right(self, upper_right):
cv.check_type('UFS mesh upper right corner', upper_right, Iterable, Real)
cv.check_length('UFS mesh upper right corner', upper_right, 3)
self._ufs_upper_right = upper_right
@ufs_mesh.setter
def ufs_mesh(self, ufs_mesh):
cv.check_type('UFS mesh', ufs_mesh, Mesh)
cv.check_length('UFS mesh dimension', ufs_mesh.dimension, 3)
cv.check_length('UFS mesh lower-left corner', ufs_mesh.lower_left, 3)
cv.check_length('UFS mesh upper-right corner', ufs_mesh.upper_right, 3)
self._ufs_mesh = ufs_mesh
@dd_mesh_dimension.setter
def dd_mesh_dimension(self, dimension):
@ -883,172 +793,152 @@ class Settings(object):
create_fission_neutrons, bool)
self._create_fission_neutrons = create_fission_neutrons
def _create_run_mode_subelement(self):
def _create_run_mode_subelement(self, root):
if self.run_mode == 'eigenvalue':
self._run_mode_subelement = \
ET.SubElement(self._settings_file, "eigenvalue")
self._create_particles_subelement()
self._create_batches_subelement()
self._create_inactive_subelement()
self._create_generations_per_batch_subelement()
self._create_keff_trigger_subelement()
elem = ET.SubElement(root, "eigenvalue")
self._create_particles_subelement(elem)
self._create_batches_subelement(elem)
self._create_inactive_subelement(elem)
self._create_generations_per_batch_subelement(elem)
self._create_keff_trigger_subelement(elem)
else:
if self._run_mode_subelement is None:
self._run_mode_subelement = \
ET.SubElement(self._settings_file, "fixed_source")
self._create_particles_subelement()
self._create_batches_subelement()
elem = ET.SubElement(root, "fixed_source")
self._create_particles_subelement(elem)
self._create_batches_subelement(elem)
def _create_batches_subelement(self):
def _create_batches_subelement(self, run_mode_element):
if self._batches is not None:
element = ET.SubElement(self._run_mode_subelement, "batches")
element = ET.SubElement(run_mode_element, "batches")
element.text = str(self._batches)
def _create_generations_per_batch_subelement(self):
def _create_generations_per_batch_subelement(self, run_mode_element):
if self._generations_per_batch is not None:
element = ET.SubElement(self._run_mode_subelement,
element = ET.SubElement(run_mode_element,
"generations_per_batch")
element.text = str(self._generations_per_batch)
def _create_inactive_subelement(self):
def _create_inactive_subelement(self, run_mode_element):
if self._inactive is not None:
element = ET.SubElement(self._run_mode_subelement, "inactive")
element = ET.SubElement(run_mode_element, "inactive")
element.text = str(self._inactive)
def _create_particles_subelement(self):
def _create_particles_subelement(self, run_mode_element):
if self._particles is not None:
element = ET.SubElement(self._run_mode_subelement, "particles")
element = ET.SubElement(run_mode_element, "particles")
element.text = str(self._particles)
def _create_keff_trigger_subelement(self):
def _create_keff_trigger_subelement(self, run_mode_element):
if self._keff_trigger is not None:
element = ET.SubElement(self._run_mode_subelement, "keff_trigger")
element = ET.SubElement(run_mode_subelement, "keff_trigger")
for key in self._keff_trigger:
subelement = ET.SubElement(element, key)
subelement.text = str(self._keff_trigger[key]).lower()
def _create_energy_mode_subelement(self):
def _create_energy_mode_subelement(self, root):
if self._energy_mode is not None:
element = ET.SubElement(self._settings_file, "energy_mode")
element = ET.SubElement(root, "energy_mode")
element.text = str(self._energy_mode)
def _create_max_order_subelement(self):
def _create_max_order_subelement(self, root):
if self._max_order is not None:
element = ET.SubElement(self._settings_file, "max_order")
element = ET.SubElement(root, "max_order")
element.text = str(self._max_order)
def _create_source_subelement(self):
def _create_source_subelement(self, root):
for source in self.source:
self._settings_file.append(source.to_xml_element())
root.append(source.to_xml_element())
def _create_volume_calcs_subelement(self):
def _create_volume_calcs_subelement(self, root):
for calc in self.volume_calculations:
self._settings_file.append(calc.to_xml_element())
root.append(calc.to_xml_element())
def _create_output_subelement(self):
def _create_output_subelement(self, root):
if self._output is not None:
element = ET.SubElement(self._settings_file, "output")
element = ET.SubElement(root, "output")
for key in self._output:
subelement = ET.SubElement(element, key)
subelement.text = str(self._output[key]).lower()
self._create_output_path_subelement()
if self._output_path is not None:
element = ET.SubElement(root, "output_path")
element.text = self._output_path
def _create_output_path_subelement(self):
if self._output_path is not None:
element = ET.SubElement(self._settings_file, "output_path")
element.text = self._output_path
def _create_verbosity_subelement(self):
def _create_verbosity_subelement(self, root):
if self._verbosity is not None:
element = ET.SubElement(self._settings_file, "verbosity")
element = ET.SubElement(root, "verbosity")
element.text = str(self._verbosity)
def _create_statepoint_subelement(self):
# Batches subelement
if self._statepoint_batches is not None:
element = ET.SubElement(self._settings_file, "state_point")
subelement = ET.SubElement(element, "batches")
subelement.text = ' '.join(map(str, self._statepoint_batches))
def _create_statepoint_subelement(self, root):
if self._statepoint:
element = ET.SubElement(root, "state_point")
if 'batches' in self._statepoint:
subelement = ET.SubElement(element, "batches")
subelement.text = ' '.join(
str(x) for x in self._statepoint['batches'])
# Interval subelement
elif self._statepoint_interval is not None:
element = ET.SubElement(self._settings_file, "state_point")
subelement = ET.SubElement(element, "interval")
subelement.text = str(self._statepoint_interval)
def _create_sourcepoint_subelement(self, root):
if self._sourcepoint:
element = ET.SubElement(root, "source_point")
def _create_sourcepoint_subelement(self):
# Batches subelement
if self._sourcepoint_batches is not None:
element = ET.SubElement(self._settings_file, "source_point")
subelement = ET.SubElement(element, "batches")
subelement.text = ' '.join(map(str, self._sourcepoint_batches))
if 'batches' in self._sourcepoint:
subelement = ET.SubElement(element, "batches")
subelement.text = ' '.join(
str(x) for x in self._sourcepoint['batches'])
# Interval subelement
elif self._sourcepoint_interval is not None:
element = ET.SubElement(self._settings_file, "source_point")
subelement = ET.SubElement(element, "interval")
subelement.text = str(self._sourcepoint_interval)
if 'separate' in self._sourcepoint:
subelement = ET.SubElement(element, "separate")
subelement.text = str(self._sourcepoint['separate']).lower()
# Separate subelement
if self._sourcepoint_separate is not None:
element = ET.SubElement(self._settings_file, "source_point")
subelement = ET.SubElement(element, "separate")
subelement.text = str(self._sourcepoint_separate).lower()
if 'write' in self._sourcepoint:
subelement = ET.SubElement(element, "write")
subelement.text = str(self._sourcepoint['write']).lower()
# Write subelement
if self._sourcepoint_write is not None:
element = ET.SubElement(self._settings_file, "source_point")
subelement = ET.SubElement(element, "write")
subelement.text = str(self._sourcepoint_write).lower()
# Overwrite latest subelement
if 'overwrite' in self._sourcepoint:
subelement = ET.SubElement(element, "overwrite_latest")
subelement.text = str(self._sourcepoint['overwrite']).lower()
# Overwrite latest subelement
if self._sourcepoint_overwrite is not None:
element = ET.SubElement(self._settings_file, "source_point")
subelement = ET.SubElement(element, "overwrite_latest")
subelement.text = str(self._sourcepoint_overwrite).lower()
def _create_confidence_intervals(self):
def _create_confidence_intervals(self, root):
if self._confidence_intervals is not None:
element = ET.SubElement(self._settings_file, "confidence_intervals")
element = ET.SubElement(root, "confidence_intervals")
element.text = str(self._confidence_intervals).lower()
def _create_cross_sections_subelement(self):
def _create_cross_sections_subelement(self, root):
if self._cross_sections is not None:
element = ET.SubElement(self._settings_file, "cross_sections")
element = ET.SubElement(root, "cross_sections")
element.text = str(self._cross_sections)
def _create_multipole_library_subelement(self):
def _create_multipole_library_subelement(self, root):
if self._multipole_library is not None:
element = ET.SubElement(self._settings_file, "multipole_library")
element = ET.SubElement(root, "multipole_library")
element.text = str(self._multipole_library)
def _create_ptables_subelement(self):
def _create_ptables_subelement(self, root):
if self._ptables is not None:
element = ET.SubElement(self._settings_file, "ptables")
element = ET.SubElement(root, "ptables")
element.text = str(self._ptables).lower()
def _create_run_cmfd_subelement(self):
def _create_run_cmfd_subelement(self, root):
if self._run_cmfd is not None:
element = ET.SubElement(self._settings_file, "run_cmfd")
element = ET.SubElement(root, "run_cmfd")
element.text = str(self._run_cmfd).lower()
def _create_seed_subelement(self):
def _create_seed_subelement(self, root):
if self._seed is not None:
element = ET.SubElement(self._settings_file, "seed")
element = ET.SubElement(root, "seed")
element.text = str(self._seed)
def _create_survival_biasing_subelement(self):
def _create_survival_biasing_subelement(self, root):
if self._survival_biasing is not None:
element = ET.SubElement(self._settings_file, "survival_biasing")
element = ET.SubElement(root, "survival_biasing")
element.text = str(self._survival_biasing).lower()
def _create_cutoff_subelement(self):
def _create_cutoff_subelement(self, root):
if self._cutoff is not None:
element = ET.SubElement(self._settings_file, "cutoff")
element = ET.SubElement(root, "cutoff")
if 'weight' in self._cutoff:
subelement = ET.SubElement(element, "weight")
subelement.text = str(self._cutoff['weight'])
@ -1061,110 +951,90 @@ class Settings(object):
subelement = ET.SubElement(element, "energy")
subelement.text = str(self._cutoff['energy'])
def _create_entropy_subelement(self):
if self._entropy_lower_left is not None and \
self._entropy_upper_right is not None:
element = ET.SubElement(self._settings_file, "entropy")
subelement = ET.SubElement(element, "dimension")
subelement.text = ' '.join(map(str, self._entropy_dimension))
def _create_entropy_subelement(self, root):
if self._entropy_mesh is not None:
element = ET.SubElement(root, "entropy")
if self._entropy_mesh.dimension is not None:
subelement = ET.SubElement(element, "dimension")
subelement.text = ' '.join(
str(x) for x in self._entropy_mesh.dimension)
subelement = ET.SubElement(element, "lower_left")
subelement.text = ' '.join(map(str, self._entropy_lower_left))
subelement.text = ' '.join(
str(x) for x in self._entropy_mesh.lower_left)
subelement = ET.SubElement(element, "upper_right")
subelement.text = ' '.join(map(str, self._entropy_upper_right))
subelement.text = ' '.join(
str(x) for x in self._entropy_mesh.upper_right)
def _create_trigger_subelement(self):
self._create_trigger_active_subelement()
self._create_trigger_max_batches_subelement()
self._create_trigger_batch_interval_subelement()
def _create_trigger_active_subelement(self):
def _create_trigger_subelement(self, root):
if self._trigger_active is not None:
if self._trigger_subelement is None:
self._trigger_subelement = ET.SubElement(self._settings_file,
"trigger")
element = ET.SubElement(self._trigger_subelement, "active")
trigger_element = ET.SubElement(root, "trigger")
element = ET.SubElement(trigger_element, "active")
element.text = str(self._trigger_active).lower()
def _create_trigger_max_batches_subelement(self):
if self._trigger_max_batches is not None:
if self._trigger_subelement is None:
self._trigger_subelement = ET.SubElement(self._settings_file,
"trigger")
if self._trigger_max_batches is not None:
element = ET.SubElement(trigger_element, "max_batches")
element.text = str(self._trigger_max_batches)
element = ET.SubElement(self._trigger_subelement, "max_batches")
element.text = str(self._trigger_max_batches)
if self._trigger_batch_interval is not None:
element = ET.SubElement(trigger_element, "batch_interval")
element.text = str(self._trigger_batch_interval)
def _create_trigger_batch_interval_subelement(self):
if self._trigger_batch_interval is not None:
if self._trigger_subelement is None:
self._trigger_subelement = ET.SubElement(self._settings_file,
"trigger")
element = ET.SubElement(self._trigger_subelement, "batch_interval")
element.text = str(self._trigger_batch_interval)
def _create_no_reduce_subelement(self):
def _create_no_reduce_subelement(self, root):
if self._no_reduce is not None:
element = ET.SubElement(self._settings_file, "no_reduce")
element = ET.SubElement(root, "no_reduce")
element.text = str(self._no_reduce).lower()
def _create_tabular_legendre_subelements(self):
def _create_tabular_legendre_subelements(self, root):
if self.tabular_legendre:
element = ET.SubElement(self._settings_file, "tabular_legendre")
element = ET.SubElement(root, "tabular_legendre")
subelement = ET.SubElement(element, "enable")
subelement.text = str(self._tabular_legendre['enable']).lower()
if 'num_points' in self._tabular_legendre:
subelement = ET.SubElement(element, "num_points")
subelement.text = str(self._tabular_legendre['num_points'])
def _create_temperature_subelements(self):
def _create_temperature_subelements(self, root):
if self.temperature:
for key, value in sorted(self.temperature.items()):
element = ET.SubElement(self._settings_file,
element = ET.SubElement(root,
"temperature_{}".format(key))
element.text = str(value)
def _create_threads_subelement(self):
def _create_threads_subelement(self, root):
if self._threads is not None:
element = ET.SubElement(self._settings_file, "threads")
element = ET.SubElement(root, "threads")
element.text = str(self._threads)
def _create_trace_subelement(self):
def _create_trace_subelement(self, root):
if self._trace is not None:
element = ET.SubElement(self._settings_file, "trace")
element = ET.SubElement(root, "trace")
element.text = ' '.join(map(str, self._trace))
def _create_track_subelement(self):
def _create_track_subelement(self, root):
if self._track is not None:
element = ET.SubElement(self._settings_file, "track")
element = ET.SubElement(root, "track")
element.text = ' '.join(map(str, self._track))
def _create_ufs_subelement(self):
if self._ufs_lower_left is not None and \
self._ufs_upper_right is not None:
element = ET.SubElement(self._settings_file, "uniform_fs")
def _create_ufs_subelement(self, root):
if self._ufs_mesh is not None:
element = ET.SubElement(root, "uniform_fs")
subelement = ET.SubElement(element, "dimension")
subelement.text = ' '.join(map(str, self._ufs_dimension))
subelement.text = ' '.join(str(x) for x in
self._ufs_mesh.dimension)
subelement = ET.SubElement(element, "lower_left")
subelement.text = ' '.join(map(str, self._ufs_lower_left))
subelement.text = ' '.join(str(x) for x in
self._ufs_mesh.lower_left)
subelement = ET.SubElement(element, "upper_right")
subelement.text = ' '.join(map(str, self._ufs_upper_right))
subelement.text = ' '.join(str(x) for x in
self._ufs_mesh.upper_right)
def _create_dd_subelement(self):
def _create_dd_subelement(self, root):
if self._dd_mesh_lower_left is not None and \
self._dd_mesh_upper_right is not None and \
self._dd_mesh_dimension is not None:
element = ET.SubElement(self._settings_file, "domain_decomposition")
element = ET.SubElement(root, "domain_decomposition")
subelement = ET.SubElement(element, "mesh")
subsubelement = ET.SubElement(subelement, "dimension")
@ -1186,15 +1056,15 @@ class Settings(object):
subelement = ET.SubElement(element, "count_interactions")
subelement.text = str(self._dd_count_interactions).lower()
def _create_resonance_scattering_subelement(self):
def _create_resonance_scattering_subelement(self, root):
if len(self.resonance_scattering) > 0:
elem = ET.SubElement(self._settings_file, 'resonance_scattering')
elem = ET.SubElement(root, 'resonance_scattering')
for r in self.resonance_scattering:
elem.append(r.to_xml_element())
def _create_create_fission_neutrons_subelement(self):
def _create_create_fission_neutrons_subelement(self, root):
if self._create_fission_neutrons is not None:
elem = ET.SubElement(self._settings_file, "create_fission_neutrons")
elem = ET.SubElement(root, "create_fission_neutrons")
elem.text = str(self._create_fission_neutrons).lower()
def export_to_xml(self, path='settings.xml'):
@ -1208,46 +1078,43 @@ class Settings(object):
"""
# Reset xml element tree
self._settings_file.clear()
self._source_subelement = None
self._trigger_subelement = None
self._run_mode_subelement = None
root_element = ET.Element("settings")
self._create_run_mode_subelement()
self._create_source_subelement()
self._create_output_subelement()
self._create_statepoint_subelement()
self._create_sourcepoint_subelement()
self._create_confidence_intervals()
self._create_cross_sections_subelement()
self._create_multipole_library_subelement()
self._create_energy_mode_subelement()
self._create_max_order_subelement()
self._create_ptables_subelement()
self._create_run_cmfd_subelement()
self._create_seed_subelement()
self._create_survival_biasing_subelement()
self._create_cutoff_subelement()
self._create_entropy_subelement()
self._create_trigger_subelement()
self._create_no_reduce_subelement()
self._create_threads_subelement()
self._create_verbosity_subelement()
self._create_tabular_legendre_subelements()
self._create_temperature_subelements()
self._create_trace_subelement()
self._create_track_subelement()
self._create_ufs_subelement()
self._create_dd_subelement()
self._create_resonance_scattering_subelement()
self._create_volume_calcs_subelement()
self._create_create_fission_neutrons_subelement()
self._create_run_mode_subelement(root_element)
self._create_source_subelement(root_element)
self._create_output_subelement(root_element)
self._create_statepoint_subelement(root_element)
self._create_sourcepoint_subelement(root_element)
self._create_confidence_intervals(root_element)
self._create_cross_sections_subelement(root_element)
self._create_multipole_library_subelement(root_element)
self._create_energy_mode_subelement(root_element)
self._create_max_order_subelement(root_element)
self._create_ptables_subelement(root_element)
self._create_run_cmfd_subelement(root_element)
self._create_seed_subelement(root_element)
self._create_survival_biasing_subelement(root_element)
self._create_cutoff_subelement(root_element)
self._create_entropy_subelement(root_element)
self._create_trigger_subelement(root_element)
self._create_no_reduce_subelement(root_element)
self._create_threads_subelement(root_element)
self._create_verbosity_subelement(root_element)
self._create_tabular_legendre_subelements(root_element)
self._create_temperature_subelements(root_element)
self._create_trace_subelement(root_element)
self._create_track_subelement(root_element)
self._create_ufs_subelement(root_element)
self._create_dd_subelement(root_element)
self._create_resonance_scattering_subelement(root_element)
self._create_volume_calcs_subelement(root_element)
self._create_create_fission_neutrons_subelement(root_element)
# Clean the indentation in the file to be user-readable
clean_xml_indentation(self._settings_file)
clean_xml_indentation(root_element)
# Write the XML Tree to the settings.xml file
tree = ET.ElementTree(self._settings_file)
tree = ET.ElementTree(root_element)
tree.write(path, xml_declaration=True, encoding='utf-8', method="xml")

14
openmc/surface.py
View file

@ -8,7 +8,7 @@ from six import add_metaclass, string_types
import numpy as np
from openmc.checkvalue import check_type, check_value, check_greater_than
from openmc.region import Region, Intersection
from openmc.region import Region, Intersection, Union
# A static variable for auto-generated Surface IDs
@ -1736,6 +1736,18 @@ class Halfspace(Region):
self.surface = surface
self.side = side
def __and__(self, other):
if isinstance(other, Intersection):
return Intersection(self, *other.nodes)
else:
return Intersection(self, other)
def __or__(self, other):
if isinstance(other, Union):
return Union(self, *other.nodes)
else:
return Union(self, other)
def __invert__(self):
return -self.surface if self.side == '+' else +self.surface

33
openmc/tallies.py
View file

@ -1015,7 +1015,7 @@ class Tally(object):
return merged_tally
def get_tally_xml(self):
def to_xml_element(self):
"""Return XML representation of the tally
Returns
@ -3307,7 +3307,6 @@ class Tallies(cv.CheckedList):
def __init__(self, tallies=None):
super(Tallies, self).__init__(Tally, 'tallies collection')
self._tallies_file = ET.Element("tallies")
if tallies is not None:
self += tallies
@ -3459,25 +3458,23 @@ class Tallies(cv.CheckedList):
"removed in a future version. Meshes do not need to be "
"managed explicitly.", DeprecationWarning)
def _create_tally_subelements(self):
def _create_tally_subelements(self, root_element):
for tally in self:
xml_element = tally.get_tally_xml()
self._tallies_file.append(xml_element)
root_element.append(tally.to_xml_element())
def _create_mesh_subelements(self):
def _create_mesh_subelements(self, root_element):
already_written = set()
for tally in self:
for f in tally.filters:
if isinstance(f, openmc.MeshFilter):
if f.mesh not in already_written:
if len(f.mesh.name) > 0:
self._tallies_file.append(ET.Comment(f.mesh.name))
root_element.append(ET.Comment(f.mesh.name))
xml_element = f.mesh.get_mesh_xml()
self._tallies_file.append(xml_element)
root_element.append(f.mesh.to_xml_element())
already_written.add(f.mesh)
def _create_derivative_subelements(self):
def _create_derivative_subelements(self, root_element):
# Get a list of all derivatives referenced in a tally.
derivs = []
for tally in self:
@ -3487,24 +3484,22 @@ class Tallies(cv.CheckedList):
# Add the derivatives to the XML tree.
for d in derivs:
self._tallies_file.append(d.to_xml_element())
root_element.append(d.to_xml_element())
def export_to_xml(self):
"""Create a tallies.xml file that can be used for a simulation.
"""
# Reset xml element tree
self._tallies_file.clear()
self._create_mesh_subelements()
self._create_tally_subelements()
self._create_derivative_subelements()
root_element = ET.Element("tallies")
self._create_mesh_subelements(root_element)
self._create_tally_subelements(root_element)
self._create_derivative_subelements(root_element)
# Clean the indentation in the file to be user-readable
clean_xml_indentation(self._tallies_file)
clean_xml_indentation(root_element)
# Write the XML Tree to the tallies.xml file
tree = ET.ElementTree(self._tallies_file)
tree = ET.ElementTree(root_element)
tree.write("tallies.xml", xml_declaration=True,
encoding='utf-8', method="xml")

16
openmc/universe.py
View file

@ -10,10 +10,6 @@ import openmc
import openmc.checkvalue as cv
# A dictionary for storing IDs of cell elements that have already been written,
# used to optimize the writing process
WRITTEN_IDS = {}
# A static variable for auto-generated Lattice (Universe) IDs
AUTO_UNIVERSE_ID = 10000
@ -453,17 +449,15 @@ class Universe(object):
return universes
def create_xml_subelement(self, xml_element):
# Iterate over all Cells
for cell_id, cell in self._cells.items():
path = "./cell[@id='{}']".format(cell_id)
# If the cell was not already written, write it
if cell_id not in WRITTEN_IDS:
WRITTEN_IDS[cell_id] = None
if xml_element.find(path) is None:
# Create XML subelement for this Cell
cell_subelement = cell.create_xml_subelement(xml_element)
cell_element = cell.create_xml_subelement(xml_element)
# Append the Universe ID to the subelement and add to Element
cell_subelement.set("universe", str(self._id))
xml_element.append(cell_subelement)
cell_element.set("universe", str(self._id))
xml_element.append(cell_element)

14
src/input_xml.F90
View file

@ -814,13 +814,6 @@ contains
call statepoint_batch % add(temp_int_array(i))
end do
deallocate(temp_int_array)
elseif (check_for_node(node_sp, "interval")) then
! User gave an interval for writing state points
call get_node_value(node_sp, "interval", temp_int)
n_state_points = n_batches / temp_int
do i = 1, n_state_points
call statepoint_batch % add(temp_int * i)
end do
else
! If neither were specified, write state point at last batch
n_state_points = 1
@ -854,13 +847,6 @@ contains
call sourcepoint_batch % add(temp_int_array(i))
end do
deallocate(temp_int_array)
elseif (check_for_node(node_sp, "interval")) then
! User gave an interval for writing source points
call get_node_value(node_sp, "interval", temp_int)
n_source_points = n_batches / temp_int
do i = 1, n_source_points
call sourcepoint_batch % add(temp_int * i)
end do
else
! If neither were specified, write source points with state points
n_source_points = n_state_points

226
tests/test_asymmetric_lattice/inputs_true.dat
View file

@ -1 +1,225 @@
6bcc9cca24d42995bdff9bf9aca5e852c2dbca5cfb42a12ac637def9cf5cac227654182fc9cf9e17d07cf2e9af11fea832e3ae0eb7001cc09856f73d219664f9
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell fill="202" id="1" region="10000 -10001 10002 -10003 10004 -10005" universe="0" />
<cell id="27" material="1" region="-1" universe="3" />
<cell id="28" material="2" region="1 -2" universe="3" />
<cell id="29" material="4" region="2" universe="3" />
<cell id="30" material="4" region="-3" universe="4" />
<cell id="31" material="2" region="3 -4" universe="4" />
<cell id="32" material="4" region="4" universe="4" />
<cell id="70" material="4" region="35 -36" universe="7" />
<cell fill="101" id="80" region="35 -36" universe="8" />
<lattice id="101" name="Fuel assembly (upper half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 </universes>
</lattice>
<lattice id="202" name="3x3 Core Lattice">
<pitch>21.42 21.42</pitch>
<dimension>3 3</dimension>
<lower_left>-32.13 -32.13</lower_left>
<universes>
8 7 7
8 8 8
7 7 7 </universes>
</lattice>
<surface coeffs="0.0 0.0 0.41" id="1" type="z-cylinder" />
<surface boundary="reflective" coeffs="-32.13" id="10000" type="x-plane" />
<surface boundary="reflective" coeffs="32.13" id="10001" type="x-plane" />
<surface boundary="reflective" coeffs="-32.13" id="10002" type="y-plane" />
<surface boundary="reflective" coeffs="32.13" id="10003" type="y-plane" />
<surface boundary="reflective" coeffs="0" id="10004" type="z-plane" />
<surface boundary="reflective" coeffs="32.13" id="10005" type="z-plane" />
<surface coeffs="0.0 0.0 0.475" id="2" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.56" id="3" type="z-cylinder" />
<surface coeffs="0.0" id="35" type="z-plane" />
<surface coeffs="183.0" id="36" type="z-plane" />
<surface coeffs="0.0 0.0 0.62" id="4" type="z-cylinder" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="Fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
<nuclide ao="0.021504" name="U238" />
<nuclide ao="1.0801e-08" name="Xe135" />
<nuclide ao="0.045737" name="O16" />
</material>
<material id="10" name="Top nozzle region">
<density units="g/cm3" value="1.746" />
<nuclide name="H1" wo="0.035887" />
<nuclide name="O16" wo="0.2847761" />
<nuclide name="B10" wo="0.000115699" />
<nuclide name="B11" wo="0.000527075" />
<nuclide name="Fe54" wo="0.02644016154" />
<nuclide name="Fe56" wo="0.43037146399" />
<nuclide name="Fe57" wo="0.0101152584" />
<nuclide name="Fe58" wo="0.00137211607" />
<nuclide name="Ni58" wo="0.04104621835" />
<nuclide name="Mn55" wo="0.0135739" />
<nuclide name="Cr52" wo="0.107931450781" />
<sab name="c_H_in_H2O" />
</material>
<material id="11" name="Top of fuel assemblies">
<density units="g/cm3" value="3.044" />
<nuclide name="H1" wo="0.0162913" />
<nuclide name="O16" wo="0.1292776" />
<nuclide name="B10" wo="5.25228e-05" />
<nuclide name="B11" wo="0.000239272" />
<nuclide name="Zr90" wo="0.43313403903" />
<nuclide name="Zr91" wo="0.09549277374" />
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" />
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
<nuclide name="H1" wo="0.0292856" />
<nuclide name="O16" wo="0.2323919" />
<nuclide name="B10" wo="9.44159e-05" />
<nuclide name="B11" wo="0.00043012" />
<nuclide name="Zr90" wo="0.3741373658" />
<nuclide name="Zr91" wo="0.0824858164" />
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" />
</material>
<material id="2" name="Cladding">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="Cold borated water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
<nuclide name="Fe54" wo="0.05437098" />
<nuclide name="Fe56" wo="0.88500663" />
<nuclide name="Fe57" wo="0.0208008" />
<nuclide name="Fe58" wo="0.00282159" />
<nuclide name="Ni58" wo="0.0067198" />
<nuclide name="Ni60" wo="0.0026776" />
<nuclide name="Mn55" wo="0.01" />
<nuclide name="Cr52" wo="0.002092475" />
<nuclide name="C0" wo="0.0025" />
<nuclide name="Cu63" wo="0.0013696" />
</material>
<material id="6" name="Lower radial reflector">
<density units="g/cm3" value="4.32" />
<nuclide name="H1" wo="0.0095661" />
<nuclide name="O16" wo="0.0759107" />
<nuclide name="B10" wo="3.08409e-05" />
<nuclide name="B11" wo="0.000140499" />
<nuclide name="Fe54" wo="0.035620772088" />
<nuclide name="Fe56" wo="0.579805982228" />
<nuclide name="Fe57" wo="0.01362750048" />
<nuclide name="Fe58" wo="0.001848545204" />
<nuclide name="Ni58" wo="0.055298376566" />
<nuclide name="Mn55" wo="0.018287" />
<nuclide name="Cr52" wo="0.145407678031" />
<sab name="c_H_in_H2O" />
</material>
<material id="7" name="Upper radial reflector /Top plate region">
<density units="g/cm3" value="4.28" />
<nuclide name="H1" wo="0.0086117" />
<nuclide name="O16" wo="0.0683369" />
<nuclide name="B10" wo="2.77638e-05" />
<nuclide name="B11" wo="0.000126481" />
<nuclide name="Fe54" wo="0.035953677186" />
<nuclide name="Fe56" wo="0.585224740891" />
<nuclide name="Fe57" wo="0.01375486056" />
<nuclide name="Fe58" wo="0.001865821363" />
<nuclide name="Ni58" wo="0.055815129186" />
<nuclide name="Mn55" wo="0.0184579" />
<nuclide name="Cr52" wo="0.146766614995" />
<sab name="c_H_in_H2O" />
</material>
<material id="8" name="Bottom plate region">
<density units="g/cm3" value="7.184" />
<nuclide name="H1" wo="0.0011505" />
<nuclide name="O16" wo="0.0091296" />
<nuclide name="B10" wo="3.70915e-06" />
<nuclide name="B11" wo="1.68974e-05" />
<nuclide name="Fe54" wo="0.03855611055" />
<nuclide name="Fe56" wo="0.627585036425" />
<nuclide name="Fe57" wo="0.014750478" />
<nuclide name="Fe58" wo="0.002000875025" />
<nuclide name="Ni58" wo="0.059855207342" />
<nuclide name="Mn55" wo="0.019794" />
<nuclide name="Cr52" wo="0.157390026871" />
<sab name="c_H_in_H2O" />
</material>
<material id="9" name="Bottom nozzle region">
<density units="g/cm3" value="2.53" />
<nuclide name="H1" wo="0.0245014" />
<nuclide name="O16" wo="0.1944274" />
<nuclide name="B10" wo="7.89917e-05" />
<nuclide name="B11" wo="0.000359854" />
<nuclide name="Fe54" wo="0.030411411144" />
<nuclide name="Fe56" wo="0.495012237964" />
<nuclide name="Fe57" wo="0.01163454624" />
<nuclide name="Fe58" wo="0.001578204652" />
<nuclide name="Ni58" wo="0.047211231662" />
<nuclide name="Mn55" wo="0.0156126" />
<nuclide name="Cr52" wo="0.124142524198" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
</eigenvalue>
<source strength="1.0">
<space type="fission">
<parameters>-32 -32 0 32 32 32</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<tally id="27" name="distribcell tally">
<filter bins="27" type="distribcell" />
<scores>nu-fission</scores>
</tally>
</tallies>

6
tests/test_asymmetric_lattice/test_asymmetric_lattice.py
View file

@ -69,7 +69,6 @@ class AsymmetricLatticeTestHarness(PyAPITestHarness):
source = openmc.Source(space=openmc.stats.Box([-32, -32, 0], [32, 32, 32]))
source.space.only_fissionable = True
self._input_set.settings.source = source
self._input_set.settings.output = {'summary': True}
# Write input XML files
self._input_set.export()
@ -107,11 +106,6 @@ class AsymmetricLatticeTestHarness(PyAPITestHarness):
return outstr
def _cleanup(self):
super(AsymmetricLatticeTestHarness, self)._cleanup()
f = os.path.join(os.getcwd(), 'tallies.xml')
if os.path.exists(f): os.remove(f)
if __name__ == '__main__':
harness = AsymmetricLatticeTestHarness('statepoint.10.h5', True)

39
tests/test_create_fission_neutrons/inputs_true.dat
View file

@ -1 +1,38 @@
2feaef10cd32d90d89bf3f1c10cddcb7b1c2daaf739dfe13427c3453168cef0d9f57d272bab24d4493bdcae6f97e2afdf636f5b966a7a93d1d16edb6728cc2eb
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="box" region="1 -2 3 -4 5 -6" universe="0" />
<surface boundary="reflective" coeffs="-1" id="1" type="x-plane" />
<surface boundary="reflective" coeffs="1" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="-1" id="3" type="y-plane" />
<surface boundary="reflective" coeffs="1" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="-1" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="1" id="6" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="mat">
<density units="atom/b-cm" value="0.069335" />
<nuclide ao="40.0" name="H1" />
<nuclide ao="1.0" name="U235" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<fixed_source>
<particles>100</particles>
<batches>10</batches>
</fixed_source>
<source strength="1.0">
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
<energy parameters="988000.0 2.249e-06" type="watt" />
</source>
<create_fission_neutrons>false</create_fission_neutrons>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<tally id="1">
<scores>flux</scores>
</tally>
</tallies>

12
tests/test_create_fission_neutrons/test_create_fission_neutrons.py
View file

@ -62,18 +62,12 @@ class CreateFissionNeutronsTestHarness(PyAPITestHarness):
# Write out tally data.
outstr = ''
t = sp.get_tally()
outstr += 'tally {0}:\n'.format(t.id)
outstr += 'sum = {0:12.6E}\n'.format(t.sum[0, 0, 0])
outstr += 'sum_sq = {0:12.6E}\n'.format(t.sum_sq[0, 0, 0])
outstr += 'tally {}:\n'.format(t.id)
outstr += 'sum = {:12.6E}\n'.format(t.sum[0, 0, 0])
outstr += 'sum_sq = {:12.6E}\n'.format(t.sum_sq[0, 0, 0])
return outstr
def _cleanup(self):
super(CreateFissionNeutronsTestHarness, self)._cleanup()
f = os.path.join(os.getcwd(), 'tallies.xml')
if os.path.exists(f):
os.remove(f)
if __name__ == '__main__':
harness = CreateFissionNeutronsTestHarness('statepoint.10.h5', True)

440
tests/test_diff_tally/inputs_true.dat
View file

@ -1 +1,439 @@
df5a0ee7d353fe25344496058cea42e3244a7ab32c13c34c03b4b2f6adf88579f08a71ec0d22d8d264e50e3663717068ff54308e2d16aed8e085c222a8c2fdbd
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell fill="200" id="1" region="-6 34 -35" universe="0" />
<cell id="10" material="5" region="7 -8 31 -39" universe="0" />
<cell id="11" material="6" region="5 -6 32 -34" universe="0" />
<cell id="12" material="7" region="5 -6 36 -38" universe="0" />
<cell fill="201" id="2" region="-6 35 -36" universe="0" />
<cell id="21" material="1" region="-1" universe="1" />
<cell id="22" material="2" region="1 -2" universe="1" />
<cell id="23" material="3" region="2" universe="1" />
<cell id="24" material="3" region="-3" universe="2" />
<cell id="25" material="2" region="3 -4" universe="2" />
<cell id="26" material="3" region="4" universe="2" />
<cell id="27" material="1" region="-1" universe="3" />
<cell id="28" material="2" region="1 -2" universe="3" />
<cell id="29" material="4" region="2" universe="3" />
<cell id="3" material="8" region="-7 31 -32" universe="0" />
<cell id="30" material="4" region="-3" universe="4" />
<cell id="31" material="2" region="3 -4" universe="4" />
<cell id="32" material="4" region="4" universe="4" />
<cell id="4" material="9" region="-5 32 -33" universe="0" />
<cell id="5" material="12" region="-5 33 -34" universe="0" />
<cell id="50" material="3" region="34 -35" universe="5" />
<cell id="6" material="11" region="-5 36 -37" universe="0" />
<cell fill="100" id="60" region="34 -35" universe="6" />
<cell id="7" material="10" region="-5 37 -38" universe="0" />
<cell id="70" material="4" region="35 -36" universe="7" />
<cell id="8" material="7" region="-7 38 -39" universe="0" />
<cell fill="101" id="80" region="35 -36" universe="8" />
<cell id="9" material="9" region="6 -7 32 -38" universe="0" />
<lattice id="100" name="Fuel assembly (lower half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 </universes>
</lattice>
<lattice id="101" name="Fuel assembly (upper half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 </universes>
</lattice>
<lattice id="200" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 </universes>
</lattice>
<lattice id="201" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 </universes>
</lattice>
<surface coeffs="0.0 0.0 0.41" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.475" id="2" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.56" id="3" type="z-cylinder" />
<surface boundary="vacuum" coeffs="-229.0" id="31" type="z-plane" />
<surface coeffs="-199.0" id="32" type="z-plane" />
<surface coeffs="-193.0" id="33" type="z-plane" />
<surface coeffs="-183.0" id="34" type="z-plane" />
<surface coeffs="0.0" id="35" type="z-plane" />
<surface coeffs="183.0" id="36" type="z-plane" />
<surface coeffs="203.0" id="37" type="z-plane" />
<surface coeffs="215.0" id="38" type="z-plane" />
<surface boundary="vacuum" coeffs="223.0" id="39" type="z-plane" />
<surface coeffs="0.0 0.0 0.62" id="4" type="z-cylinder" />
<surface coeffs="0.0 0.0 187.6" id="5" type="z-cylinder" />
<surface coeffs="0.0 0.0 209.0" id="6" type="z-cylinder" />
<surface coeffs="0.0 0.0 229.0" id="7" type="z-cylinder" />
<surface boundary="vacuum" coeffs="0.0 0.0 249.0" id="8" type="z-cylinder" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="Fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
<nuclide ao="0.021504" name="U238" />
<nuclide ao="1.0801e-08" name="Xe135" />
<nuclide ao="0.045737" name="O16" />
</material>
<material id="10" name="Top nozzle region">
<density units="g/cm3" value="1.746" />
<nuclide name="H1" wo="0.035887" />
<nuclide name="O16" wo="0.2847761" />
<nuclide name="B10" wo="0.000115699" />
<nuclide name="B11" wo="0.000527075" />
<nuclide name="Fe54" wo="0.02644016154" />
<nuclide name="Fe56" wo="0.43037146399" />
<nuclide name="Fe57" wo="0.0101152584" />
<nuclide name="Fe58" wo="0.00137211607" />
<nuclide name="Ni58" wo="0.04104621835" />
<nuclide name="Mn55" wo="0.0135739" />
<nuclide name="Cr52" wo="0.107931450781" />
<sab name="c_H_in_H2O" />
</material>
<material id="11" name="Top of fuel assemblies">
<density units="g/cm3" value="3.044" />
<nuclide name="H1" wo="0.0162913" />
<nuclide name="O16" wo="0.1292776" />
<nuclide name="B10" wo="5.25228e-05" />
<nuclide name="B11" wo="0.000239272" />
<nuclide name="Zr90" wo="0.43313403903" />
<nuclide name="Zr91" wo="0.09549277374" />
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" />
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
<nuclide name="H1" wo="0.0292856" />
<nuclide name="O16" wo="0.2323919" />
<nuclide name="B10" wo="9.44159e-05" />
<nuclide name="B11" wo="0.00043012" />
<nuclide name="Zr90" wo="0.3741373658" />
<nuclide name="Zr91" wo="0.0824858164" />
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" />
</material>
<material id="2" name="Cladding">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="Cold borated water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
<nuclide name="Fe54" wo="0.05437098" />
<nuclide name="Fe56" wo="0.88500663" />
<nuclide name="Fe57" wo="0.0208008" />
<nuclide name="Fe58" wo="0.00282159" />
<nuclide name="Ni58" wo="0.0067198" />
<nuclide name="Ni60" wo="0.0026776" />
<nuclide name="Mn55" wo="0.01" />
<nuclide name="Cr52" wo="0.002092475" />
<nuclide name="C0" wo="0.0025" />
<nuclide name="Cu63" wo="0.0013696" />
</material>
<material id="6" name="Lower radial reflector">
<density units="g/cm3" value="4.32" />
<nuclide name="H1" wo="0.0095661" />
<nuclide name="O16" wo="0.0759107" />
<nuclide name="B10" wo="3.08409e-05" />
<nuclide name="B11" wo="0.000140499" />
<nuclide name="Fe54" wo="0.035620772088" />
<nuclide name="Fe56" wo="0.579805982228" />
<nuclide name="Fe57" wo="0.01362750048" />
<nuclide name="Fe58" wo="0.001848545204" />
<nuclide name="Ni58" wo="0.055298376566" />
<nuclide name="Mn55" wo="0.018287" />
<nuclide name="Cr52" wo="0.145407678031" />
<sab name="c_H_in_H2O" />
</material>
<material id="7" name="Upper radial reflector /Top plate region">
<density units="g/cm3" value="4.28" />
<nuclide name="H1" wo="0.0086117" />
<nuclide name="O16" wo="0.0683369" />
<nuclide name="B10" wo="2.77638e-05" />
<nuclide name="B11" wo="0.000126481" />
<nuclide name="Fe54" wo="0.035953677186" />
<nuclide name="Fe56" wo="0.585224740891" />
<nuclide name="Fe57" wo="0.01375486056" />
<nuclide name="Fe58" wo="0.001865821363" />
<nuclide name="Ni58" wo="0.055815129186" />
<nuclide name="Mn55" wo="0.0184579" />
<nuclide name="Cr52" wo="0.146766614995" />
<sab name="c_H_in_H2O" />
</material>
<material id="8" name="Bottom plate region">
<density units="g/cm3" value="7.184" />
<nuclide name="H1" wo="0.0011505" />
<nuclide name="O16" wo="0.0091296" />
<nuclide name="B10" wo="3.70915e-06" />
<nuclide name="B11" wo="1.68974e-05" />
<nuclide name="Fe54" wo="0.03855611055" />
<nuclide name="Fe56" wo="0.627585036425" />
<nuclide name="Fe57" wo="0.014750478" />
<nuclide name="Fe58" wo="0.002000875025" />
<nuclide name="Ni58" wo="0.059855207342" />
<nuclide name="Mn55" wo="0.019794" />
<nuclide name="Cr52" wo="0.157390026871" />
<sab name="c_H_in_H2O" />
</material>
<material id="9" name="Bottom nozzle region">
<density units="g/cm3" value="2.53" />
<nuclide name="H1" wo="0.0245014" />
<nuclide name="O16" wo="0.1944274" />
<nuclide name="B10" wo="7.89917e-05" />
<nuclide name="B11" wo="0.000359854" />
<nuclide name="Fe54" wo="0.030411411144" />
<nuclide name="Fe56" wo="0.495012237964" />
<nuclide name="Fe57" wo="0.01163454624" />
<nuclide name="Fe58" wo="0.001578204652" />
<nuclide name="Ni58" wo="0.047211231662" />
<nuclide name="Mn55" wo="0.0156126" />
<nuclide name="Cr52" wo="0.124142524198" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>100</particles>
<batches>3</batches>
<inactive>0</inactive>
</eigenvalue>
<source strength="1.0">
<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
<temperature_multipole>True</temperature_multipole>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<tally id="10000">
<filter bins="1 3" type="material" />
<scores>flux</scores>
<derivative>1</derivative>
</tally>
<tally id="10001">
<filter bins="1 3" type="material" />
<scores>flux</scores>
<derivative>2</derivative>
</tally>
<tally id="10002">
<filter bins="1 3" type="material" />
<scores>flux</scores>
<derivative>3</derivative>
</tally>
<tally id="10003">
<filter bins="1 3" type="material" />
<scores>flux</scores>
<derivative>4</derivative>
</tally>
<tally id="10004">
<filter bins="1 3" type="material" />
<scores>flux</scores>
<derivative>5</derivative>
</tally>
<tally id="10005">
<filter bins="1 3" type="material" />
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>1</derivative>
</tally>
<tally id="10006">
<filter bins="1 3" type="material" />
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>2</derivative>
</tally>
<tally id="10007">
<filter bins="1 3" type="material" />
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>3</derivative>
</tally>
<tally id="10008">
<filter bins="1 3" type="material" />
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>4</derivative>
</tally>
<tally id="10009">
<filter bins="1 3" type="material" />
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>5</derivative>
</tally>
<tally id="10010">
<filter bins="1 3" type="material" />
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>1</derivative>
</tally>
<tally id="10011">
<filter bins="1 3" type="material" />
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>2</derivative>
</tally>
<tally id="10012">
<filter bins="1 3" type="material" />
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>3</derivative>
</tally>
<tally id="10013">
<filter bins="1 3" type="material" />
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>4</derivative>
</tally>
<tally id="10014">
<filter bins="1 3" type="material" />
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>5</derivative>
</tally>
<tally id="10015">
<filter bins="1 3" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>total U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>1</derivative>
</tally>
<tally id="10016">
<filter bins="1 3" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>total U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>2</derivative>
</tally>
<tally id="10017">
<filter bins="1 3" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>3</derivative>
</tally>
<tally id="10018">
<filter bins="1 3" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>4</derivative>
</tally>
<tally id="10019">
<filter bins="1 3" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>5</derivative>
</tally>
<derivative id="1" material="3" variable="density" />
<derivative id="2" material="1" variable="density" />
<derivative id="3" material="1" nuclide="O16" variable="nuclide_density" />
<derivative id="4" material="1" nuclide="U235" variable="nuclide_density" />
<derivative id="5" material="1" variable="temperature" />
</tallies>

5
tests/test_diff_tally/test_diff_tally.py
View file

@ -129,11 +129,6 @@ class DiffTallyTestHarness(PyAPITestHarness):
'std. dev.')
return df.to_csv(None, columns=cols, index=False, float_format='%.7e')
def _cleanup(self):
super(DiffTallyTestHarness, self)._cleanup()
f = os.path.join(os.getcwd(), 'tallies.xml')
if os.path.exists(f): os.remove(f)
if __name__ == '__main__':
harness = DiffTallyTestHarness('statepoint.3.h5', True)

67
tests/test_distribmat/inputs_true.dat
View file

@ -1 +1,66 @@
6ae54c198e7659503d297e40be746a5bd72b35909fceed4b3ef357876b781946c0ea5021342556ef21f4034fa9e42b2c6014077c0efd3459dc063e6da4b12b59
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" universe="1" />
<cell fill="101" id="101" region="10001 -10002 10003 -10004" universe="0" />
<cell id="11" material="2 3 void 2" region="-10000" universe="11" />
<cell id="12" material="1" region="10000" universe="11" />
<lattice id="101">
<pitch>2.0 2.0</pitch>
<outer>1</outer>
<dimension>2 2</dimension>
<lower_left>-2.0 -2.0</lower_left>
<universes>
11 11
11 11 </universes>
</lattice>
<surface coeffs="0.0 0.0 0.3" id="10000" type="z-cylinder" />
<surface boundary="reflective" coeffs="-3.0" id="10001" type="x-plane" />
<surface boundary="reflective" coeffs="3.0" id="10002" type="x-plane" />
<surface boundary="reflective" coeffs="-3.0" id="10003" type="y-plane" />
<surface boundary="reflective" coeffs="3.0" id="10004" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1">
<density units="g/cc" value="1.0" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
<material id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="3">
<density units="g/cc" value="2.0" />
<nuclide ao="1.0" name="U235" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>1000</particles>
<batches>5</batches>
<inactive>0</inactive>
</eigenvalue>
<source strength="1.0">
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
</source>
<output>
<summary>true</summary>
</output>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<plots>
<plot basis="xy" color="cell" filename="cellplot" id="1" type="slice">
<origin>0 0 0</origin>
<width>7 7</width>
<pixels>400 400</pixels>
</plot>
<plot basis="xy" color="mat" filename="matplot" id="2" type="slice">
<origin>0 0 0</origin>
<width>7 7</width>
<pixels>400 400</pixels>
</plot>
</plots>

41
tests/test_energy_cutoff/inputs_true.dat
View file

@ -1 +1,40 @@
3c242912caf520c09de59edc2911d886fe77041577c1ab6a57985527f5b9e34d79d74c1fefff13d83462909d37d2318626cc14dcc717ce42f32420a799bd5c58
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="box" region="1 -2 3 -4 5 -6" universe="0" />
<surface boundary="reflective" coeffs="-1" id="1" type="x-plane" />
<surface boundary="reflective" coeffs="1" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="-1" id="3" type="y-plane" />
<surface boundary="reflective" coeffs="1" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="-1" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="1" id="6" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="mat">
<density units="atom/b-cm" value="0.069335" />
<nuclide ao="40.0" name="H1" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<fixed_source>
<particles>100</particles>
<batches>10</batches>
</fixed_source>
<source strength="1.0">
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
<energy parameters="988000.0 2.249e-06" type="watt" />
</source>
<cutoff>
<energy>4.0</energy>
</cutoff>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<tally id="1">
<filter bins="0.0 4.0" type="energy" />
<scores>flux</scores>
</tally>
</tallies>

12
tests/test_energy_cutoff/test_energy_cutoff.py
View file

@ -66,18 +66,12 @@ class EnergyCutoffTestHarness(PyAPITestHarness):
# Write out tally data.
outstr = ''
t = sp.get_tally()
outstr += 'tally {0}:\n'.format(t.id)
outstr += 'sum = {0:12.6E}\n'.format(t.sum[0, 0, 0])
outstr += 'sum_sq = {0:12.6E}\n'.format(t.sum_sq[0, 0, 0])
outstr += 'tally {}:\n'.format(t.id)
outstr += 'sum = {:12.6E}\n'.format(t.sum[0, 0, 0])
outstr += 'sum_sq = {:12.6E}\n'.format(t.sum_sq[0, 0, 0])
return outstr
def _cleanup(self):
super(EnergyCutoffTestHarness, self)._cleanup()
f = os.path.join(os.getcwd(), 'tallies.xml')
if os.path.exists(f):
os.remove(f)
if __name__ == '__main__':
harness = EnergyCutoffTestHarness('statepoint.10.h5', True)

324
tests/test_filter_energyfun/inputs_true.dat
View file

@ -1 +1,323 @@
2a08e03d9e0f40486fa26ba00800d264f43906a38c851da48f0fd76bacc0b862e8f45f16c970b7c62db03d96e3acb1b58e74179f554a851ccaaf4492e97fc163
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell fill="200" id="1" region="-6 34 -35" universe="0" />
<cell id="10" material="5" region="7 -8 31 -39" universe="0" />
<cell id="11" material="6" region="5 -6 32 -34" universe="0" />
<cell id="12" material="7" region="5 -6 36 -38" universe="0" />
<cell fill="201" id="2" region="-6 35 -36" universe="0" />
<cell id="21" material="1" region="-1" universe="1" />
<cell id="22" material="2" region="1 -2" universe="1" />
<cell id="23" material="3" region="2" universe="1" />
<cell id="24" material="3" region="-3" universe="2" />
<cell id="25" material="2" region="3 -4" universe="2" />
<cell id="26" material="3" region="4" universe="2" />
<cell id="27" material="1" region="-1" universe="3" />
<cell id="28" material="2" region="1 -2" universe="3" />
<cell id="29" material="4" region="2" universe="3" />
<cell id="3" material="8" region="-7 31 -32" universe="0" />
<cell id="30" material="4" region="-3" universe="4" />
<cell id="31" material="2" region="3 -4" universe="4" />
<cell id="32" material="4" region="4" universe="4" />
<cell id="4" material="9" region="-5 32 -33" universe="0" />
<cell id="5" material="12" region="-5 33 -34" universe="0" />
<cell id="50" material="3" region="34 -35" universe="5" />
<cell id="6" material="11" region="-5 36 -37" universe="0" />
<cell fill="100" id="60" region="34 -35" universe="6" />
<cell id="7" material="10" region="-5 37 -38" universe="0" />
<cell id="70" material="4" region="35 -36" universe="7" />
<cell id="8" material="7" region="-7 38 -39" universe="0" />
<cell fill="101" id="80" region="35 -36" universe="8" />
<cell id="9" material="9" region="6 -7 32 -38" universe="0" />
<lattice id="100" name="Fuel assembly (lower half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 </universes>
</lattice>
<lattice id="101" name="Fuel assembly (upper half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 </universes>
</lattice>
<lattice id="200" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 </universes>
</lattice>
<lattice id="201" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 </universes>
</lattice>
<surface coeffs="0.0 0.0 0.41" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.475" id="2" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.56" id="3" type="z-cylinder" />
<surface boundary="vacuum" coeffs="-229.0" id="31" type="z-plane" />
<surface coeffs="-199.0" id="32" type="z-plane" />
<surface coeffs="-193.0" id="33" type="z-plane" />
<surface coeffs="-183.0" id="34" type="z-plane" />
<surface coeffs="0.0" id="35" type="z-plane" />
<surface coeffs="183.0" id="36" type="z-plane" />
<surface coeffs="203.0" id="37" type="z-plane" />
<surface coeffs="215.0" id="38" type="z-plane" />
<surface boundary="vacuum" coeffs="223.0" id="39" type="z-plane" />
<surface coeffs="0.0 0.0 0.62" id="4" type="z-cylinder" />
<surface coeffs="0.0 0.0 187.6" id="5" type="z-cylinder" />
<surface coeffs="0.0 0.0 209.0" id="6" type="z-cylinder" />
<surface coeffs="0.0 0.0 229.0" id="7" type="z-cylinder" />
<surface boundary="vacuum" coeffs="0.0 0.0 249.0" id="8" type="z-cylinder" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="Fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
<nuclide ao="0.021504" name="U238" />
<nuclide ao="1.0801e-08" name="Xe135" />
<nuclide ao="0.045737" name="O16" />
</material>
<material id="10" name="Top nozzle region">
<density units="g/cm3" value="1.746" />
<nuclide name="H1" wo="0.035887" />
<nuclide name="O16" wo="0.2847761" />
<nuclide name="B10" wo="0.000115699" />
<nuclide name="B11" wo="0.000527075" />
<nuclide name="Fe54" wo="0.02644016154" />
<nuclide name="Fe56" wo="0.43037146399" />
<nuclide name="Fe57" wo="0.0101152584" />
<nuclide name="Fe58" wo="0.00137211607" />
<nuclide name="Ni58" wo="0.04104621835" />
<nuclide name="Mn55" wo="0.0135739" />
<nuclide name="Cr52" wo="0.107931450781" />
<sab name="c_H_in_H2O" />
</material>
<material id="11" name="Top of fuel assemblies">
<density units="g/cm3" value="3.044" />
<nuclide name="H1" wo="0.0162913" />
<nuclide name="O16" wo="0.1292776" />
<nuclide name="B10" wo="5.25228e-05" />
<nuclide name="B11" wo="0.000239272" />
<nuclide name="Zr90" wo="0.43313403903" />
<nuclide name="Zr91" wo="0.09549277374" />
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" />
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
<nuclide name="H1" wo="0.0292856" />
<nuclide name="O16" wo="0.2323919" />
<nuclide name="B10" wo="9.44159e-05" />
<nuclide name="B11" wo="0.00043012" />
<nuclide name="Zr90" wo="0.3741373658" />
<nuclide name="Zr91" wo="0.0824858164" />
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" />
</material>
<material id="2" name="Cladding">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
<nuclide ao="1e-07" name="Am241" />
</material>
<material id="3" name="Cold borated water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
<nuclide name="Fe54" wo="0.05437098" />
<nuclide name="Fe56" wo="0.88500663" />
<nuclide name="Fe57" wo="0.0208008" />
<nuclide name="Fe58" wo="0.00282159" />
<nuclide name="Ni58" wo="0.0067198" />
<nuclide name="Ni60" wo="0.0026776" />
<nuclide name="Mn55" wo="0.01" />
<nuclide name="Cr52" wo="0.002092475" />
<nuclide name="C0" wo="0.0025" />
<nuclide name="Cu63" wo="0.0013696" />
</material>
<material id="6" name="Lower radial reflector">
<density units="g/cm3" value="4.32" />
<nuclide name="H1" wo="0.0095661" />
<nuclide name="O16" wo="0.0759107" />
<nuclide name="B10" wo="3.08409e-05" />
<nuclide name="B11" wo="0.000140499" />
<nuclide name="Fe54" wo="0.035620772088" />
<nuclide name="Fe56" wo="0.579805982228" />
<nuclide name="Fe57" wo="0.01362750048" />
<nuclide name="Fe58" wo="0.001848545204" />
<nuclide name="Ni58" wo="0.055298376566" />
<nuclide name="Mn55" wo="0.018287" />
<nuclide name="Cr52" wo="0.145407678031" />
<sab name="c_H_in_H2O" />
</material>
<material id="7" name="Upper radial reflector /Top plate region">
<density units="g/cm3" value="4.28" />
<nuclide name="H1" wo="0.0086117" />
<nuclide name="O16" wo="0.0683369" />
<nuclide name="B10" wo="2.77638e-05" />
<nuclide name="B11" wo="0.000126481" />
<nuclide name="Fe54" wo="0.035953677186" />
<nuclide name="Fe56" wo="0.585224740891" />
<nuclide name="Fe57" wo="0.01375486056" />
<nuclide name="Fe58" wo="0.001865821363" />
<nuclide name="Ni58" wo="0.055815129186" />
<nuclide name="Mn55" wo="0.0184579" />
<nuclide name="Cr52" wo="0.146766614995" />
<sab name="c_H_in_H2O" />
</material>
<material id="8" name="Bottom plate region">
<density units="g/cm3" value="7.184" />
<nuclide name="H1" wo="0.0011505" />
<nuclide name="O16" wo="0.0091296" />
<nuclide name="B10" wo="3.70915e-06" />
<nuclide name="B11" wo="1.68974e-05" />
<nuclide name="Fe54" wo="0.03855611055" />
<nuclide name="Fe56" wo="0.627585036425" />
<nuclide name="Fe57" wo="0.014750478" />
<nuclide name="Fe58" wo="0.002000875025" />
<nuclide name="Ni58" wo="0.059855207342" />
<nuclide name="Mn55" wo="0.019794" />
<nuclide name="Cr52" wo="0.157390026871" />
<sab name="c_H_in_H2O" />
</material>
<material id="9" name="Bottom nozzle region">
<density units="g/cm3" value="2.53" />
<nuclide name="H1" wo="0.0245014" />
<nuclide name="O16" wo="0.1944274" />
<nuclide name="B10" wo="7.89917e-05" />
<nuclide name="B11" wo="0.000359854" />
<nuclide name="Fe54" wo="0.030411411144" />
<nuclide name="Fe56" wo="0.495012237964" />
<nuclide name="Fe57" wo="0.01163454624" />
<nuclide name="Fe58" wo="0.001578204652" />
<nuclide name="Ni58" wo="0.047211231662" />
<nuclide name="Mn55" wo="0.0156126" />
<nuclide name="Cr52" wo="0.124142524198" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
</eigenvalue>
<source strength="1.0">
<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<tally id="10000">
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<tally id="10001">
<filter energy="1e-05 0.369 1000.0 100000.0 600000.0 1000000.0 2000000.0 4000000.0 30000000.0" type="energyfunction" y="0.1 0.1 0.1333 0.158 0.18467 0.25618 0.4297 0.48 0.48" />
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
</tallies>

5
tests/test_filter_energyfun/test_filter_energyfun.py
View file

@ -53,11 +53,6 @@ class FilterEnergyFunHarness(PyAPITestHarness):
# Output the tally in a Pandas DataFrame.
return br_tally.get_pandas_dataframe().to_string() + '\n'
def _cleanup(self):
super(FilterEnergyFunHarness, self)._cleanup()
f = os.path.join(os.getcwd(), 'tallies.xml')
if os.path.exists(f): os.remove(f)
if __name__ == '__main__':
harness = FilterEnergyFunHarness('statepoint.10.h5', True)

356
tests/test_filter_mesh/inputs_true.dat
View file

@ -1 +1,355 @@
c0882d16048d434219d32ed7b875615e00142b55ab78be5b51e0195e23cb534a3aa5a8e9c212f0bfff96c452177315deb1264421d688438814560b4131c88930
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell fill="200" id="1" region="-6 34 -35" universe="0" />
<cell id="10" material="5" region="7 -8 31 -39" universe="0" />
<cell id="11" material="6" region="5 -6 32 -34" universe="0" />
<cell id="12" material="7" region="5 -6 36 -38" universe="0" />
<cell fill="201" id="2" region="-6 35 -36" universe="0" />
<cell id="21" material="1" region="-1" universe="1" />
<cell id="22" material="2" region="1 -2" universe="1" />
<cell id="23" material="3" region="2" universe="1" />
<cell id="24" material="3" region="-3" universe="2" />
<cell id="25" material="2" region="3 -4" universe="2" />
<cell id="26" material="3" region="4" universe="2" />
<cell id="27" material="1" region="-1" universe="3" />
<cell id="28" material="2" region="1 -2" universe="3" />
<cell id="29" material="4" region="2" universe="3" />
<cell id="3" material="8" region="-7 31 -32" universe="0" />
<cell id="30" material="4" region="-3" universe="4" />
<cell id="31" material="2" region="3 -4" universe="4" />
<cell id="32" material="4" region="4" universe="4" />
<cell id="4" material="9" region="-5 32 -33" universe="0" />
<cell id="5" material="12" region="-5 33 -34" universe="0" />
<cell id="50" material="3" region="34 -35" universe="5" />
<cell id="6" material="11" region="-5 36 -37" universe="0" />
<cell fill="100" id="60" region="34 -35" universe="6" />
<cell id="7" material="10" region="-5 37 -38" universe="0" />
<cell id="70" material="4" region="35 -36" universe="7" />
<cell id="8" material="7" region="-7 38 -39" universe="0" />
<cell fill="101" id="80" region="35 -36" universe="8" />
<cell id="9" material="9" region="6 -7 32 -38" universe="0" />
<lattice id="100" name="Fuel assembly (lower half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 </universes>
</lattice>
<lattice id="101" name="Fuel assembly (upper half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 </universes>
</lattice>
<lattice id="200" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 </universes>
</lattice>
<lattice id="201" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 </universes>
</lattice>
<surface coeffs="0.0 0.0 0.41" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.475" id="2" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.56" id="3" type="z-cylinder" />
<surface boundary="vacuum" coeffs="-229.0" id="31" type="z-plane" />
<surface coeffs="-199.0" id="32" type="z-plane" />
<surface coeffs="-193.0" id="33" type="z-plane" />
<surface coeffs="-183.0" id="34" type="z-plane" />
<surface coeffs="0.0" id="35" type="z-plane" />
<surface coeffs="183.0" id="36" type="z-plane" />
<surface coeffs="203.0" id="37" type="z-plane" />
<surface coeffs="215.0" id="38" type="z-plane" />
<surface boundary="vacuum" coeffs="223.0" id="39" type="z-plane" />
<surface coeffs="0.0 0.0 0.62" id="4" type="z-cylinder" />
<surface coeffs="0.0 0.0 187.6" id="5" type="z-cylinder" />
<surface coeffs="0.0 0.0 209.0" id="6" type="z-cylinder" />
<surface coeffs="0.0 0.0 229.0" id="7" type="z-cylinder" />
<surface boundary="vacuum" coeffs="0.0 0.0 249.0" id="8" type="z-cylinder" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="Fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
<nuclide ao="0.021504" name="U238" />
<nuclide ao="1.0801e-08" name="Xe135" />
<nuclide ao="0.045737" name="O16" />
</material>
<material id="10" name="Top nozzle region">
<density units="g/cm3" value="1.746" />
<nuclide name="H1" wo="0.035887" />
<nuclide name="O16" wo="0.2847761" />
<nuclide name="B10" wo="0.000115699" />
<nuclide name="B11" wo="0.000527075" />
<nuclide name="Fe54" wo="0.02644016154" />
<nuclide name="Fe56" wo="0.43037146399" />
<nuclide name="Fe57" wo="0.0101152584" />
<nuclide name="Fe58" wo="0.00137211607" />
<nuclide name="Ni58" wo="0.04104621835" />
<nuclide name="Mn55" wo="0.0135739" />
<nuclide name="Cr52" wo="0.107931450781" />
<sab name="c_H_in_H2O" />
</material>
<material id="11" name="Top of fuel assemblies">
<density units="g/cm3" value="3.044" />
<nuclide name="H1" wo="0.0162913" />
<nuclide name="O16" wo="0.1292776" />
<nuclide name="B10" wo="5.25228e-05" />
<nuclide name="B11" wo="0.000239272" />
<nuclide name="Zr90" wo="0.43313403903" />
<nuclide name="Zr91" wo="0.09549277374" />
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" />
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
<nuclide name="H1" wo="0.0292856" />
<nuclide name="O16" wo="0.2323919" />
<nuclide name="B10" wo="9.44159e-05" />
<nuclide name="B11" wo="0.00043012" />
<nuclide name="Zr90" wo="0.3741373658" />
<nuclide name="Zr91" wo="0.0824858164" />
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" />
</material>
<material id="2" name="Cladding">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="Cold borated water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
<nuclide name="Fe54" wo="0.05437098" />
<nuclide name="Fe56" wo="0.88500663" />
<nuclide name="Fe57" wo="0.0208008" />
<nuclide name="Fe58" wo="0.00282159" />
<nuclide name="Ni58" wo="0.0067198" />
<nuclide name="Ni60" wo="0.0026776" />
<nuclide name="Mn55" wo="0.01" />
<nuclide name="Cr52" wo="0.002092475" />
<nuclide name="C0" wo="0.0025" />
<nuclide name="Cu63" wo="0.0013696" />
</material>
<material id="6" name="Lower radial reflector">
<density units="g/cm3" value="4.32" />
<nuclide name="H1" wo="0.0095661" />
<nuclide name="O16" wo="0.0759107" />
<nuclide name="B10" wo="3.08409e-05" />
<nuclide name="B11" wo="0.000140499" />
<nuclide name="Fe54" wo="0.035620772088" />
<nuclide name="Fe56" wo="0.579805982228" />
<nuclide name="Fe57" wo="0.01362750048" />
<nuclide name="Fe58" wo="0.001848545204" />
<nuclide name="Ni58" wo="0.055298376566" />
<nuclide name="Mn55" wo="0.018287" />
<nuclide name="Cr52" wo="0.145407678031" />
<sab name="c_H_in_H2O" />
</material>
<material id="7" name="Upper radial reflector /Top plate region">
<density units="g/cm3" value="4.28" />
<nuclide name="H1" wo="0.0086117" />
<nuclide name="O16" wo="0.0683369" />
<nuclide name="B10" wo="2.77638e-05" />
<nuclide name="B11" wo="0.000126481" />
<nuclide name="Fe54" wo="0.035953677186" />
<nuclide name="Fe56" wo="0.585224740891" />
<nuclide name="Fe57" wo="0.01375486056" />
<nuclide name="Fe58" wo="0.001865821363" />
<nuclide name="Ni58" wo="0.055815129186" />
<nuclide name="Mn55" wo="0.0184579" />
<nuclide name="Cr52" wo="0.146766614995" />
<sab name="c_H_in_H2O" />
</material>
<material id="8" name="Bottom plate region">
<density units="g/cm3" value="7.184" />
<nuclide name="H1" wo="0.0011505" />
<nuclide name="O16" wo="0.0091296" />
<nuclide name="B10" wo="3.70915e-06" />
<nuclide name="B11" wo="1.68974e-05" />
<nuclide name="Fe54" wo="0.03855611055" />
<nuclide name="Fe56" wo="0.627585036425" />
<nuclide name="Fe57" wo="0.014750478" />
<nuclide name="Fe58" wo="0.002000875025" />
<nuclide name="Ni58" wo="0.059855207342" />
<nuclide name="Mn55" wo="0.019794" />
<nuclide name="Cr52" wo="0.157390026871" />
<sab name="c_H_in_H2O" />
</material>
<material id="9" name="Bottom nozzle region">
<density units="g/cm3" value="2.53" />
<nuclide name="H1" wo="0.0245014" />
<nuclide name="O16" wo="0.1944274" />
<nuclide name="B10" wo="7.89917e-05" />
<nuclide name="B11" wo="0.000359854" />
<nuclide name="Fe54" wo="0.030411411144" />
<nuclide name="Fe56" wo="0.495012237964" />
<nuclide name="Fe57" wo="0.01163454624" />
<nuclide name="Fe58" wo="0.001578204652" />
<nuclide name="Ni58" wo="0.047211231662" />
<nuclide name="Mn55" wo="0.0156126" />
<nuclide name="Cr52" wo="0.124142524198" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
</eigenvalue>
<source strength="1.0">
<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
<output>
<summary>true</summary>
</output>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1" type="regular">
<dimension>17</dimension>
<lower_left>-182.07</lower_left>
<upper_right>182.07</upper_right>
</mesh>
<mesh id="2" type="regular">
<dimension>17 17</dimension>
<lower_left>-182.07 -182.07</lower_left>
<upper_right>182.07 182.07</upper_right>
</mesh>
<mesh id="3" type="regular">
<dimension>17 17 17</dimension>
<lower_left>-182.07 -182.07 -183.0</lower_left>
<upper_right>182.07 182.07 183.0</upper_right>
</mesh>
<tally id="10000" name="tally 1">
<filter bins="1" type="mesh" />
<scores>total</scores>
</tally>
<tally id="10001" name="tally 2">
<filter bins="1" type="mesh" />
<scores>current</scores>
</tally>
<tally id="10002" name="tally 3">
<filter bins="2" type="mesh" />
<scores>total</scores>
</tally>
<tally id="10003" name="tally 4">
<filter bins="2" type="mesh" />
<scores>current</scores>
</tally>
<tally id="10004" name="tally 5">
<filter bins="3" type="mesh" />
<scores>total</scores>
</tally>
<tally id="10005" name="tally 6">
<filter bins="3" type="mesh" />
<scores>current</scores>
</tally>
</tallies>

7
tests/test_filter_mesh/test_filter_mesh.py
View file

@ -77,12 +77,7 @@ class FilterMeshTestHarness(HashedPyAPITestHarness):
self._input_set.tallies = tallies_file
super(FilterMeshTestHarness, self)._build_inputs()
def _cleanup(self):
super(FilterMeshTestHarness, self)._cleanup()
f = os.path.join(os.getcwd(), 'tallies.xml')
if os.path.exists(f): os.remove(f)
if __name__ == '__main__':
harness = FilterMeshTestHarness('statepoint.10.*', True)
harness = FilterMeshTestHarness('statepoint.10.h5', True)
harness.main()

311
tests/test_iso_in_lab/inputs_true.dat
View file

@ -1 +1,310 @@
57d1ece4aa9633e5fc6d2fce9f7bba444d02046e0cdadc6e53efdf591b6e50fd0e5a14b956b7ad10710b4535b10354899e2ffc783fd78de5ccd09a061cb5678d
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell fill="200" id="1" region="-6 34 -35" universe="0" />
<cell id="10" material="5" region="7 -8 31 -39" universe="0" />
<cell id="11" material="6" region="5 -6 32 -34" universe="0" />
<cell id="12" material="7" region="5 -6 36 -38" universe="0" />
<cell fill="201" id="2" region="-6 35 -36" universe="0" />
<cell id="21" material="1" region="-1" universe="1" />
<cell id="22" material="2" region="1 -2" universe="1" />
<cell id="23" material="3" region="2" universe="1" />
<cell id="24" material="3" region="-3" universe="2" />
<cell id="25" material="2" region="3 -4" universe="2" />
<cell id="26" material="3" region="4" universe="2" />
<cell id="27" material="1" region="-1" universe="3" />
<cell id="28" material="2" region="1 -2" universe="3" />
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99
tests/test_mg_basic/inputs_true.dat
View file

@ -1 +1,98 @@
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<source strength="1.0">
<space type="box">
<parameters>0.0 0.0 0.0 10.0 10.0 5.0</parameters>
</space>
</source>
<energy_mode>multi-group</energy_mode>
</settings>

46
tests/test_mg_max_order/inputs_true.dat
View file

@ -1 +1,45 @@
1f82e622b36562a0a14536fe24c95ee9c901c428f7f082f245afae5c699ccd647aaf31a49790822ceb7ec136bdb75f8e25c3677642f73702ca2e30b058f6b440
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="10000" material="10000" region="10000 -10001 10002 -10003 10004 -10005" universe="0" />
<cell id="10001" material="10001" region="10000 -10001 10002 -10003 10005 -10006" universe="0" />
<cell id="10002" material="10002" region="10000 -10001 10002 -10003 10006 -10007" universe="0" />
<surface boundary="reflective" coeffs="0.0" id="10000" type="x-plane" />
<surface boundary="reflective" coeffs="10.0" id="10001" type="x-plane" />
<surface boundary="reflective" coeffs="0.0" id="10002" type="y-plane" />
<surface boundary="reflective" coeffs="10.0" id="10003" type="y-plane" />
<surface boundary="reflective" coeffs="0.0" id="10004" type="z-plane" />
<surface coeffs="1.6667" id="10005" type="z-plane" />
<surface coeffs="3.3334" id="10006" type="z-plane" />
<surface boundary="reflective" coeffs="5.0" id="10007" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>../1d_mgxs.h5</cross_sections>
<material id="10000" name="1">
<density units="macro" value="1.0" />
<macroscopic name="uo2_iso" />
</material>
<material id="10001" name="2">
<density units="macro" value="1.0" />
<macroscopic name="clad_iso" />
</material>
<material id="10002" name="3">
<density units="macro" value="1.0" />
<macroscopic name="lwtr_iso" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
</eigenvalue>
<source strength="1.0">
<space type="box">
<parameters>0.0 0.0 0.0 10.0 10.0 5.0</parameters>
</space>
</source>
<energy_mode>multi-group</energy_mode>
<max_order>1</max_order>
</settings>

99
tests/test_mg_nuclide/inputs_true.dat
View file

@ -1 +1,98 @@
ec7f0697d22668dcc4cdaf134c58b9f84137730d52cb44264ee9205369abcf995b2f66847d620715cd609bd2f5f865294374978f8fb89f182962e40801171cba
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="10000" material="10000" region="10000 -10001 10002 -10003 10004 -10005" universe="0" />
<cell id="10001" material="10001" region="10000 -10001 10002 -10003 10005 -10006" universe="0" />
<cell id="10002" material="10002" region="10000 -10001 10002 -10003 10006 -10007" universe="0" />
<cell id="10003" material="10003" region="10000 -10001 10002 -10003 10007 -10008" universe="0" />
<cell id="10004" material="10004" region="10000 -10001 10002 -10003 10008 -10009" universe="0" />
<cell id="10005" material="10005" region="10000 -10001 10002 -10003 10009 -10010" universe="0" />
<cell id="10006" material="10006" region="10000 -10001 10002 -10003 10010 -10011" universe="0" />
<cell id="10007" material="10007" region="10000 -10001 10002 -10003 10011 -10012" universe="0" />
<cell id="10008" material="10008" region="10000 -10001 10002 -10003 10012 -10013" universe="0" />
<cell id="10009" material="10009" region="10000 -10001 10002 -10003 10013 -10014" universe="0" />
<cell id="10010" material="10010" region="10000 -10001 10002 -10003 10014 -10015" universe="0" />
<cell id="10011" material="10011" region="10000 -10001 10002 -10003 10015 -10016" universe="0" />
<surface boundary="reflective" coeffs="0.0" id="10000" type="x-plane" />
<surface boundary="reflective" coeffs="10.0" id="10001" type="x-plane" />
<surface boundary="reflective" coeffs="0.0" id="10002" type="y-plane" />
<surface boundary="reflective" coeffs="10.0" id="10003" type="y-plane" />
<surface boundary="reflective" coeffs="0.0" id="10004" type="z-plane" />
<surface coeffs="0.4167" id="10005" type="z-plane" />
<surface coeffs="0.8334" id="10006" type="z-plane" />
<surface coeffs="1.2501" id="10007" type="z-plane" />
<surface coeffs="1.6668" id="10008" type="z-plane" />
<surface coeffs="2.0835" id="10009" type="z-plane" />
<surface coeffs="2.5002" id="10010" type="z-plane" />
<surface coeffs="2.9169" id="10011" type="z-plane" />
<surface coeffs="3.3336" id="10012" type="z-plane" />
<surface coeffs="3.7503" id="10013" type="z-plane" />
<surface coeffs="4.167" id="10014" type="z-plane" />
<surface coeffs="4.5837" id="10015" type="z-plane" />
<surface boundary="reflective" coeffs="5.0" id="10016" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>../1d_mgxs.h5</cross_sections>
<material id="10000" name="1">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="uo2_ang" />
</material>
<material id="10001" name="2">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="uo2_ang_mu" />
</material>
<material id="10002" name="3">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="uo2_iso" />
</material>
<material id="10003" name="4">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="uo2_iso_mu" />
</material>
<material id="10004" name="5">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="clad_ang" />
</material>
<material id="10005" name="6">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="clad_ang_mu" />
</material>
<material id="10006" name="7">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="clad_iso" />
</material>
<material id="10007" name="8">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="clad_iso_mu" />
</material>
<material id="10008" name="9">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="lwtr_ang" />
</material>
<material id="10009" name="10">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="lwtr_ang_mu" />
</material>
<material id="10010" name="11">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="lwtr_iso" />
</material>
<material id="10011" name="12">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="lwtr_iso_mu" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
</eigenvalue>
<source strength="1.0">
<space type="box">
<parameters>0.0 0.0 0.0 10.0 10.0 5.0</parameters>
</space>
</source>
<energy_mode>multi-group</energy_mode>
</settings>

181
tests/test_mg_tallies/inputs_true.dat
View file

@ -1 +1,180 @@
8f9b2d1ba196fc0ad2e70647fb8691c5fc06b64b78f17414149a7fadfe63dd7e431830f73cb239e9c84f01e88896bf3f3d3cad1f57645bd63936dcc7db67e8a9
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="10000" material="10000" region="10000 -10001 10002 -10003 10004 -10005" universe="0" />
<cell id="10001" material="10001" region="10000 -10001 10002 -10003 10005 -10006" universe="0" />
<cell id="10002" material="10002" region="10000 -10001 10002 -10003 10006 -10007" universe="0" />
<cell id="10003" material="10003" region="10000 -10001 10002 -10003 10007 -10008" universe="0" />
<cell id="10004" material="10004" region="10000 -10001 10002 -10003 10008 -10009" universe="0" />
<cell id="10005" material="10005" region="10000 -10001 10002 -10003 10009 -10010" universe="0" />
<cell id="10006" material="10006" region="10000 -10001 10002 -10003 10010 -10011" universe="0" />
<cell id="10007" material="10007" region="10000 -10001 10002 -10003 10011 -10012" universe="0" />
<cell id="10008" material="10008" region="10000 -10001 10002 -10003 10012 -10013" universe="0" />
<cell id="10009" material="10009" region="10000 -10001 10002 -10003 10013 -10014" universe="0" />
<cell id="10010" material="10010" region="10000 -10001 10002 -10003 10014 -10015" universe="0" />
<cell id="10011" material="10011" region="10000 -10001 10002 -10003 10015 -10016" universe="0" />
<surface boundary="reflective" coeffs="0.0" id="10000" type="x-plane" />
<surface boundary="reflective" coeffs="10.0" id="10001" type="x-plane" />
<surface boundary="reflective" coeffs="0.0" id="10002" type="y-plane" />
<surface boundary="reflective" coeffs="10.0" id="10003" type="y-plane" />
<surface boundary="reflective" coeffs="0.0" id="10004" type="z-plane" />
<surface coeffs="0.4167" id="10005" type="z-plane" />
<surface coeffs="0.8334" id="10006" type="z-plane" />
<surface coeffs="1.2501" id="10007" type="z-plane" />
<surface coeffs="1.6668" id="10008" type="z-plane" />
<surface coeffs="2.0835" id="10009" type="z-plane" />
<surface coeffs="2.5002" id="10010" type="z-plane" />
<surface coeffs="2.9169" id="10011" type="z-plane" />
<surface coeffs="3.3336" id="10012" type="z-plane" />
<surface coeffs="3.7503" id="10013" type="z-plane" />
<surface coeffs="4.167" id="10014" type="z-plane" />
<surface coeffs="4.5837" id="10015" type="z-plane" />
<surface boundary="reflective" coeffs="5.0" id="10016" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>../1d_mgxs.h5</cross_sections>
<material id="10000" name="1">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="uo2_ang" />
</material>
<material id="10001" name="2">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="uo2_ang_mu" />
</material>
<material id="10002" name="3">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="uo2_iso" />
</material>
<material id="10003" name="4">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="uo2_iso_mu" />
</material>
<material id="10004" name="5">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="clad_ang" />
</material>
<material id="10005" name="6">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="clad_ang_mu" />
</material>
<material id="10006" name="7">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="clad_iso" />
</material>
<material id="10007" name="8">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="clad_iso_mu" />
</material>
<material id="10008" name="9">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="lwtr_ang" />
</material>
<material id="10009" name="10">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="lwtr_ang_mu" />
</material>
<material id="10010" name="11">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="lwtr_iso" />
</material>
<material id="10011" name="12">
<density units="atom/b-cm" value="1.0" />
<nuclide ao="1.0" name="lwtr_iso_mu" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
</eigenvalue>
<source strength="1.0">
<space type="box">
<parameters>0.0 0.0 0.0 10.0 10.0 5.0</parameters>
</space>
</source>
<energy_mode>multi-group</energy_mode>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1" type="regular">
<dimension>1 1 10</dimension>
<lower_left>0.0 0.0 0.0</lower_left>
<upper_right>10 10 5</upper_right>
</mesh>
<tally id="10000">
<filter bins="1" type="mesh" />
<scores>total absorption flux fission nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10001">
<filter bins="1" type="mesh" />
<scores>total absorption flux fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10002">
<filter bins="10000 10001 10002 10003 10004 10005 10006 10007 10008 10009 10010 10011" type="material" />
<filter bins="0.0 20000000.0" type="energy" />
<scores>total absorption flux fission nu-fission scatter nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10003">
<filter bins="10000 10001 10002 10003 10004 10005 10006 10007 10008 10009 10010 10011" type="material" />
<filter bins="0.0 20000000.0" type="energy" />
<scores>total absorption flux fission nu-fission</scores>
<estimator>collision</estimator>
</tally>
<tally id="10004">
<filter bins="10000 10001 10002 10003 10004 10005 10006 10007 10008 10009 10010 10011" type="material" />
<filter bins="0.0 20000000.0" type="energy" />
<scores>total absorption flux fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10005">
<filter bins="10000 10001 10002 10003 10004 10005 10006 10007 10008 10009 10010 10011" type="material" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<scores>scatter nu-scatter nu-fission</scores>
</tally>
<tally id="10006">
<filter bins="1" type="mesh" />
<nuclides>uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu</nuclides>
<scores>total absorption fission nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10007">
<filter bins="1" type="mesh" />
<nuclides>uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu</nuclides>
<scores>total absorption fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10008">
<filter bins="10000 10001 10002 10003 10004 10005 10006 10007 10008 10009 10010 10011" type="material" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu</nuclides>
<scores>total absorption fission nu-fission scatter nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10009">
<filter bins="10000 10001 10002 10003 10004 10005 10006 10007 10008 10009 10010 10011" type="material" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu</nuclides>
<scores>total absorption fission nu-fission</scores>
<estimator>collision</estimator>
</tally>
<tally id="10010">
<filter bins="10000 10001 10002 10003 10004 10005 10006 10007 10008 10009 10010 10011" type="material" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu</nuclides>
<scores>total absorption fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10011">
<filter bins="10000 10001 10002 10003 10004 10005 10006 10007 10008 10009 10010 10011" type="material" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu</nuclides>
<scores>scatter nu-scatter nu-fission</scores>
</tally>
</tallies>

7
tests/test_mg_tallies/test_mg_tallies.py
View file

@ -82,12 +82,7 @@ class MGTalliesTestHarness(HashedPyAPITestHarness):
self._input_set.export()
def _cleanup(self):
super(MGTalliesTestHarness, self)._cleanup()
f = os.path.join(os.getcwd(), 'tallies.xml')
if os.path.exists(f): os.remove(f)
if __name__ == '__main__':
harness = MGTalliesTestHarness('statepoint.10.*', True, mg=True)
harness = MGTalliesTestHarness('statepoint.10.h5', True, mg=True)
harness.main()

277
tests/test_mgxs_library_ce_to_mg/inputs_true.dat
View file

@ -1 +1,276 @@
74f306b40647c6d7125af404234bbd6883ae88a446b00f828fcda9adc8bca5167b544b23d083c802e2c0630f7fcec9052e31bced490cc94b3e3193512359cb96
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="10000" material="10000" name="cell 1" region="-10000" universe="0" />
<cell id="10001" material="10001" name="cell 3" region="10000 -10001" universe="0" />
<cell id="10002" material="10002" name="cell 2" region="10001 10002 -10003 10004 -10005" universe="0" />
<surface coeffs="0 0 0.39218" id="10000" name="Fuel OR" type="z-cylinder" />
<surface coeffs="0 0 0.4572" id="10001" name="Clad OR" type="z-cylinder" />
<surface boundary="reflective" coeffs="-0.63" id="10002" name="left" type="x-plane" />
<surface boundary="reflective" coeffs="0.63" id="10003" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-0.63" id="10004" name="bottom" type="y-plane" />
<surface boundary="reflective" coeffs="0.63" id="10005" name="top" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="10000" name="Fuel">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />
<nuclide ao="0.022408" name="U238" />
<nuclide ao="0.045829" name="O16" />
</material>
<material id="10001" name="Cladding">
<density units="g/cm3" value="6.55" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
<nuclide ao="0.0072758" name="Zr92" />
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="10002" name="Hot borated water">
<density units="g/cm3" value="0.740582" />
<nuclide ao="0.049457" name="H1" />
<nuclide ao="0.024672" name="O16" />
<nuclide ao="8.0042e-06" name="B10" />
<nuclide ao="3.2218e-05" name="B11" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
</eigenvalue>
<source strength="1.0">
<space type="fission">
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<tally id="10000">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10001">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10002">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10003">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10004">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10005">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10006">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10007">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10008">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10009">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10010">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10011">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10012">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10013">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10014">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10015">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10016">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10017">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10018">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10019">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10020">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10021">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10022">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10023">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10024">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10025">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10026">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10027">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10028">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10029">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
</tallies>

1168
tests/test_mgxs_library_condense/inputs_true.dat
View file

File diff suppressed because it is too large Load diff

6
tests/test_mgxs_library_condense/test_mgxs_library_condense.py
View file

@ -71,12 +71,6 @@ class MGXSTestHarness(PyAPITestHarness):
return outstr
def _cleanup(self):
super(MGXSTestHarness, self)._cleanup()
f = os.path.join(os.getcwd(), 'tallies.xml')
if os.path.exists(f): os.remove(f)
if __name__ == '__main__':
harness = MGXSTestHarness('statepoint.10.*', True)
harness.main()

453
tests/test_mgxs_library_distribcell/inputs_true.dat
View file

@ -1 +1,452 @@
df187239f7481867cc09138709da90bc28eeb647b4bcbb08b894e7fdf6ff45510341b77e34754c2358f0e0665f8e552bb1eafed8c42cd2c50595b60366320ce4
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="10000" material="10000" name="fuel" region="-10000" universe="10000" />
<cell id="10001" material="10001" name="clad" region="10000 -10001" universe="10000" />
<cell id="10002" material="10002" name="hot water" region="10001" universe="10000" />
<cell id="10003" material="10002" name="guide tube inner water" region="-10000" universe="10001" />
<cell id="10004" material="10001" name="guide tube clad" region="10000 -10001" universe="10001" />
<cell id="10005" material="10002" name="guide tube outer water" region="10001" universe="10001" />
<cell fill="10002" id="10006" name="root cell" region="10002 -10003 10004 -10005" universe="0" />
<lattice id="10002" name="Fuel Assembly">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000
10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000
10000 10000 10000 10000 10000 10001 10000 10000 10001 10000 10000 10001 10000 10000 10000 10000 10000
10000 10000 10000 10001 10000 10000 10000 10000 10000 10000 10000 10000 10000 10001 10000 10000 10000
10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000
10000 10000 10001 10000 10000 10001 10000 10000 10001 10000 10000 10001 10000 10000 10001 10000 10000
10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000
10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000
10000 10000 10001 10000 10000 10001 10000 10000 10001 10000 10000 10001 10000 10000 10001 10000 10000
10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000
10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000
10000 10000 10001 10000 10000 10001 10000 10000 10001 10000 10000 10001 10000 10000 10001 10000 10000
10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000
10000 10000 10000 10001 10000 10000 10000 10000 10000 10000 10000 10000 10000 10001 10000 10000 10000
10000 10000 10000 10000 10000 10001 10000 10000 10001 10000 10000 10001 10000 10000 10000 10000 10000
10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000
10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 </universes>
</lattice>
<surface coeffs="0 0 0.39218" id="10000" name="Fuel OR" type="z-cylinder" />
<surface coeffs="0 0 0.4572" id="10001" name="Clad OR" type="z-cylinder" />
<surface boundary="reflective" coeffs="-10.71" id="10002" type="x-plane" />
<surface boundary="reflective" coeffs="10.71" id="10003" type="x-plane" />
<surface boundary="reflective" coeffs="-10.71" id="10004" type="y-plane" />
<surface boundary="reflective" coeffs="10.71" id="10005" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="10000" name="Fuel">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />
<nuclide ao="0.022408" name="U238" />
<nuclide ao="0.045829" name="O16" />
</material>
<material id="10001" name="Cladding">
<density units="g/cm3" value="6.55" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
<nuclide ao="0.0072758" name="Zr92" />
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="10002" name="Hot borated water">
<density units="g/cm3" value="0.740582" />
<nuclide ao="0.049457" name="H1" />
<nuclide ao="0.024672" name="O16" />
<nuclide ao="8.0042e-06" name="B10" />
<nuclide ao="3.2218e-05" name="B11" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
</eigenvalue>
<source strength="1.0">
<space type="fission">
<parameters>-10.71 -10.71 -1 10.71 10.71 1</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<tally id="10000">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10001">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10002">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10003">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>analog</estimator>
</tally>
<tally id="10004">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>scatter-1</scores>
<estimator>analog</estimator>
</tally>
<tally id="10005">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10006">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>analog</estimator>
</tally>
<tally id="10007">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-scatter-1</scores>
<estimator>analog</estimator>
</tally>
<tally id="10008">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10009">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10010">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10011">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10012">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10013">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10014">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10015">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10016">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10017">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10018">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>kappa-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10019">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10020">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10021">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10022">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10023">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10024">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10025">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10026">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10027">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10028">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10029">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10030">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10031">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10032">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10033">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10034">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10035">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10036">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>inverse-velocity</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10037">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10038">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10039">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10040">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10041">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10042">
<filter bins="10000" type="distribcell" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10043">
<filter bins="10000" type="distribcell" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10044">
<filter bins="10000" type="distribcell" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10045">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10046">
<filter bins="10000" type="distribcell" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10047">
<filter bins="10000" type="distribcell" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10048">
<filter bins="10000" type="distribcell" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>decay-rate</scores>
<estimator>analog</estimator>
</tally>
<tally id="10049">
<filter bins="10000" type="distribcell" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10050">
<filter bins="10000" type="distribcell" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
</tallies>

7
tests/test_mgxs_library_distribcell/test_mgxs_library_distribcell.py
View file

@ -72,12 +72,7 @@ class MGXSTestHarness(PyAPITestHarness):
return outstr
def _cleanup(self):
super(MGXSTestHarness, self)._cleanup()
f = os.path.join(os.getcwd(), 'tallies.xml')
if os.path.exists(f): os.remove(f)
if __name__ == '__main__':
harness = MGXSTestHarness('statepoint.10.*', True)
harness = MGXSTestHarness('statepoint.10.h5', True)
harness.main()

1168
tests/test_mgxs_library_hdf5/inputs_true.dat
View file

File diff suppressed because it is too large Load diff

690
tests/test_mgxs_library_mesh/inputs_true.dat
View file

@ -1 +1,689 @@
03d894a7995ac40f7971b17349b460f4b563cb1c94abaa7e7241e6f7edad7f0cb80d3f80829db14ea6b7d70d18197cb15e308047cd10f699d834178eeb6396be
<?xml version='1.0' encoding='utf-8'?>
<geometry>
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<cell id="24" material="3" region="-3" universe="2" />
<cell id="25" material="2" region="3 -4" universe="2" />
<cell id="26" material="3" region="4" universe="2" />
<cell id="27" material="1" region="-1" universe="3" />
<cell id="28" material="2" region="1 -2" universe="3" />
<cell id="29" material="4" region="2" universe="3" />
<cell id="3" material="8" region="-7 31 -32" universe="0" />
<cell id="30" material="4" region="-3" universe="4" />
<cell id="31" material="2" region="3 -4" universe="4" />
<cell id="32" material="4" region="4" universe="4" />
<cell id="4" material="9" region="-5 32 -33" universe="0" />
<cell id="5" material="12" region="-5 33 -34" universe="0" />
<cell id="50" material="3" region="34 -35" universe="5" />
<cell id="6" material="11" region="-5 36 -37" universe="0" />
<cell fill="100" id="60" region="34 -35" universe="6" />
<cell id="7" material="10" region="-5 37 -38" universe="0" />
<cell id="70" material="4" region="35 -36" universe="7" />
<cell id="8" material="7" region="-7 38 -39" universe="0" />
<cell fill="101" id="80" region="35 -36" universe="8" />
<cell id="9" material="9" region="6 -7 32 -38" universe="0" />
<lattice id="100" name="Fuel assembly (lower half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 </universes>
</lattice>
<lattice id="101" name="Fuel assembly (upper half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 </universes>
</lattice>
<lattice id="200" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
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5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
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5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 </universes>
</lattice>
<lattice id="201" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
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7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 </universes>
</lattice>
<surface coeffs="0.0 0.0 0.41" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.475" id="2" type="z-cylinder" />
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<surface boundary="vacuum" coeffs="223.0" id="39" type="z-plane" />
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<surface coeffs="0.0 0.0 187.6" id="5" type="z-cylinder" />
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</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="Fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
<nuclide ao="0.021504" name="U238" />
<nuclide ao="1.0801e-08" name="Xe135" />
<nuclide ao="0.045737" name="O16" />
</material>
<material id="10" name="Top nozzle region">
<density units="g/cm3" value="1.746" />
<nuclide name="H1" wo="0.035887" />
<nuclide name="O16" wo="0.2847761" />
<nuclide name="B10" wo="0.000115699" />
<nuclide name="B11" wo="0.000527075" />
<nuclide name="Fe54" wo="0.02644016154" />
<nuclide name="Fe56" wo="0.43037146399" />
<nuclide name="Fe57" wo="0.0101152584" />
<nuclide name="Fe58" wo="0.00137211607" />
<nuclide name="Ni58" wo="0.04104621835" />
<nuclide name="Mn55" wo="0.0135739" />
<nuclide name="Cr52" wo="0.107931450781" />
<sab name="c_H_in_H2O" />
</material>
<material id="11" name="Top of fuel assemblies">
<density units="g/cm3" value="3.044" />
<nuclide name="H1" wo="0.0162913" />
<nuclide name="O16" wo="0.1292776" />
<nuclide name="B10" wo="5.25228e-05" />
<nuclide name="B11" wo="0.000239272" />
<nuclide name="Zr90" wo="0.43313403903" />
<nuclide name="Zr91" wo="0.09549277374" />
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" />
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
<nuclide name="H1" wo="0.0292856" />
<nuclide name="O16" wo="0.2323919" />
<nuclide name="B10" wo="9.44159e-05" />
<nuclide name="B11" wo="0.00043012" />
<nuclide name="Zr90" wo="0.3741373658" />
<nuclide name="Zr91" wo="0.0824858164" />
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" />
</material>
<material id="2" name="Cladding">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="Cold borated water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
<nuclide name="Fe54" wo="0.05437098" />
<nuclide name="Fe56" wo="0.88500663" />
<nuclide name="Fe57" wo="0.0208008" />
<nuclide name="Fe58" wo="0.00282159" />
<nuclide name="Ni58" wo="0.0067198" />
<nuclide name="Ni60" wo="0.0026776" />
<nuclide name="Mn55" wo="0.01" />
<nuclide name="Cr52" wo="0.002092475" />
<nuclide name="C0" wo="0.0025" />
<nuclide name="Cu63" wo="0.0013696" />
</material>
<material id="6" name="Lower radial reflector">
<density units="g/cm3" value="4.32" />
<nuclide name="H1" wo="0.0095661" />
<nuclide name="O16" wo="0.0759107" />
<nuclide name="B10" wo="3.08409e-05" />
<nuclide name="B11" wo="0.000140499" />
<nuclide name="Fe54" wo="0.035620772088" />
<nuclide name="Fe56" wo="0.579805982228" />
<nuclide name="Fe57" wo="0.01362750048" />
<nuclide name="Fe58" wo="0.001848545204" />
<nuclide name="Ni58" wo="0.055298376566" />
<nuclide name="Mn55" wo="0.018287" />
<nuclide name="Cr52" wo="0.145407678031" />
<sab name="c_H_in_H2O" />
</material>
<material id="7" name="Upper radial reflector /Top plate region">
<density units="g/cm3" value="4.28" />
<nuclide name="H1" wo="0.0086117" />
<nuclide name="O16" wo="0.0683369" />
<nuclide name="B10" wo="2.77638e-05" />
<nuclide name="B11" wo="0.000126481" />
<nuclide name="Fe54" wo="0.035953677186" />
<nuclide name="Fe56" wo="0.585224740891" />
<nuclide name="Fe57" wo="0.01375486056" />
<nuclide name="Fe58" wo="0.001865821363" />
<nuclide name="Ni58" wo="0.055815129186" />
<nuclide name="Mn55" wo="0.0184579" />
<nuclide name="Cr52" wo="0.146766614995" />
<sab name="c_H_in_H2O" />
</material>
<material id="8" name="Bottom plate region">
<density units="g/cm3" value="7.184" />
<nuclide name="H1" wo="0.0011505" />
<nuclide name="O16" wo="0.0091296" />
<nuclide name="B10" wo="3.70915e-06" />
<nuclide name="B11" wo="1.68974e-05" />
<nuclide name="Fe54" wo="0.03855611055" />
<nuclide name="Fe56" wo="0.627585036425" />
<nuclide name="Fe57" wo="0.014750478" />
<nuclide name="Fe58" wo="0.002000875025" />
<nuclide name="Ni58" wo="0.059855207342" />
<nuclide name="Mn55" wo="0.019794" />
<nuclide name="Cr52" wo="0.157390026871" />
<sab name="c_H_in_H2O" />
</material>
<material id="9" name="Bottom nozzle region">
<density units="g/cm3" value="2.53" />
<nuclide name="H1" wo="0.0245014" />
<nuclide name="O16" wo="0.1944274" />
<nuclide name="B10" wo="7.89917e-05" />
<nuclide name="B11" wo="0.000359854" />
<nuclide name="Fe54" wo="0.030411411144" />
<nuclide name="Fe56" wo="0.495012237964" />
<nuclide name="Fe57" wo="0.01163454624" />
<nuclide name="Fe58" wo="0.001578204652" />
<nuclide name="Ni58" wo="0.047211231662" />
<nuclide name="Mn55" wo="0.0156126" />
<nuclide name="Cr52" wo="0.124142524198" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
</eigenvalue>
<source strength="1.0">
<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1" type="regular">
<dimension>2 2</dimension>
<lower_left>-100.0 -100.0</lower_left>
<width>100.0 100.0</width>
</mesh>
<tally id="10000">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10001">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10002">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10003">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>analog</estimator>
</tally>
<tally id="10004">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>scatter-1</scores>
<estimator>analog</estimator>
</tally>
<tally id="10005">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10006">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>analog</estimator>
</tally>
<tally id="10007">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-scatter-1</scores>
<estimator>analog</estimator>
</tally>
<tally id="10008">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10009">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10010">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10011">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10012">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10013">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10014">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10015">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10016">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10017">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10018">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>kappa-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10019">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10020">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10021">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10022">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10023">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10024">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10025">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10026">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10027">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10028">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10029">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10030">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10031">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10032">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10033">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10034">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10035">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10036">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>inverse-velocity</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10037">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10038">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10039">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10040">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10041">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10042">
<filter bins="1" type="mesh" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10043">
<filter bins="1" type="mesh" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10044">
<filter bins="1" type="mesh" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10045">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10046">
<filter bins="1" type="mesh" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10047">
<filter bins="1" type="mesh" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10048">
<filter bins="1" type="mesh" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>decay-rate</scores>
<estimator>analog</estimator>
</tally>
<tally id="10049">
<filter bins="1" type="mesh" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10050">
<filter bins="1" type="mesh" />
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<filter bins="0.0 20000000.0" type="energy" />
<filter bins="0.0 20000000.0" type="energyout" />
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
</tallies>

7
tests/test_mgxs_library_mesh/test_mgxs_library_mesh.py
View file

@ -72,12 +72,7 @@ class MGXSTestHarness(PyAPITestHarness):
return outstr
def _cleanup(self):
super(MGXSTestHarness, self)._cleanup()
f = os.path.join(os.getcwd(), 'tallies.xml')
if os.path.exists(f): os.remove(f)
if __name__ == '__main__':
harness = MGXSTestHarness('statepoint.10.*', True)
harness = MGXSTestHarness('statepoint.10.h5', True)
harness.main()

1168
tests/test_mgxs_library_no_nuclides/inputs_true.dat
View file

File diff suppressed because it is too large Load diff

8
tests/test_mgxs_library_no_nuclides/test_mgxs_library_no_nuclides.py
View file

@ -67,12 +67,6 @@ class MGXSTestHarness(PyAPITestHarness):
return outstr
def _cleanup(self):
super(MGXSTestHarness, self)._cleanup()
f = os.path.join(os.getcwd(), 'tallies.xml')
if os.path.exists(f): os.remove(f)
if __name__ == '__main__':
harness = MGXSTestHarness('statepoint.10.*', True)
harness = MGXSTestHarness('statepoint.10.h5', True)
harness.main()

934
tests/test_mgxs_library_nuclides/inputs_true.dat
View file

@ -1 +1,933 @@
eed0190893105747f0146472dfea86ca58b9fc2e8d039961d9fef8f235f79da32215f9b59b840419e6b69c5a04544b4659f2634b63e3a76b6b0f8c75d05e416c
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="10000" material="10000" name="cell 1" region="-10000" universe="0" />
<cell id="10001" material="10001" name="cell 3" region="10000 -10001" universe="0" />
<cell id="10002" material="10002" name="cell 2" region="10001 10002 -10003 10004 -10005" universe="0" />
<surface coeffs="0 0 0.39218" id="10000" name="Fuel OR" type="z-cylinder" />
<surface coeffs="0 0 0.4572" id="10001" name="Clad OR" type="z-cylinder" />
<surface boundary="reflective" coeffs="-0.63" id="10002" name="left" type="x-plane" />
<surface boundary="reflective" coeffs="0.63" id="10003" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-0.63" id="10004" name="bottom" type="y-plane" />
<surface boundary="reflective" coeffs="0.63" id="10005" name="top" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="10000" name="Fuel">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />
<nuclide ao="0.022408" name="U238" />
<nuclide ao="0.045829" name="O16" />
</material>
<material id="10001" name="Cladding">
<density units="g/cm3" value="6.55" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
<nuclide ao="0.0072758" name="Zr92" />
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="10002" name="Hot borated water">
<density units="g/cm3" value="0.740582" />
<nuclide ao="0.049457" name="H1" />
<nuclide ao="0.024672" name="O16" />
<nuclide ao="8.0042e-06" name="B10" />
<nuclide ao="3.2218e-05" name="B11" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
</eigenvalue>
<source strength="1.0">
<space type="fission">
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<tally id="10000">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10001">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10002">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10003">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>total</scores>
<estimator>analog</estimator>
</tally>
<tally id="10004">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>scatter-1</scores>
<estimator>analog</estimator>
</tally>
<tally id="10005">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10006">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>total</scores>
<estimator>analog</estimator>
</tally>
<tally id="10007">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>nu-scatter-1</scores>
<estimator>analog</estimator>
</tally>
<tally id="10008">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10009">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10010">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10011">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10012">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10013">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10014">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10015">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10016">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10017">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10018">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>kappa-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10019">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10020">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10021">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10022">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10023">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10024">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10025">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10026">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>nu-scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10027">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10028">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10029">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10030">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10031">
<filter bins="10000" type="material" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10032">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10033">
<filter bins="10000" type="material" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10034">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10035">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10036">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>inverse-velocity</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10037">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10038">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10039">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10040">
<filter bins="10000" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>U234 U235 U238 O16</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10041">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10042">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10043">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10044">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>total</scores>
<estimator>analog</estimator>
</tally>
<tally id="10045">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>scatter-1</scores>
<estimator>analog</estimator>
</tally>
<tally id="10046">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10047">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>total</scores>
<estimator>analog</estimator>
</tally>
<tally id="10048">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>nu-scatter-1</scores>
<estimator>analog</estimator>
</tally>
<tally id="10049">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10050">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10051">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10052">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10053">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10054">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10055">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10056">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10057">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10058">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10059">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>kappa-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10060">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10061">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10062">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10063">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10064">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10065">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10066">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10067">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>nu-scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10068">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10069">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10070">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10071">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10072">
<filter bins="10001" type="material" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10073">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10074">
<filter bins="10001" type="material" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10075">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10076">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10077">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>inverse-velocity</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10078">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10079">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10080">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10081">
<filter bins="10001" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>Zr90 Zr91 Zr92 Zr94 Zr96</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10082">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10083">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10084">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10085">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>total</scores>
<estimator>analog</estimator>
</tally>
<tally id="10086">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>scatter-1</scores>
<estimator>analog</estimator>
</tally>
<tally id="10087">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10088">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>total</scores>
<estimator>analog</estimator>
</tally>
<tally id="10089">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>nu-scatter-1</scores>
<estimator>analog</estimator>
</tally>
<tally id="10090">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10091">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10092">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10093">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10094">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10095">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10096">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10097">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10098">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10099">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10100">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>kappa-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10101">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10102">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10103">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10104">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10105">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10106">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10107">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10108">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>nu-scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10109">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10110">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10111">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10112">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10113">
<filter bins="10002" type="material" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10114">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10115">
<filter bins="10002" type="material" />
<filter bins="0.0 20000000.0" type="energy" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10116">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10117">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10118">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>inverse-velocity</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10119">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10120">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10121">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10122">
<filter bins="10002" type="material" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<filter bins="0.0 0.625 20000000.0" type="energyout" />
<nuclides>H1 O16 B10 B11</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
</tallies>

8
tests/test_mgxs_library_nuclides/test_mgxs_library_nuclides.py
View file

@ -64,12 +64,6 @@ class MGXSTestHarness(PyAPITestHarness):
return outstr
def _cleanup(self):
super(MGXSTestHarness, self)._cleanup()
f = os.path.join(os.getcwd(), 'tallies.xml')
if os.path.exists(f): os.remove(f)
if __name__ == '__main__':
harness = MGXSTestHarness('statepoint.10.*', True)
harness = MGXSTestHarness('statepoint.10.h5', True)
harness.main()

66
tests/test_multipole/inputs_true.dat
View file

@ -1 +1,65 @@
2be927608035759f52a2ac88b2c84e28c06e0f7905187bfd4695fecd80f417e727d8879c52fe03253938f7aa0301061f72dce9b5ae46b8675049b5bc4d9525a0
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" universe="1" />
<cell fill="101" id="101" region="10001 -10002 10003 -10004" universe="0" />
<cell id="11" material="2" region="-10000" temperature="500 0 700 800" universe="11" />
<cell id="12" material="1" region="10000" universe="11" />
<lattice id="101">
<pitch>2.0 2.0</pitch>
<outer>1</outer>
<dimension>2 2</dimension>
<lower_left>-2.0 -2.0</lower_left>
<universes>
11 11
11 11 </universes>
</lattice>
<surface coeffs="0.0 0.0 0.3" id="10000" type="z-cylinder" />
<surface boundary="reflective" coeffs="-3.0" id="10001" type="x-plane" />
<surface boundary="reflective" coeffs="3.0" id="10002" type="x-plane" />
<surface boundary="reflective" coeffs="-3.0" id="10003" type="y-plane" />
<surface boundary="reflective" coeffs="3.0" id="10004" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1">
<density units="g/cc" value="1.0" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<sab name="c_H_in_H2O" />
</material>
<material id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>1000</particles>
<batches>5</batches>
<inactive>0</inactive>
</eigenvalue>
<source strength="1.0">
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
</source>
<output>
<summary>true</summary>
</output>
<temperature_multipole>True</temperature_multipole>
<temperature_tolerance>1000</temperature_tolerance>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<plots>
<plot basis="xy" color="cell" filename="cellplot" id="1" type="slice">
<origin>0 0 0</origin>
<width>7 7</width>
<pixels>400 400</pixels>
</plot>
<plot basis="xy" color="mat" filename="matplot" id="2" type="slice">
<origin>0 0 0</origin>
<width>7 7</width>
<pixels>400 400</pixels>
</plot>
</plots>

39
tests/test_periodic/inputs_true.dat
View file

@ -1 +1,38 @@
259ea7c22920ddea0bc076ee77d35e76f36d2c7043cb8d036b182a11fd7d0f6524e3cbd9c6b0bf4a1af905ebe10b765d3d43e43e899d3edbb601baf6fd172365
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="1 -2 3 -4 5 -6 7" universe="0" />
<cell id="2" material="2" region="5 -6 -7" universe="0" />
<surface boundary="periodic" coeffs="-5.0" id="1" periodic_surface_id="2" type="x-plane" />
<surface boundary="periodic" coeffs="5.0" id="2" periodic_surface_id="1" type="x-plane" />
<surface boundary="periodic" coeffs="-5.0" id="3" type="y-plane" />
<surface boundary="periodic" coeffs="5.0" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="-5.0" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="5.0" id="6" type="z-plane" />
<surface coeffs="-2.5 2.5 2.0" id="7" type="z-cylinder" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1">
<density units="g/cc" value="1.0" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<sab name="c_H_in_H2O" />
</material>
<material id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>1000</particles>
<batches>4</batches>
<inactive>0</inactive>
</eigenvalue>
<source strength="1.0">
<space type="box">
<parameters>-5.0 -5.0 -5.0 5.0 5.0 5.0</parameters>
</space>
</source>
</settings>

14
tests/test_periodic/tallies.xml
View file

@ -1,14 +0,0 @@
<?xml version="1.0"?>
<tallies>
<mesh id="1">
<type>regular</type>
<lower_left>-200. -1e50</lower_left>
<upper_right>200. 1e50</upper_right>
<dimension>50 1</dimension>
</mesh>
<tally id="1">
<estimator>collision</estimator>
<filter type="mesh" bins="1" />
<scores>fission</scores>
</tally>
</tallies>

49
tests/test_resonance_scattering/inputs_true.dat
View file

@ -1 +1,48 @@
13dde9c81e70ffdbb94f2ef47b64a63d5af0557424748cd224104bc0e1ca3c1078c0c8968ff29953d61dd8ddd8f90905ab945470d296faba18a99bd9ad278af2
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="-10000" universe="0" />
<surface boundary="reflective" coeffs="100" id="10000" type="x-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1">
<density units="g/cc" value="1.0" />
<nuclide ao="1.0" name="U238" />
<nuclide ao="0.02" name="U235" />
<nuclide ao="0.02" name="Pu239" />
<nuclide ao="20.0" name="H1" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
</eigenvalue>
<source strength="1.0">
<space type="box">
<parameters>-4 -4 -4 4 4 4</parameters>
</space>
</source>
<resonance_scattering>
<scatterer>
<nuclide>U238</nuclide>
<method>DBRC</method>
<E_min>1.0</E_min>
<E_max>210.0</E_max>
</scatterer>
<scatterer>
<nuclide>U235</nuclide>
<method>WCM</method>
<E_min>1.0</E_min>
<E_max>210.0</E_max>
</scatterer>
<scatterer>
<nuclide>Pu239</nuclide>
<method>ARES</method>
<E_min>1.0</E_min>
<E_max>210.0</E_max>
</scatterer>
</resonance_scattering>
</settings>

56
tests/test_source/inputs_true.dat
View file

@ -1 +1,55 @@
d9298c0829bc671a41883023a12caee5cb17eb863f30898f48b60212f646ac8869bd55b66f4dd0157daa053b31b7e6f4f393ed98162952f243565b70a19c249f
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" region="-1" universe="0" />
<surface boundary="vacuum" coeffs="0.0 0.0 0.0 10.0" id="1" type="sphere" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1">
<temperature>294</temperature>
<density units="g/cm3" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
</eigenvalue>
<source strength="0.5">
<space type="cartesian">
<x parameters="-3.0 3.0" type="uniform" />
<y type="discrete">
<parameters>-4.0 -1.0 3.0 0.2 0.3 0.5</parameters>
</y>
<z interpolation="linear-linear" type="tabular">
<parameters>-2.0 0.0 2.0 0.2 0.3 0.2</parameters>
</z>
</space>
<angle reference_uvw="0.0 0.0 1.0" type="mu-phi">
<mu type="discrete">
<parameters>-1.0 0.0 1.0 0.5 0.25 0.25</parameters>
</mu>
<phi parameters="0.0 6.28318530718" type="uniform" />
</angle>
<energy parameters="1289500.0" type="maxwell" />
</source>
<source strength="0.3">
<space type="box">
<parameters>-4.0 -4.0 -4.0 4.0 4.0 4.0</parameters>
</space>
<angle reference_uvw="0.0 1.0 0.0" type="monodirectional" />
<energy parameters="988000.0 2.249e-06" type="watt" />
</source>
<source strength="0.2">
<space type="point">
<parameters>1.2 -2.3 0.781</parameters>
</space>
<angle type="isotropic" />
<energy interpolation="histogram" type="tabular">
<parameters>1.0 1.38949549437 1.93069772888 2.68269579528 3.72759372031 5.17947467923 7.19685673001 10.0 13.8949549437 19.3069772888 26.8269579528 37.2759372031 51.7947467923 71.9685673001 100.0 138.949549437 193.069772888 268.269579528 372.759372031 517.947467923 719.685673001 1000.0 1389.49549437 1930.69772888 2682.69579528 3727.59372031 5179.47467923 7196.85673001 10000.0 13894.9549437 19306.9772888 26826.9579528 37275.9372031 51794.7467923 71968.5673001 100000.0 138949.549437 193069.772888 268269.579528 372759.372031 517947.467923 719685.673001 1000000.0 1389495.49437 1930697.72888 2682695.79528 3727593.72031 5179474.67923 7196856.73001 10000000.0 0.0 2.90864392994e-08 5.80533561806e-08 8.67817193689e-08 1.15153477858e-07 1.43052046006e-07 1.70362782612e-07 1.96973462002e-07 2.22774735186e-07 2.47660579198e-07 2.71528732767e-07 2.9428111653e-07 3.15824236062e-07 3.36069566065e-07 3.54933914133e-07 3.72339762616e-07 3.88215587147e-07 4.02496150558e-07 4.15122770952e-07 4.26043562837e-07 4.35213650335e-07 4.42595351592e-07 4.48158333612e-07 4.5187973691e-07 4.53744269441e-07 4.53744269441e-07 4.5187973691e-07 4.48158333612e-07 4.42595351592e-07 4.35213650335e-07 4.26043562837e-07 4.15122770952e-07 4.02496150558e-07 3.88215587147e-07 3.72339762616e-07 3.54933914133e-07 3.36069566065e-07 3.15824236062e-07 2.9428111653e-07 2.71528732767e-07 2.47660579198e-07 2.22774735186e-07 1.96973462002e-07 1.70362782612e-07 1.43052046006e-07 1.15153477858e-07 8.67817193689e-08 5.80533561806e-08 2.90864392994e-08 5.55962111528e-23</parameters>
</energy>
</source>
</settings>

8
tests/test_sourcepoint_interval/geometry.xml
View file

@ -1,8 +0,0 @@
<?xml version="1.0"?>
<geometry>
<!-- Sphere with radius 10 -->
<surface id="1" type="sphere" coeffs="0 0 0 10" boundary="vacuum"/>
<cell id="1" material="1" region="-1" />
</geometry>

9
tests/test_sourcepoint_interval/materials.xml
View file

@ -1,9 +0,0 @@
<?xml version="1.0"?>
<materials>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

3
tests/test_sourcepoint_interval/results_true.dat
View file

@ -1,3 +0,0 @@
k-combined:
0.000000E+00 0.000000E+00
1.892327E+00 -3.385257E+00 6.702634E-01

19
tests/test_sourcepoint_interval/settings.xml
View file

@ -1,19 +0,0 @@
<?xml version="1.0"?>
<settings>
<state_point interval="2"/>
<source_point interval="4"/>
<eigenvalue>
<batches>10</batches>
<inactive>5</inactive>
<particles>1000</particles>
</eigenvalue>
<source>
<space type="box">
<parameters>-4 -4 -4 4 4 4</parameters>
</space>
</source>
</settings>

38
tests/test_sourcepoint_interval/test_sourcepoint_interval.py
View file

@ -1,38 +0,0 @@
#!/usr/bin/env python
import glob
import os
import sys
sys.path.insert(0, os.pardir)
from testing_harness import TestHarness
from openmc.statepoint import StatePoint
class SourcepointTestHarness(TestHarness):
def _test_output_created(self):
"""Make sure statepoint.* files have been created."""
statepoint = glob.glob(os.path.join(os.getcwd(), 'statepoint.*'))
assert len(statepoint) == 5, '5 statepoint files must exist.'
assert statepoint[0].endswith('h5'), \
'Statepoint file is not a HDF5 file.'
def _get_results(self):
"""Digest info in the statepoint and return as a string."""
# Read the statepoint file.
statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0]
sp = StatePoint(statepoint)
# Get the eigenvalue information.
outstr = TestHarness._get_results(self)
# Add the source information.
xyz = sp.source[0]['xyz']
outstr += ' '.join(['{0:12.6E}'.format(x) for x in xyz])
outstr += "\n"
return outstr
if __name__ == '__main__':
harness = SourcepointTestHarness('statepoint.08.*')
harness.main()

8
tests/test_statepoint_interval/geometry.xml
View file

@ -1,8 +0,0 @@
<?xml version="1.0"?>
<geometry>
<!-- Sphere with radius 10 -->
<surface id="1" type="sphere" coeffs="0 0 0 10" boundary="vacuum"/>
<cell id="1" material="1" region="-1" />
</geometry>

9
tests/test_statepoint_interval/materials.xml
View file

@ -1,9 +0,0 @@
<?xml version="1.0"?>
<materials>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

2
tests/test_statepoint_interval/results_true.dat
View file

@ -1,2 +0,0 @@
k-combined:
2.943619E-01 3.309635E-03

18
tests/test_statepoint_interval/settings.xml
View file

@ -1,18 +0,0 @@
<?xml version="1.0"?>
<settings>
<state_point interval="2" />
<eigenvalue>
<batches>10</batches>
<inactive>5</inactive>
<particles>1000</particles>
</eigenvalue>
<source>
<space type="box">
<parameters>-4 -4 -4 4 4 4</parameters>
</space>
</source>
</settings>

24
tests/test_statepoint_interval/test_statepoint_interval.py
View file

@ -1,24 +0,0 @@
#!/usr/bin/env python
import os
import sys
sys.path.insert(0, os.pardir)
from testing_harness import TestHarness
class StatepointTestHarness(TestHarness):
def __init__(self):
super(StatepointTestHarness, self).__init__(None, False)
def _test_output_created(self):
"""Make sure statepoint files have been created."""
sps = ('statepoint.02.*', 'statepoint.04.*', 'statepoint.06.*',
'statepoint.08.*', 'statepoint.10.*')
for sp in sps:
self._sp_name = sp
TestHarness._test_output_created(self)
if __name__ == '__main__':
harness = StatepointTestHarness()
harness.main()

477
tests/test_tallies/inputs_true.dat
View file

@ -1 +1,476 @@
c01691348435ace955eb9ba8c6771f4e62cef427d1ce935971683f87bdadb9f4695379d9d664511213e883b6588d341d8e6265a4e36676f40bdbf3be6cc39898
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell fill="200" id="1" region="-6 34 -35" universe="0" />
<cell id="10" material="5" region="7 -8 31 -39" universe="0" />
<cell id="11" material="6" region="5 -6 32 -34" universe="0" />
<cell id="12" material="7" region="5 -6 36 -38" universe="0" />
<cell fill="201" id="2" region="-6 35 -36" universe="0" />
<cell id="21" material="1" region="-1" universe="1" />
<cell id="22" material="2" region="1 -2" universe="1" />
<cell id="23" material="3" region="2" universe="1" />
<cell id="24" material="3" region="-3" universe="2" />
<cell id="25" material="2" region="3 -4" universe="2" />
<cell id="26" material="3" region="4" universe="2" />
<cell id="27" material="1" region="-1" universe="3" />
<cell id="28" material="2" region="1 -2" universe="3" />
<cell id="29" material="4" region="2" universe="3" />
<cell id="3" material="8" region="-7 31 -32" universe="0" />
<cell id="30" material="4" region="-3" universe="4" />
<cell id="31" material="2" region="3 -4" universe="4" />
<cell id="32" material="4" region="4" universe="4" />
<cell id="4" material="9" region="-5 32 -33" universe="0" />
<cell id="5" material="12" region="-5 33 -34" universe="0" />
<cell id="50" material="3" region="34 -35" universe="5" />
<cell id="6" material="11" region="-5 36 -37" universe="0" />
<cell fill="100" id="60" region="34 -35" universe="6" />
<cell id="7" material="10" region="-5 37 -38" universe="0" />
<cell id="70" material="4" region="35 -36" universe="7" />
<cell id="8" material="7" region="-7 38 -39" universe="0" />
<cell fill="101" id="80" region="35 -36" universe="8" />
<cell id="9" material="9" region="6 -7 32 -38" universe="0" />
<lattice id="100" name="Fuel assembly (lower half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 </universes>
</lattice>
<lattice id="101" name="Fuel assembly (upper half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 </universes>
</lattice>
<lattice id="200" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 </universes>
</lattice>
<lattice id="201" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 </universes>
</lattice>
<surface coeffs="0.0 0.0 0.41" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.475" id="2" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.56" id="3" type="z-cylinder" />
<surface boundary="vacuum" coeffs="-229.0" id="31" type="z-plane" />
<surface coeffs="-199.0" id="32" type="z-plane" />
<surface coeffs="-193.0" id="33" type="z-plane" />
<surface coeffs="-183.0" id="34" type="z-plane" />
<surface coeffs="0.0" id="35" type="z-plane" />
<surface coeffs="183.0" id="36" type="z-plane" />
<surface coeffs="203.0" id="37" type="z-plane" />
<surface coeffs="215.0" id="38" type="z-plane" />
<surface boundary="vacuum" coeffs="223.0" id="39" type="z-plane" />
<surface coeffs="0.0 0.0 0.62" id="4" type="z-cylinder" />
<surface coeffs="0.0 0.0 187.6" id="5" type="z-cylinder" />
<surface coeffs="0.0 0.0 209.0" id="6" type="z-cylinder" />
<surface coeffs="0.0 0.0 229.0" id="7" type="z-cylinder" />
<surface boundary="vacuum" coeffs="0.0 0.0 249.0" id="8" type="z-cylinder" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="Fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
<nuclide ao="0.021504" name="U238" />
<nuclide ao="1.0801e-08" name="Xe135" />
<nuclide ao="0.045737" name="O16" />
</material>
<material id="10" name="Top nozzle region">
<density units="g/cm3" value="1.746" />
<nuclide name="H1" wo="0.035887" />
<nuclide name="O16" wo="0.2847761" />
<nuclide name="B10" wo="0.000115699" />
<nuclide name="B11" wo="0.000527075" />
<nuclide name="Fe54" wo="0.02644016154" />
<nuclide name="Fe56" wo="0.43037146399" />
<nuclide name="Fe57" wo="0.0101152584" />
<nuclide name="Fe58" wo="0.00137211607" />
<nuclide name="Ni58" wo="0.04104621835" />
<nuclide name="Mn55" wo="0.0135739" />
<nuclide name="Cr52" wo="0.107931450781" />
<sab name="c_H_in_H2O" />
</material>
<material id="11" name="Top of fuel assemblies">
<density units="g/cm3" value="3.044" />
<nuclide name="H1" wo="0.0162913" />
<nuclide name="O16" wo="0.1292776" />
<nuclide name="B10" wo="5.25228e-05" />
<nuclide name="B11" wo="0.000239272" />
<nuclide name="Zr90" wo="0.43313403903" />
<nuclide name="Zr91" wo="0.09549277374" />
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" />
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
<nuclide name="H1" wo="0.0292856" />
<nuclide name="O16" wo="0.2323919" />
<nuclide name="B10" wo="9.44159e-05" />
<nuclide name="B11" wo="0.00043012" />
<nuclide name="Zr90" wo="0.3741373658" />
<nuclide name="Zr91" wo="0.0824858164" />
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" />
</material>
<material id="2" name="Cladding">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="Cold borated water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
<nuclide name="Fe54" wo="0.05437098" />
<nuclide name="Fe56" wo="0.88500663" />
<nuclide name="Fe57" wo="0.0208008" />
<nuclide name="Fe58" wo="0.00282159" />
<nuclide name="Ni58" wo="0.0067198" />
<nuclide name="Ni60" wo="0.0026776" />
<nuclide name="Mn55" wo="0.01" />
<nuclide name="Cr52" wo="0.002092475" />
<nuclide name="C0" wo="0.0025" />
<nuclide name="Cu63" wo="0.0013696" />
</material>
<material id="6" name="Lower radial reflector">
<density units="g/cm3" value="4.32" />
<nuclide name="H1" wo="0.0095661" />
<nuclide name="O16" wo="0.0759107" />
<nuclide name="B10" wo="3.08409e-05" />
<nuclide name="B11" wo="0.000140499" />
<nuclide name="Fe54" wo="0.035620772088" />
<nuclide name="Fe56" wo="0.579805982228" />
<nuclide name="Fe57" wo="0.01362750048" />
<nuclide name="Fe58" wo="0.001848545204" />
<nuclide name="Ni58" wo="0.055298376566" />
<nuclide name="Mn55" wo="0.018287" />
<nuclide name="Cr52" wo="0.145407678031" />
<sab name="c_H_in_H2O" />
</material>
<material id="7" name="Upper radial reflector /Top plate region">
<density units="g/cm3" value="4.28" />
<nuclide name="H1" wo="0.0086117" />
<nuclide name="O16" wo="0.0683369" />
<nuclide name="B10" wo="2.77638e-05" />
<nuclide name="B11" wo="0.000126481" />
<nuclide name="Fe54" wo="0.035953677186" />
<nuclide name="Fe56" wo="0.585224740891" />
<nuclide name="Fe57" wo="0.01375486056" />
<nuclide name="Fe58" wo="0.001865821363" />
<nuclide name="Ni58" wo="0.055815129186" />
<nuclide name="Mn55" wo="0.0184579" />
<nuclide name="Cr52" wo="0.146766614995" />
<sab name="c_H_in_H2O" />
</material>
<material id="8" name="Bottom plate region">
<density units="g/cm3" value="7.184" />
<nuclide name="H1" wo="0.0011505" />
<nuclide name="O16" wo="0.0091296" />
<nuclide name="B10" wo="3.70915e-06" />
<nuclide name="B11" wo="1.68974e-05" />
<nuclide name="Fe54" wo="0.03855611055" />
<nuclide name="Fe56" wo="0.627585036425" />
<nuclide name="Fe57" wo="0.014750478" />
<nuclide name="Fe58" wo="0.002000875025" />
<nuclide name="Ni58" wo="0.059855207342" />
<nuclide name="Mn55" wo="0.019794" />
<nuclide name="Cr52" wo="0.157390026871" />
<sab name="c_H_in_H2O" />
</material>
<material id="9" name="Bottom nozzle region">
<density units="g/cm3" value="2.53" />
<nuclide name="H1" wo="0.0245014" />
<nuclide name="O16" wo="0.1944274" />
<nuclide name="B10" wo="7.89917e-05" />
<nuclide name="B11" wo="0.000359854" />
<nuclide name="Fe54" wo="0.030411411144" />
<nuclide name="Fe56" wo="0.495012237964" />
<nuclide name="Fe57" wo="0.01163454624" />
<nuclide name="Fe58" wo="0.001578204652" />
<nuclide name="Ni58" wo="0.047211231662" />
<nuclide name="Mn55" wo="0.0156126" />
<nuclide name="Cr52" wo="0.124142524198" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>400</particles>
<batches>5</batches>
<inactive>0</inactive>
</eigenvalue>
<source strength="1.0">
<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1" type="regular">
<dimension>2 2</dimension>
<lower_left>-182.07 -182.07</lower_left>
<upper_right>182.07 182.07</upper_right>
</mesh>
<tally id="10000">
<filter bins="-3.14159 -1.885 -0.6283 0.6283 1.885 3.14159" type="azimuthal" />
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10001">
<filter bins="-3.14159 -1.885 -0.6283 0.6283 1.885 3.14159" type="azimuthal" />
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10002">
<filter bins="-3.14159 -1.885 -0.6283 0.6283 1.885 3.14159" type="azimuthal" />
<filter bins="1" type="mesh" />
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10003">
<filter bins="10 21 22 23" type="cellborn" />
<scores>total</scores>
</tally>
<tally id="10004">
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
<scores>delayed-nu-fission</scores>
</tally>
<tally id="10005">
<filter bins="0.0 0.253 1000.0 1000000.0 20000000.0" type="energy" />
<scores>total</scores>
</tally>
<tally id="10006">
<filter bins="0.0 0.253 1000.0 1000000.0 20000000.0" type="energyout" />
<scores>scatter</scores>
</tally>
<tally id="10007">
<filter bins="0.0 0.253 1000.0 1000000.0 20000000.0" type="energy" />
<filter bins="0.0 0.253 1000.0 1000000.0 20000000.0" type="energyout" />
<scores>scatter nu-fission</scores>
</tally>
<tally id="10008">
<filter bins="1 2 3 4" type="material" />
<scores>total</scores>
</tally>
<tally id="10009">
<filter bins="-1.0 -0.5 0.0 0.5 1.0" type="mu" />
<scores>scatter nu-scatter</scores>
</tally>
<tally id="10010">
<filter bins="-1.0 -0.5 0.0 0.5 1.0" type="mu" />
<filter bins="1" type="mesh" />
<scores>scatter nu-scatter</scores>
</tally>
<tally id="10011">
<filter bins="0.0 0.6283 1.2566 1.885 2.5132 3.14159" type="polar" />
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10012">
<filter bins="0.0 0.6283 1.2566 1.885 2.5132 3.14159" type="polar" />
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10013">
<filter bins="0.0 0.6283 1.2566 1.885 2.5132 3.14159" type="polar" />
<filter bins="1" type="mesh" />
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10014">
<filter bins="1 2 3 4 6 8" type="universe" />
<scores>total</scores>
</tally>
<tally id="10015">
<filter bins="10 21 22 23 60" type="cell" />
<scores>absorption delayed-nu-fission events fission inverse-velocity kappa-fission (n,2n) (n,n1) (n,gamma) nu-fission scatter elastic total prompt-nu-fission fission-q-prompt fission-q-recoverable</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10016">
<filter bins="10 21 22 23 60" type="cell" />
<scores>absorption delayed-nu-fission events fission inverse-velocity kappa-fission (n,2n) (n,n1) (n,gamma) nu-fission scatter elastic total prompt-nu-fission fission-q-prompt fission-q-recoverable</scores>
<estimator>analog</estimator>
</tally>
<tally id="10017">
<filter bins="10 21 22 23 60" type="cell" />
<scores>absorption delayed-nu-fission events fission inverse-velocity kappa-fission (n,2n) (n,n1) (n,gamma) nu-fission scatter elastic total prompt-nu-fission fission-q-prompt fission-q-recoverable</scores>
<estimator>collision</estimator>
</tally>
<tally id="10018">
<filter bins="21 22 23 27 28 29 60" type="cell" />
<scores>flux</scores>
</tally>
<tally id="10019">
<filter bins="21 22 23 27 28 29 60" type="cell" />
<scores>flux-y5</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10020">
<filter bins="21 22 23 27 28 29 60" type="cell" />
<scores>flux-y5</scores>
<estimator>analog</estimator>
</tally>
<tally id="10021">
<filter bins="21 22 23 27 28 29 60" type="cell" />
<scores>flux-y5</scores>
<estimator>collision</estimator>
</tally>
<tally id="10022">
<filter bins="10 21 22 23 60" type="cell" />
<scores>scatter scatter-1 scatter-2 scatter-3 scatter-4 nu-scatter nu-scatter-1 nu-scatter-2 nu-scatter-3 nu-scatter-4</scores>
</tally>
<tally id="10023">
<filter bins="10 21 22 23 60" type="cell" />
<scores>scatter-p4 scatter-y4 nu-scatter-p4 nu-scatter-y3</scores>
</tally>
<tally id="10024">
<filter bins="10 21 22 23 60" type="cell" />
<scores>total</scores>
</tally>
<tally id="10025">
<filter bins="10 21 22 23 60" type="cell" />
<nuclides>U235 total</nuclides>
<scores>total-y4</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10026">
<filter bins="10 21 22 23 60" type="cell" />
<nuclides>U235 total</nuclides>
<scores>total-y4</scores>
<estimator>analog</estimator>
</tally>
<tally id="10027">
<filter bins="10 21 22 23 60" type="cell" />
<nuclides>U235 total</nuclides>
<scores>total-y4</scores>
<estimator>collision</estimator>
</tally>
<tally id="10028">
<filter bins="10 21 22 23 60" type="cell" />
<nuclides>all</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10029">
<filter bins="10 21 22 23 60" type="cell" />
<nuclides>all</nuclides>
<scores>total</scores>
<estimator>collision</estimator>
</tally>
<tally id="10030">
<filter bins="1" type="mesh" />
<nuclides>all</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10031">
<filter bins="1" type="mesh" />
<nuclides>U235</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
</tallies>

7
tests/test_tallies/test_tallies.py
View file

@ -177,12 +177,7 @@ class TalliesTestHarness(PyAPITestHarness):
def _get_results(self):
return super(TalliesTestHarness, self)._get_results(hash_output=True)
def _cleanup(self):
super(TalliesTestHarness, self)._cleanup()
f = os.path.join(os.getcwd(), 'tallies.xml')
if os.path.exists(f): os.remove(f)
if __name__ == '__main__':
harness = TalliesTestHarness('statepoint.5.*', True)
harness = TalliesTestHarness('statepoint.5.h5', True)
harness.main()

323
tests/test_tally_aggregation/inputs_true.dat
View file

@ -1 +1,322 @@
2ca11b519f903c106940ca4095764a5decab2c474f76a13a0869a9527db7e5bb5733b53b18b4dbb2a5e0dd0ae58cf55017491dae94d41b8094c1140d9079beb8
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell fill="200" id="1" region="-6 34 -35" universe="0" />
<cell id="10" material="5" region="7 -8 31 -39" universe="0" />
<cell id="11" material="6" region="5 -6 32 -34" universe="0" />
<cell id="12" material="7" region="5 -6 36 -38" universe="0" />
<cell fill="201" id="2" region="-6 35 -36" universe="0" />
<cell id="21" material="1" region="-1" universe="1" />
<cell id="22" material="2" region="1 -2" universe="1" />
<cell id="23" material="3" region="2" universe="1" />
<cell id="24" material="3" region="-3" universe="2" />
<cell id="25" material="2" region="3 -4" universe="2" />
<cell id="26" material="3" region="4" universe="2" />
<cell id="27" material="1" region="-1" universe="3" />
<cell id="28" material="2" region="1 -2" universe="3" />
<cell id="29" material="4" region="2" universe="3" />
<cell id="3" material="8" region="-7 31 -32" universe="0" />
<cell id="30" material="4" region="-3" universe="4" />
<cell id="31" material="2" region="3 -4" universe="4" />
<cell id="32" material="4" region="4" universe="4" />
<cell id="4" material="9" region="-5 32 -33" universe="0" />
<cell id="5" material="12" region="-5 33 -34" universe="0" />
<cell id="50" material="3" region="34 -35" universe="5" />
<cell id="6" material="11" region="-5 36 -37" universe="0" />
<cell fill="100" id="60" region="34 -35" universe="6" />
<cell id="7" material="10" region="-5 37 -38" universe="0" />
<cell id="70" material="4" region="35 -36" universe="7" />
<cell id="8" material="7" region="-7 38 -39" universe="0" />
<cell fill="101" id="80" region="35 -36" universe="8" />
<cell id="9" material="9" region="6 -7 32 -38" universe="0" />
<lattice id="100" name="Fuel assembly (lower half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 </universes>
</lattice>
<lattice id="101" name="Fuel assembly (upper half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 </universes>
</lattice>
<lattice id="200" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 </universes>
</lattice>
<lattice id="201" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 </universes>
</lattice>
<surface coeffs="0.0 0.0 0.41" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.475" id="2" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.56" id="3" type="z-cylinder" />
<surface boundary="vacuum" coeffs="-229.0" id="31" type="z-plane" />
<surface coeffs="-199.0" id="32" type="z-plane" />
<surface coeffs="-193.0" id="33" type="z-plane" />
<surface coeffs="-183.0" id="34" type="z-plane" />
<surface coeffs="0.0" id="35" type="z-plane" />
<surface coeffs="183.0" id="36" type="z-plane" />
<surface coeffs="203.0" id="37" type="z-plane" />
<surface coeffs="215.0" id="38" type="z-plane" />
<surface boundary="vacuum" coeffs="223.0" id="39" type="z-plane" />
<surface coeffs="0.0 0.0 0.62" id="4" type="z-cylinder" />
<surface coeffs="0.0 0.0 187.6" id="5" type="z-cylinder" />
<surface coeffs="0.0 0.0 209.0" id="6" type="z-cylinder" />
<surface coeffs="0.0 0.0 229.0" id="7" type="z-cylinder" />
<surface boundary="vacuum" coeffs="0.0 0.0 249.0" id="8" type="z-cylinder" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="Fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
<nuclide ao="0.021504" name="U238" />
<nuclide ao="1.0801e-08" name="Xe135" />
<nuclide ao="0.045737" name="O16" />
</material>
<material id="10" name="Top nozzle region">
<density units="g/cm3" value="1.746" />
<nuclide name="H1" wo="0.035887" />
<nuclide name="O16" wo="0.2847761" />
<nuclide name="B10" wo="0.000115699" />
<nuclide name="B11" wo="0.000527075" />
<nuclide name="Fe54" wo="0.02644016154" />
<nuclide name="Fe56" wo="0.43037146399" />
<nuclide name="Fe57" wo="0.0101152584" />
<nuclide name="Fe58" wo="0.00137211607" />
<nuclide name="Ni58" wo="0.04104621835" />
<nuclide name="Mn55" wo="0.0135739" />
<nuclide name="Cr52" wo="0.107931450781" />
<sab name="c_H_in_H2O" />
</material>
<material id="11" name="Top of fuel assemblies">
<density units="g/cm3" value="3.044" />
<nuclide name="H1" wo="0.0162913" />
<nuclide name="O16" wo="0.1292776" />
<nuclide name="B10" wo="5.25228e-05" />
<nuclide name="B11" wo="0.000239272" />
<nuclide name="Zr90" wo="0.43313403903" />
<nuclide name="Zr91" wo="0.09549277374" />
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" />
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
<nuclide name="H1" wo="0.0292856" />
<nuclide name="O16" wo="0.2323919" />
<nuclide name="B10" wo="9.44159e-05" />
<nuclide name="B11" wo="0.00043012" />
<nuclide name="Zr90" wo="0.3741373658" />
<nuclide name="Zr91" wo="0.0824858164" />
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" />
</material>
<material id="2" name="Cladding">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="Cold borated water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
<nuclide name="Fe54" wo="0.05437098" />
<nuclide name="Fe56" wo="0.88500663" />
<nuclide name="Fe57" wo="0.0208008" />
<nuclide name="Fe58" wo="0.00282159" />
<nuclide name="Ni58" wo="0.0067198" />
<nuclide name="Ni60" wo="0.0026776" />
<nuclide name="Mn55" wo="0.01" />
<nuclide name="Cr52" wo="0.002092475" />
<nuclide name="C0" wo="0.0025" />
<nuclide name="Cu63" wo="0.0013696" />
</material>
<material id="6" name="Lower radial reflector">
<density units="g/cm3" value="4.32" />
<nuclide name="H1" wo="0.0095661" />
<nuclide name="O16" wo="0.0759107" />
<nuclide name="B10" wo="3.08409e-05" />
<nuclide name="B11" wo="0.000140499" />
<nuclide name="Fe54" wo="0.035620772088" />
<nuclide name="Fe56" wo="0.579805982228" />
<nuclide name="Fe57" wo="0.01362750048" />
<nuclide name="Fe58" wo="0.001848545204" />
<nuclide name="Ni58" wo="0.055298376566" />
<nuclide name="Mn55" wo="0.018287" />
<nuclide name="Cr52" wo="0.145407678031" />
<sab name="c_H_in_H2O" />
</material>
<material id="7" name="Upper radial reflector /Top plate region">
<density units="g/cm3" value="4.28" />
<nuclide name="H1" wo="0.0086117" />
<nuclide name="O16" wo="0.0683369" />
<nuclide name="B10" wo="2.77638e-05" />
<nuclide name="B11" wo="0.000126481" />
<nuclide name="Fe54" wo="0.035953677186" />
<nuclide name="Fe56" wo="0.585224740891" />
<nuclide name="Fe57" wo="0.01375486056" />
<nuclide name="Fe58" wo="0.001865821363" />
<nuclide name="Ni58" wo="0.055815129186" />
<nuclide name="Mn55" wo="0.0184579" />
<nuclide name="Cr52" wo="0.146766614995" />
<sab name="c_H_in_H2O" />
</material>
<material id="8" name="Bottom plate region">
<density units="g/cm3" value="7.184" />
<nuclide name="H1" wo="0.0011505" />
<nuclide name="O16" wo="0.0091296" />
<nuclide name="B10" wo="3.70915e-06" />
<nuclide name="B11" wo="1.68974e-05" />
<nuclide name="Fe54" wo="0.03855611055" />
<nuclide name="Fe56" wo="0.627585036425" />
<nuclide name="Fe57" wo="0.014750478" />
<nuclide name="Fe58" wo="0.002000875025" />
<nuclide name="Ni58" wo="0.059855207342" />
<nuclide name="Mn55" wo="0.019794" />
<nuclide name="Cr52" wo="0.157390026871" />
<sab name="c_H_in_H2O" />
</material>
<material id="9" name="Bottom nozzle region">
<density units="g/cm3" value="2.53" />
<nuclide name="H1" wo="0.0245014" />
<nuclide name="O16" wo="0.1944274" />
<nuclide name="B10" wo="7.89917e-05" />
<nuclide name="B11" wo="0.000359854" />
<nuclide name="Fe54" wo="0.030411411144" />
<nuclide name="Fe56" wo="0.495012237964" />
<nuclide name="Fe57" wo="0.01163454624" />
<nuclide name="Fe58" wo="0.001578204652" />
<nuclide name="Ni58" wo="0.047211231662" />
<nuclide name="Mn55" wo="0.0156126" />
<nuclide name="Cr52" wo="0.124142524198" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
</eigenvalue>
<source strength="1.0">
<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
<output>
<summary>true</summary>
</output>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<tally id="10000" name="distribcell tally">
<filter bins="0.0 0.253 1000.0 1000000.0 20000000.0" type="energy" />
<filter bins="60" type="distribcell" />
<nuclides>U234 U235 U238</nuclides>
<scores>nu-fission total</scores>
</tally>
</tallies>

4
tests/test_tally_aggregation/test_tally_aggregation.py
View file

@ -76,10 +76,6 @@ class TallyAggregationTestHarness(PyAPITestHarness):
return outstr
def _cleanup(self):
super(TallyAggregationTestHarness, self)._cleanup()
f = os.path.join(os.getcwd(), 'tallies.xml')
if os.path.exists(f): os.remove(f)
if __name__ == '__main__':
harness = TallyAggregationTestHarness('statepoint.10.h5', True)

335
tests/test_tally_arithmetic/inputs_true.dat
View file

@ -1 +1,334 @@
530c54691a4f2df131627849dd58c5e6f331ede786c1ffff0b1126c4c0fe64929a15113699103a05f2c6178ec90be4a3d6fc12b80c32ec608ed4a59c965ef2e4
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell fill="200" id="1" region="-6 34 -35" universe="0" />
<cell id="10" material="5" region="7 -8 31 -39" universe="0" />
<cell id="11" material="6" region="5 -6 32 -34" universe="0" />
<cell id="12" material="7" region="5 -6 36 -38" universe="0" />
<cell fill="201" id="2" region="-6 35 -36" universe="0" />
<cell id="21" material="1" region="-1" universe="1" />
<cell id="22" material="2" region="1 -2" universe="1" />
<cell id="23" material="3" region="2" universe="1" />
<cell id="24" material="3" region="-3" universe="2" />
<cell id="25" material="2" region="3 -4" universe="2" />
<cell id="26" material="3" region="4" universe="2" />
<cell id="27" material="1" region="-1" universe="3" />
<cell id="28" material="2" region="1 -2" universe="3" />
<cell id="29" material="4" region="2" universe="3" />
<cell id="3" material="8" region="-7 31 -32" universe="0" />
<cell id="30" material="4" region="-3" universe="4" />
<cell id="31" material="2" region="3 -4" universe="4" />
<cell id="32" material="4" region="4" universe="4" />
<cell id="4" material="9" region="-5 32 -33" universe="0" />
<cell id="5" material="12" region="-5 33 -34" universe="0" />
<cell id="50" material="3" region="34 -35" universe="5" />
<cell id="6" material="11" region="-5 36 -37" universe="0" />
<cell fill="100" id="60" region="34 -35" universe="6" />
<cell id="7" material="10" region="-5 37 -38" universe="0" />
<cell id="70" material="4" region="35 -36" universe="7" />
<cell id="8" material="7" region="-7 38 -39" universe="0" />
<cell fill="101" id="80" region="35 -36" universe="8" />
<cell id="9" material="9" region="6 -7 32 -38" universe="0" />
<lattice id="100" name="Fuel assembly (lower half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 </universes>
</lattice>
<lattice id="101" name="Fuel assembly (upper half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 </universes>
</lattice>
<lattice id="200" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 </universes>
</lattice>
<lattice id="201" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 </universes>
</lattice>
<surface coeffs="0.0 0.0 0.41" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.475" id="2" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.56" id="3" type="z-cylinder" />
<surface boundary="vacuum" coeffs="-229.0" id="31" type="z-plane" />
<surface coeffs="-199.0" id="32" type="z-plane" />
<surface coeffs="-193.0" id="33" type="z-plane" />
<surface coeffs="-183.0" id="34" type="z-plane" />
<surface coeffs="0.0" id="35" type="z-plane" />
<surface coeffs="183.0" id="36" type="z-plane" />
<surface coeffs="203.0" id="37" type="z-plane" />
<surface coeffs="215.0" id="38" type="z-plane" />
<surface boundary="vacuum" coeffs="223.0" id="39" type="z-plane" />
<surface coeffs="0.0 0.0 0.62" id="4" type="z-cylinder" />
<surface coeffs="0.0 0.0 187.6" id="5" type="z-cylinder" />
<surface coeffs="0.0 0.0 209.0" id="6" type="z-cylinder" />
<surface coeffs="0.0 0.0 229.0" id="7" type="z-cylinder" />
<surface boundary="vacuum" coeffs="0.0 0.0 249.0" id="8" type="z-cylinder" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="Fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
<nuclide ao="0.021504" name="U238" />
<nuclide ao="1.0801e-08" name="Xe135" />
<nuclide ao="0.045737" name="O16" />
</material>
<material id="10" name="Top nozzle region">
<density units="g/cm3" value="1.746" />
<nuclide name="H1" wo="0.035887" />
<nuclide name="O16" wo="0.2847761" />
<nuclide name="B10" wo="0.000115699" />
<nuclide name="B11" wo="0.000527075" />
<nuclide name="Fe54" wo="0.02644016154" />
<nuclide name="Fe56" wo="0.43037146399" />
<nuclide name="Fe57" wo="0.0101152584" />
<nuclide name="Fe58" wo="0.00137211607" />
<nuclide name="Ni58" wo="0.04104621835" />
<nuclide name="Mn55" wo="0.0135739" />
<nuclide name="Cr52" wo="0.107931450781" />
<sab name="c_H_in_H2O" />
</material>
<material id="11" name="Top of fuel assemblies">
<density units="g/cm3" value="3.044" />
<nuclide name="H1" wo="0.0162913" />
<nuclide name="O16" wo="0.1292776" />
<nuclide name="B10" wo="5.25228e-05" />
<nuclide name="B11" wo="0.000239272" />
<nuclide name="Zr90" wo="0.43313403903" />
<nuclide name="Zr91" wo="0.09549277374" />
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" />
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
<nuclide name="H1" wo="0.0292856" />
<nuclide name="O16" wo="0.2323919" />
<nuclide name="B10" wo="9.44159e-05" />
<nuclide name="B11" wo="0.00043012" />
<nuclide name="Zr90" wo="0.3741373658" />
<nuclide name="Zr91" wo="0.0824858164" />
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" />
</material>
<material id="2" name="Cladding">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="Cold borated water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
<nuclide name="Fe54" wo="0.05437098" />
<nuclide name="Fe56" wo="0.88500663" />
<nuclide name="Fe57" wo="0.0208008" />
<nuclide name="Fe58" wo="0.00282159" />
<nuclide name="Ni58" wo="0.0067198" />
<nuclide name="Ni60" wo="0.0026776" />
<nuclide name="Mn55" wo="0.01" />
<nuclide name="Cr52" wo="0.002092475" />
<nuclide name="C0" wo="0.0025" />
<nuclide name="Cu63" wo="0.0013696" />
</material>
<material id="6" name="Lower radial reflector">
<density units="g/cm3" value="4.32" />
<nuclide name="H1" wo="0.0095661" />
<nuclide name="O16" wo="0.0759107" />
<nuclide name="B10" wo="3.08409e-05" />
<nuclide name="B11" wo="0.000140499" />
<nuclide name="Fe54" wo="0.035620772088" />
<nuclide name="Fe56" wo="0.579805982228" />
<nuclide name="Fe57" wo="0.01362750048" />
<nuclide name="Fe58" wo="0.001848545204" />
<nuclide name="Ni58" wo="0.055298376566" />
<nuclide name="Mn55" wo="0.018287" />
<nuclide name="Cr52" wo="0.145407678031" />
<sab name="c_H_in_H2O" />
</material>
<material id="7" name="Upper radial reflector /Top plate region">
<density units="g/cm3" value="4.28" />
<nuclide name="H1" wo="0.0086117" />
<nuclide name="O16" wo="0.0683369" />
<nuclide name="B10" wo="2.77638e-05" />
<nuclide name="B11" wo="0.000126481" />
<nuclide name="Fe54" wo="0.035953677186" />
<nuclide name="Fe56" wo="0.585224740891" />
<nuclide name="Fe57" wo="0.01375486056" />
<nuclide name="Fe58" wo="0.001865821363" />
<nuclide name="Ni58" wo="0.055815129186" />
<nuclide name="Mn55" wo="0.0184579" />
<nuclide name="Cr52" wo="0.146766614995" />
<sab name="c_H_in_H2O" />
</material>
<material id="8" name="Bottom plate region">
<density units="g/cm3" value="7.184" />
<nuclide name="H1" wo="0.0011505" />
<nuclide name="O16" wo="0.0091296" />
<nuclide name="B10" wo="3.70915e-06" />
<nuclide name="B11" wo="1.68974e-05" />
<nuclide name="Fe54" wo="0.03855611055" />
<nuclide name="Fe56" wo="0.627585036425" />
<nuclide name="Fe57" wo="0.014750478" />
<nuclide name="Fe58" wo="0.002000875025" />
<nuclide name="Ni58" wo="0.059855207342" />
<nuclide name="Mn55" wo="0.019794" />
<nuclide name="Cr52" wo="0.157390026871" />
<sab name="c_H_in_H2O" />
</material>
<material id="9" name="Bottom nozzle region">
<density units="g/cm3" value="2.53" />
<nuclide name="H1" wo="0.0245014" />
<nuclide name="O16" wo="0.1944274" />
<nuclide name="B10" wo="7.89917e-05" />
<nuclide name="B11" wo="0.000359854" />
<nuclide name="Fe54" wo="0.030411411144" />
<nuclide name="Fe56" wo="0.495012237964" />
<nuclide name="Fe57" wo="0.01163454624" />
<nuclide name="Fe58" wo="0.001578204652" />
<nuclide name="Ni58" wo="0.047211231662" />
<nuclide name="Mn55" wo="0.0156126" />
<nuclide name="Cr52" wo="0.124142524198" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
</eigenvalue>
<source strength="1.0">
<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
<output>
<summary>true</summary>
</output>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1" type="regular">
<dimension>2 2 2</dimension>
<lower_left>-160.0 -160.0 -183.0</lower_left>
<upper_right>160.0 160.0 183.0</upper_right>
</mesh>
<tally id="10000" name="tally 1">
<filter bins="1 3" type="material" />
<filter bins="0.0 2.53e-07 0.001 1.0 20.0" type="energy" />
<filter bins="60" type="distribcell" />
<nuclides>U234 U235</nuclides>
<scores>nu-fission total</scores>
</tally>
<tally id="10001" name="tally 2">
<filter bins="0.0 2.53e-07 0.001 1.0 20.0" type="energy" />
<filter bins="1" type="mesh" />
<nuclides>U238 U235</nuclides>
<scores>total fission</scores>
</tally>
</tallies>

4
tests/test_tally_arithmetic/test_tally_arithmetic.py
View file

@ -93,10 +93,6 @@ class TallyArithmeticTestHarness(PyAPITestHarness):
return outstr
def _cleanup(self):
super(TallyArithmeticTestHarness, self)._cleanup()
f = os.path.join(os.getcwd(), 'tallies.xml')
if os.path.exists(f): os.remove(f)
if __name__ == '__main__':
harness = TallyArithmeticTestHarness('statepoint.10.h5', True)

341
tests/test_tally_slice_merge/inputs_true.dat
View file

@ -1 +1,340 @@
8ce48c0217ed0e9a151a96307db9bf3b2d897f8f1d36bbc1f96e24cad914bd6eaa0510e70d9c54f222fb5178bfe515eaaa4aebd11cbcd3f6c757749fddee6e9d
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell fill="200" id="1" region="-6 34 -35" universe="0" />
<cell id="10" material="5" region="7 -8 31 -39" universe="0" />
<cell id="11" material="6" region="5 -6 32 -34" universe="0" />
<cell id="12" material="7" region="5 -6 36 -38" universe="0" />
<cell fill="201" id="2" region="-6 35 -36" universe="0" />
<cell id="21" material="1" region="-1" universe="1" />
<cell id="22" material="2" region="1 -2" universe="1" />
<cell id="23" material="3" region="2" universe="1" />
<cell id="24" material="3" region="-3" universe="2" />
<cell id="25" material="2" region="3 -4" universe="2" />
<cell id="26" material="3" region="4" universe="2" />
<cell id="27" material="1" region="-1" universe="3" />
<cell id="28" material="2" region="1 -2" universe="3" />
<cell id="29" material="4" region="2" universe="3" />
<cell id="3" material="8" region="-7 31 -32" universe="0" />
<cell id="30" material="4" region="-3" universe="4" />
<cell id="31" material="2" region="3 -4" universe="4" />
<cell id="32" material="4" region="4" universe="4" />
<cell id="4" material="9" region="-5 32 -33" universe="0" />
<cell id="5" material="12" region="-5 33 -34" universe="0" />
<cell id="50" material="3" region="34 -35" universe="5" />
<cell id="6" material="11" region="-5 36 -37" universe="0" />
<cell fill="100" id="60" region="34 -35" universe="6" />
<cell id="7" material="10" region="-5 37 -38" universe="0" />
<cell id="70" material="4" region="35 -36" universe="7" />
<cell id="8" material="7" region="-7 38 -39" universe="0" />
<cell fill="101" id="80" region="35 -36" universe="8" />
<cell id="9" material="9" region="6 -7 32 -38" universe="0" />
<lattice id="100" name="Fuel assembly (lower half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 </universes>
</lattice>
<lattice id="101" name="Fuel assembly (upper half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 </universes>
</lattice>
<lattice id="200" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 </universes>
</lattice>
<lattice id="201" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 </universes>
</lattice>
<surface coeffs="0.0 0.0 0.41" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.475" id="2" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.56" id="3" type="z-cylinder" />
<surface boundary="vacuum" coeffs="-229.0" id="31" type="z-plane" />
<surface coeffs="-199.0" id="32" type="z-plane" />
<surface coeffs="-193.0" id="33" type="z-plane" />
<surface coeffs="-183.0" id="34" type="z-plane" />
<surface coeffs="0.0" id="35" type="z-plane" />
<surface coeffs="183.0" id="36" type="z-plane" />
<surface coeffs="203.0" id="37" type="z-plane" />
<surface coeffs="215.0" id="38" type="z-plane" />
<surface boundary="vacuum" coeffs="223.0" id="39" type="z-plane" />
<surface coeffs="0.0 0.0 0.62" id="4" type="z-cylinder" />
<surface coeffs="0.0 0.0 187.6" id="5" type="z-cylinder" />
<surface coeffs="0.0 0.0 209.0" id="6" type="z-cylinder" />
<surface coeffs="0.0 0.0 229.0" id="7" type="z-cylinder" />
<surface boundary="vacuum" coeffs="0.0 0.0 249.0" id="8" type="z-cylinder" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="Fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
<nuclide ao="0.021504" name="U238" />
<nuclide ao="1.0801e-08" name="Xe135" />
<nuclide ao="0.045737" name="O16" />
</material>
<material id="10" name="Top nozzle region">
<density units="g/cm3" value="1.746" />
<nuclide name="H1" wo="0.035887" />
<nuclide name="O16" wo="0.2847761" />
<nuclide name="B10" wo="0.000115699" />
<nuclide name="B11" wo="0.000527075" />
<nuclide name="Fe54" wo="0.02644016154" />
<nuclide name="Fe56" wo="0.43037146399" />
<nuclide name="Fe57" wo="0.0101152584" />
<nuclide name="Fe58" wo="0.00137211607" />
<nuclide name="Ni58" wo="0.04104621835" />
<nuclide name="Mn55" wo="0.0135739" />
<nuclide name="Cr52" wo="0.107931450781" />
<sab name="c_H_in_H2O" />
</material>
<material id="11" name="Top of fuel assemblies">
<density units="g/cm3" value="3.044" />
<nuclide name="H1" wo="0.0162913" />
<nuclide name="O16" wo="0.1292776" />
<nuclide name="B10" wo="5.25228e-05" />
<nuclide name="B11" wo="0.000239272" />
<nuclide name="Zr90" wo="0.43313403903" />
<nuclide name="Zr91" wo="0.09549277374" />
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" />
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
<nuclide name="H1" wo="0.0292856" />
<nuclide name="O16" wo="0.2323919" />
<nuclide name="B10" wo="9.44159e-05" />
<nuclide name="B11" wo="0.00043012" />
<nuclide name="Zr90" wo="0.3741373658" />
<nuclide name="Zr91" wo="0.0824858164" />
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" />
</material>
<material id="2" name="Cladding">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="Cold borated water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
<nuclide name="Fe54" wo="0.05437098" />
<nuclide name="Fe56" wo="0.88500663" />
<nuclide name="Fe57" wo="0.0208008" />
<nuclide name="Fe58" wo="0.00282159" />
<nuclide name="Ni58" wo="0.0067198" />
<nuclide name="Ni60" wo="0.0026776" />
<nuclide name="Mn55" wo="0.01" />
<nuclide name="Cr52" wo="0.002092475" />
<nuclide name="C0" wo="0.0025" />
<nuclide name="Cu63" wo="0.0013696" />
</material>
<material id="6" name="Lower radial reflector">
<density units="g/cm3" value="4.32" />
<nuclide name="H1" wo="0.0095661" />
<nuclide name="O16" wo="0.0759107" />
<nuclide name="B10" wo="3.08409e-05" />
<nuclide name="B11" wo="0.000140499" />
<nuclide name="Fe54" wo="0.035620772088" />
<nuclide name="Fe56" wo="0.579805982228" />
<nuclide name="Fe57" wo="0.01362750048" />
<nuclide name="Fe58" wo="0.001848545204" />
<nuclide name="Ni58" wo="0.055298376566" />
<nuclide name="Mn55" wo="0.018287" />
<nuclide name="Cr52" wo="0.145407678031" />
<sab name="c_H_in_H2O" />
</material>
<material id="7" name="Upper radial reflector /Top plate region">
<density units="g/cm3" value="4.28" />
<nuclide name="H1" wo="0.0086117" />
<nuclide name="O16" wo="0.0683369" />
<nuclide name="B10" wo="2.77638e-05" />
<nuclide name="B11" wo="0.000126481" />
<nuclide name="Fe54" wo="0.035953677186" />
<nuclide name="Fe56" wo="0.585224740891" />
<nuclide name="Fe57" wo="0.01375486056" />
<nuclide name="Fe58" wo="0.001865821363" />
<nuclide name="Ni58" wo="0.055815129186" />
<nuclide name="Mn55" wo="0.0184579" />
<nuclide name="Cr52" wo="0.146766614995" />
<sab name="c_H_in_H2O" />
</material>
<material id="8" name="Bottom plate region">
<density units="g/cm3" value="7.184" />
<nuclide name="H1" wo="0.0011505" />
<nuclide name="O16" wo="0.0091296" />
<nuclide name="B10" wo="3.70915e-06" />
<nuclide name="B11" wo="1.68974e-05" />
<nuclide name="Fe54" wo="0.03855611055" />
<nuclide name="Fe56" wo="0.627585036425" />
<nuclide name="Fe57" wo="0.014750478" />
<nuclide name="Fe58" wo="0.002000875025" />
<nuclide name="Ni58" wo="0.059855207342" />
<nuclide name="Mn55" wo="0.019794" />
<nuclide name="Cr52" wo="0.157390026871" />
<sab name="c_H_in_H2O" />
</material>
<material id="9" name="Bottom nozzle region">
<density units="g/cm3" value="2.53" />
<nuclide name="H1" wo="0.0245014" />
<nuclide name="O16" wo="0.1944274" />
<nuclide name="B10" wo="7.89917e-05" />
<nuclide name="B11" wo="0.000359854" />
<nuclide name="Fe54" wo="0.030411411144" />
<nuclide name="Fe56" wo="0.495012237964" />
<nuclide name="Fe57" wo="0.01163454624" />
<nuclide name="Fe58" wo="0.001578204652" />
<nuclide name="Ni58" wo="0.047211231662" />
<nuclide name="Mn55" wo="0.0156126" />
<nuclide name="Cr52" wo="0.124142524198" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
</eigenvalue>
<source strength="1.0">
<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<!--mesh-->
<mesh id="10000" type="regular">
<dimension>2 2</dimension>
<lower_left>-50.0 -50.0</lower_left>
<upper_right>50.0 50.0</upper_right>
</mesh>
<tally id="10030" name="cell tally">
<filter bins="21 27" type="cell" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>U235 U238</nuclides>
<scores>fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10031" name="distribcell tally">
<filter bins="21" type="distribcell" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>U235 U238</nuclides>
<scores>fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10032" name="mesh tally">
<filter bins="10000" type="mesh" />
<filter bins="0.0 0.625 20000000.0" type="energy" />
<nuclides>U235 U238</nuclides>
<scores>fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
</tallies>

4
tests/test_tally_slice_merge/test_tally_slice_merge.py
View file

@ -176,10 +176,6 @@ class TallySliceMergeTestHarness(PyAPITestHarness):
return outstr
def _cleanup(self):
super(TallySliceMergeTestHarness, self)._cleanup()
f = os.path.join(os.getcwd(), 'tallies.xml')
if os.path.exists(f): os.remove(f)
if __name__ == '__main__':
harness = TallySliceMergeTestHarness('statepoint.10.h5', True)

450
tests/test_triso/inputs_true.dat
View file

@ -1 +1,449 @@
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<?xml version='1.0' encoding='utf-8'?>
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<surface coeffs="0.146637865541 -0.000183171192208 -0.159896052961 0.04225" id="10204" type="sphere" />
<surface coeffs="-0.186695467792 -0.000183171192208 -0.159896052961 0.04225" id="10205" type="sphere" />
<surface coeffs="0.00688615671293 0.0325721225173 -0.107852540144 0.04225" id="10206" type="sphere" />
<surface coeffs="0.0594642653073 0.175629948849 0.11256068343 0.04225" id="10207" type="sphere" />
<surface coeffs="0.0594642653073 -0.157703384484 0.11256068343 0.04225" id="10208" type="sphere" />
<surface coeffs="-0.0745211393531 0.186025398941 0.07061211192 0.04225" id="10209" type="sphere" />
<surface coeffs="-0.0745211393531 -0.147307934392 0.07061211192 0.04225" id="10210" type="sphere" />
<surface coeffs="0.159713616332 -0.0241680036074 0.0623342971853 0.04225" id="10211" type="sphere" />
<surface coeffs="-0.173619717001 -0.0241680036074 0.0623342971853 0.04225" id="10212" type="sphere" />
<surface coeffs="-0.0141914194483 0.111149451072 0.0903966514578 0.04225" id="10213" type="sphere" />
<surface coeffs="0.206413378004 -0.0468919157204 0.0309383201461 0.04225" id="10214" type="sphere" />
<surface coeffs="-0.126919955329 -0.0468919157204 0.0309383201461 0.04225" id="10215" type="sphere" />
<surface coeffs="0.0429259824683 0.070555715848 -0.0961124680564 0.04225" id="10216" type="sphere" />
<surface coeffs="0.0917411839861 -0.0210268081646 -0.120747126544 0.04225" id="10217" type="sphere" />
<surface coeffs="0.187114465978 0.142190928958 0.00303951516048 0.04225" id="10218" type="sphere" />
<surface coeffs="-0.146218867356 0.142190928958 0.00303951516048 0.04225" id="10219" type="sphere" />
<surface coeffs="0.187114465978 -0.191142404375 0.00303951516048 0.04225" id="10220" type="sphere" />
<surface coeffs="-0.146218867356 -0.191142404375 0.00303951516048 0.04225" id="10221" type="sphere" />
<surface coeffs="-0.0885860120512 -0.0574080917257 0.00189379783576 0.04225" id="10222" type="sphere" />
<surface coeffs="-0.0695627245254 -0.0325861164534 0.187674961732 0.04225" id="10223" type="sphere" />
<surface coeffs="-0.0695627245254 -0.0325861164534 -0.145658371601 0.04225" id="10224" type="sphere" />
<surface coeffs="0.0648004866859 0.0803935669348 -0.0495807099831 0.04225" id="10225" type="sphere" />
<surface coeffs="0.119768828483 0.0244148877182 0.0590010758314 0.04225" id="10226" type="sphere" />
<surface coeffs="0.055815690197 -0.0386622433477 0.129344155705 0.04225" id="10227" type="sphere" />
<surface coeffs="0.055815690197 -0.0386622433477 -0.203989177628 0.04225" id="10228" type="sphere" />
<surface coeffs="-0.0705714088439 -0.0332615859242 -0.113081179589 0.04225" id="10229" type="sphere" />
<surface coeffs="0.0191891610992 -0.0877751186437 0.0949676788695 0.04225" id="10230" type="sphere" />
<surface coeffs="0.11357577214 -0.0723120607076 -0.0186231523344 0.04225" id="10231" type="sphere" />
<surface coeffs="0.0288228703292 0.0966036043404 -0.109945458994 0.04225" id="10232" type="sphere" />
<surface coeffs="-0.0302720060162 0.0427214916014 -0.111437158817 0.04225" id="10233" type="sphere" />
<surface coeffs="0.0971933921082 0.0413100742886 0.144761925354 0.04225" id="10234" type="sphere" />
<surface coeffs="0.0971933921082 0.0413100742886 -0.18857140798 0.04225" id="10235" type="sphere" />
<surface coeffs="0.107580312879 -0.0210472571374 -0.03274843538 0.04225" id="10236" type="sphere" />
<surface coeffs="0.139201957633 -0.0881443612864 -0.114798284951 0.04225" id="10237" type="sphere" />
<surface coeffs="-0.194131375701 -0.0881443612864 -0.114798284951 0.04225" id="10238" type="sphere" />
<surface coeffs="0.108471976774 0.146159230208 0.088410423839 0.04225" id="10239" type="sphere" />
<surface coeffs="0.108471976774 -0.187174103125 0.088410423839 0.04225" id="10240" type="sphere" />
<surface coeffs="0.0451270583821 0.096780721612 0.0967653665332 0.04225" id="10241" type="sphere" />
<surface coeffs="-0.0224644717455 0.0725927720514 0.107852198651 0.04225" id="10242" type="sphere" />
<surface coeffs="0.106063533699 0.0392870322973 0.172287769268 0.04225" id="10243" type="sphere" />
<surface coeffs="0.106063533699 0.0392870322973 -0.161045564066 0.04225" id="10244" type="sphere" />
<surface coeffs="0.148159419635 0.112776558875 0.0380868716968 0.04225" id="10245" type="sphere" />
<surface coeffs="-0.185173913698 0.112776558875 0.0380868716968 0.04225" id="10246" type="sphere" />
<surface coeffs="0.156935816691 0.101145318349 -0.0499235619578 0.04225" id="10247" type="sphere" />
<surface coeffs="-0.176397516643 0.101145318349 -0.0499235619578 0.04225" id="10248" type="sphere" />
<surface coeffs="0.132643578757 0.109198051281 -0.0476954987918 0.04225" id="10249" type="sphere" />
<surface coeffs="-0.200689754577 0.109198051281 -0.0476954987918 0.04225" id="10250" type="sphere" />
<surface coeffs="0.139165644346 0.131343196487 0.0701591217856 0.04225" id="10251" type="sphere" />
<surface coeffs="-0.194167688987 0.131343196487 0.0701591217856 0.04225" id="10252" type="sphere" />
<surface coeffs="0.139165644346 -0.201990136846 0.0701591217856 0.04225" id="10253" type="sphere" />
<surface coeffs="-0.194167688987 -0.201990136846 0.0701591217856 0.04225" id="10254" type="sphere" />
<surface coeffs="-0.100266886432 0.15644435527 0.175172848479 0.04225" id="10255" type="sphere" />
<surface coeffs="-0.100266886432 -0.176888978063 0.175172848479 0.04225" id="10256" type="sphere" />
<surface coeffs="-0.100266886432 0.15644435527 -0.158160484854 0.04225" id="10257" type="sphere" />
<surface coeffs="-0.100266886432 -0.176888978063 -0.158160484854 0.04225" id="10258" type="sphere" />
<surface coeffs="0.165554360307 -0.0155314552194 0.0269161414417 0.04225" id="10259" type="sphere" />
<surface coeffs="-0.167778973026 -0.0155314552194 0.0269161414417 0.04225" id="10260" type="sphere" />
<surface coeffs="0.152805274649 0.181665566207 0.0404883666838 0.04225" id="10261" type="sphere" />
<surface coeffs="-0.180528058685 0.181665566207 0.0404883666838 0.04225" id="10262" type="sphere" />
<surface coeffs="0.152805274649 -0.151667767127 0.0404883666838 0.04225" id="10263" type="sphere" />
<surface coeffs="-0.180528058685 -0.151667767127 0.0404883666838 0.04225" id="10264" type="sphere" />
<surface coeffs="0.0723111669483 0.0878537053709 0.0999705558994 0.04225" id="10265" type="sphere" />
<surface coeffs="-0.105764243624 0.0987449723258 -0.0582008094074 0.04225" id="10266" type="sphere" />
<surface coeffs="0.0468779531251 -0.0594927321842 -0.0556353418577 0.04225" id="10267" type="sphere" />
<surface coeffs="0.123942306657 0.141830462742 -0.0658381874921 0.04225" id="10268" type="sphere" />
<surface coeffs="0.123942306657 -0.191502870591 -0.0658381874921 0.04225" id="10269" type="sphere" />
<surface coeffs="0.0013087859342 -0.0632759448088 -0.0538252207421 0.04225" id="10270" type="sphere" />
<surface coeffs="0.110588836699 -0.0389541758206 0.16834558789 0.04225" id="10271" type="sphere" />
<surface coeffs="0.110588836699 -0.0389541758206 -0.164987745443 0.04225" id="10272" type="sphere" />
<surface coeffs="-0.0265701006572 0.0131449788411 0.0505879445141 0.04225" id="10273" type="sphere" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="10000">
<density units="g/cm3" value="10.5" />
<nuclide ao="0.14154" name="U235" />
<nuclide ao="0.85846" name="U238" />
<nuclide ao="0.5" name="C0" />
<nuclide ao="1.5" name="O16" />
</material>
<material id="10001">
<density units="g/cm3" value="1.0" />
<nuclide ao="1.0" name="C0" />
<sab name="c_Graphite" />
</material>
<material id="10002">
<density units="g/cm3" value="1.9" />
<nuclide ao="1.0" name="C0" />
<sab name="c_Graphite" />
</material>
<material id="10003">
<density units="g/cm3" value="3.2" />
<nuclide ao="1.0" name="C0" />
<nuclide ao="0.92223" name="Si28" />
<nuclide ao="0.04685" name="Si29" />
<nuclide ao="0.03092" name="Si30" />
</material>
<material id="10004">
<density units="g/cm3" value="1.87" />
<nuclide ao="1.0" name="C0" />
<sab name="c_Graphite" />
</material>
<material id="10005">
<density units="g/cm3" value="1.1995" />
<nuclide ao="1.0" name="C0" />
<sab name="c_Graphite" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>100</particles>
<batches>5</batches>
<inactive>0</inactive>
</eigenvalue>
<source strength="1.0">
<space type="point">
<parameters>0.0 0.0 0.0</parameters>
</space>
</source>
</settings>
<?xml version="1.0"?>
<plots>
<plot id="1" type="slice" basis="xy" color="material"
origin="0.0 0.0 0.0" width="1.0 1.0" pixels="400 400">
</plot>
</plots>

61
tests/test_volume_calc/inputs_true.dat
View file

@ -1 +1,60 @@
382404d3061d2c847c87654ab12594ba3fbb7e3a82327da872b5fe2029018ef4d5d3376fceba5c2229ea6f85e1fb63650caf54baed3f3b0304137fde61a98d63
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="2" region="-1 -3 5" universe="0" />
<cell id="2" material="1" region="-2 3" universe="0" />
<cell id="3" material="1" region="-4 -3" universe="0" />
<surface boundary="vacuum" coeffs="0.0 0.0 1.0" id="1" type="z-cylinder" />
<surface boundary="vacuum" coeffs="0.0 0.0 5.0 1.0" id="2" type="sphere" />
<surface coeffs="5.0" id="3" type="z-plane" />
<surface boundary="vacuum" coeffs="0.0 0.0 -5.0 1.0" id="4" type="sphere" />
<surface coeffs="-5.0" id="5" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1">
<density units="g/cc" value="1.0" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.0001" name="B10" />
<sab name="c_H_in_H2O" />
</material>
<material id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
<nuclide ao="0.1" name="Mo99" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>1000</particles>
<batches>4</batches>
<inactive>0</inactive>
</eigenvalue>
<source strength="1.0">
<space type="box">
<parameters>-1.0 -1.0 -5.0 1.0 1.0 5.0</parameters>
</space>
</source>
<volume_calc>
<domain_type>cell</domain_type>
<domain_ids>1 2 3</domain_ids>
<samples>100000</samples>
<lower_left>-1.0 -1.0 -6.0</lower_left>
<upper_right>1.0 1.0 6.0</upper_right>
</volume_calc>
<volume_calc>
<domain_type>material</domain_type>
<domain_ids>1 2</domain_ids>
<samples>100000</samples>
<lower_left>-1.0 -1.0 -6.0</lower_left>
<upper_right>1.0 1.0 6.0</upper_right>
</volume_calc>
<volume_calc>
<domain_type>universe</domain_type>
<domain_ids>0</domain_ids>
<samples>100000</samples>
<lower_left>-1.0 -1.0 -6.0</lower_left>
<upper_right>1.0 1.0 6.0</upper_right>
</volume_calc>
</settings>

42
tests/testing_harness.py
View file

@ -73,19 +73,19 @@ class TestHarness(object):
def _test_output_created(self):
"""Make sure statepoint.* and tallies.out have been created."""
statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))
statepoint = glob.glob(self._sp_name)
assert len(statepoint) == 1, 'Either multiple or no statepoint files' \
' exist.'
assert statepoint[0].endswith('h5'), \
'Statepoint file is not a HDF5 file.'
if self._tallies:
assert os.path.exists(os.path.join(os.getcwd(), 'tallies.out')), \
assert os.path.exists('tallies.out'), \
'Tally output file does not exist.'
def _get_results(self, hash_output=False):
"""Digest info in the statepoint and return as a string."""
# Read the statepoint file.
statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0]
statepoint = glob.glob(self._sp_name)[0]
sp = openmc.StatePoint(statepoint)
# Write out k-combined.
@ -133,11 +133,9 @@ class TestHarness(object):
def _cleanup(self):
"""Delete statepoints, tally, and test files."""
output = glob.glob(os.path.join(os.getcwd(), 'statepoint.*.h5'))
output.append(os.path.join(os.getcwd(), 'tallies.out'))
output.append(os.path.join(os.getcwd(), 'results_test.dat'))
output.append(os.path.join(os.getcwd(), 'summary.h5'))
output += glob.glob(os.path.join(os.getcwd(), 'volume_*.h5'))
output = glob.glob('statepoint.*.h5')
output += ['tallies.out', 'results_test.dat', 'summary.h5']
output += glob.glob('volume_*.h5')
for f in output:
if os.path.exists(f):
os.remove(f)
@ -157,7 +155,7 @@ class CMFDTestHarness(TestHarness):
def _get_results(self):
"""Digest info in the statepoint and return as a string."""
# Read the statepoint file.
statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0]
statepoint = glob.glob(self._sp_name)[0]
sp = openmc.StatePoint(statepoint)
# Write out the eigenvalue and tallies.
@ -206,7 +204,7 @@ class ParticleRestartTestHarness(TestHarness):
def _test_output_created(self):
"""Make sure the restart file has been created."""
particle = glob.glob(os.path.join(os.getcwd(), self._sp_name))
particle = glob.glob(self._sp_name)
assert len(particle) == 1, 'Either multiple or no particle restart ' \
'files exist.'
assert particle[0].endswith('h5'), \
@ -215,7 +213,7 @@ class ParticleRestartTestHarness(TestHarness):
def _get_results(self):
"""Digest info in the statepoint and return as a string."""
# Read the particle restart file.
particle = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0]
particle = glob.glob(self._sp_name)[0]
p = openmc.Particle(particle)
# Write out the properties.
@ -301,17 +299,10 @@ class PyAPITestHarness(TestHarness):
def _get_inputs(self):
"""Return a hash digest of the input XML files."""
xmls = ('geometry.xml', 'tallies.xml', 'materials.xml', 'settings.xml',
'plots.xml')
xmls = [os.path.join(os.getcwd(), fname) for fname in xmls]
outstr = '\n'.join([open(fname).read() for fname in xmls
if os.path.exists(fname)])
sha512 = hashlib.sha512()
sha512.update(outstr.encode('utf-8'))
outstr = sha512.hexdigest()
return outstr
xmls = ['geometry.xml', 'materials.xml', 'settings.xml',
'tallies.xml', 'plots.xml']
return ''.join([open(fname).read() for fname in xmls
if os.path.exists(fname)])
def _write_inputs(self, input_digest):
"""Write the digest of the input XMLs to an ASCII file."""
@ -336,11 +327,8 @@ class PyAPITestHarness(TestHarness):
def _cleanup(self):
"""Delete XMLs, statepoints, tally, and test files."""
super(PyAPITestHarness, self)._cleanup()
output = [os.path.join(os.getcwd(), 'materials.xml')]
output.append(os.path.join(os.getcwd(), 'geometry.xml'))
output.append(os.path.join(os.getcwd(), 'settings.xml'))
output.append(os.path.join(os.getcwd(), 'inputs_test.dat'))
output.append(os.path.join(os.getcwd(), 'summary.h5'))
output = ['materials.xml', 'geometry.xml', 'settings.xml',
'tallies.xml', 'inputs_test.dat']
for f in output:
if os.path.exists(f):
os.remove(f)