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Merge pull request #985 from paulromano/assorted-fixes

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Mesh filter bugfix and other minor changes
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Sterling Harper 2018-03-19 17:15:58 -04:00 • committed by GitHub
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15
docs/source/publications.rst
View file

@ -57,6 +57,11 @@ Benchmarking
Coupling and Multi-physics
--------------------------
- Jun Chen, Liangzhi Cao, Chuanqi Zhao, and Zhouyu Liu, "`Development of
Subchannel Code SUBSC for high-fidelity multi-physics coupling application
<https://doi.org/10.1016/j.egypro.2017.08.121>`_", Energy Procedia, **127**,
264-274 (2017).
- Tianliang Hu, Liangzhu Cao, Hongchun Wu, Xianan Du, and Mingtao He, "`Coupled
neutrons and thermal-hydraulics simulation of molten salt reactors based on
OpenMC/TANSY <https://doi.org/10.1016/j.anucene.2017.05.002>`_,"
@ -98,6 +103,11 @@ Coupling and Multi-physics
Geometry and Visualization
--------------------------
- Jin-Yang Li, Long Gu, Hu-Shan Xu, Nadezha Korepanova, Rui Yu, Yan-Lei Zhu, and
Chang-Ping Qin, "`CAD modeling study on FLUKA and OpenMC for accelerator
driven system simulation <https://doi.org/10.1016/j.anucene.2017.12.050>`_",
*Ann. Nucl. Energy*, **114**, 329-341 (2018).
- Logan Abel, William Boyd, Benoit Forget, and Kord Smith, "Interactive
Visualization of Multi-Group Cross Sections on High-Fidelity Spatial Meshes,"
*Trans. Am. Nucl. Soc.*, **114**, 391-394 (2016).
@ -114,6 +124,11 @@ Geometry and Visualization
Miscellaneous
-------------
- Bruno Merk, Dzianis Litskevich, R. Gregg, and A. R. Mount, "`Demand driven
salt clean-up in a molten salt fast reactor -- Defining a priority list
<https://doi.org/10.1371/journal.pone.0192020>`_", *PLOS One*, **13**,
e0192020 (2018).
- Adam G. Nelson, Samuel Shaner, William Boyd, and Paul K. Romano,
"Incorporation of a Multigroup Transport Capability in the OpenMC Monte Carlo
Particle Transport Code," *Trans. Am. Nucl. Soc.*, **117**, 679-681 (2017).

14
docs/source/usersguide/materials.rst
View file

@ -43,14 +43,22 @@ of an element, you specify the element itself. For example,
Internally, OpenMC stores data on the atomic masses and natural abundances of
all known isotopes and then uses this data to determine what isotopes should be
added to the material. When the material is later exported to XML for use by the
:ref:`scripts_openmc` executable, you'll see that any natural elements are
:ref:`scripts_openmc` executable, you'll see that any natural elements were
expanded to the naturally-occurring isotopes.
The :meth:`Material.add_element` method can also be used to add uranium at a
specified enrichment through the `enrichment` argument. For example, the
following would add 3.2% enriched uranium to a material::
mat.add_element('U', 1.0, enrichment=3.2)
In addition to U235 and U238, concentrations of U234 and U236 will be present
and are determined through a correlation based on measured data.
Often, cross section libraries don't actually have all naturally-occurring
isotopes for a given element. For example, in ENDF/B-VII.1, cross section
evaluations are given for O16 and O17 but not for O18. If OpenMC is aware of
what cross sections you will be using (either through the
:attr:`Materials.cross_sections` attribute or the
what cross sections you will be using (through the
:envvar:`OPENMC_CROSS_SECTIONS` environment variable), it will attempt to only
put isotopes in your model for which you have cross section data. In the case of
oxygen in ENDF/B-VII.1, the abundance of O18 would end up being lumped with O16.

2
openmc/capi/filter.py
View file

@ -128,7 +128,7 @@ class EnergyFilter(Filter):
self._index, len(energies), energies_p)
class EnergyoutFilter(Filter):
class EnergyoutFilter(EnergyFilter):
filter_type = 'energyout'

4
openmc/cell.py
View file

@ -295,7 +295,7 @@ class Cell(IDManagerMixin):
"""
if volume_calc.domain_type == 'cell':
if self.id in volume_calc.volumes:
self._volume = volume_calc.volumes[self.id][0]
self._volume = volume_calc.volumes[self.id].n
self._atoms = volume_calc.atoms[self.id]
else:
raise ValueError('No volume information found for this cell.')
@ -335,7 +335,7 @@ class Cell(IDManagerMixin):
volume = self.volume
for name, atoms in self._atoms.items():
nuclide = openmc.Nuclide(name)
density = 1.0e-24 * atoms[0]/volume # density in atoms/b-cm
density = 1.0e-24 * atoms.n/volume # density in atoms/b-cm
nuclides[name] = (nuclide, density)
else:
raise RuntimeError(

4
openmc/data/ace.py
View file

@ -22,7 +22,7 @@ import sys
import numpy as np
from openmc.mixin import EqualityMixin
from openmc.data.endf import ENDF_FLOAT_RE
from openmc.data.endf import _ENDF_FLOAT_RE
def ascii_to_binary(ascii_file, binary_file):
"""Convert an ACE file in ASCII format (type 1) to binary format (type 2).
@ -349,7 +349,7 @@ class Library(EqualityMixin):
# after it). If it's too short, then we apply the ENDF float regular
# expression. We don't do this by default because it's expensive!
if xss.size != nxs[1] + 1:
datastr = ENDF_FLOAT_RE.sub(r'\1e\2', datastr)
datastr = _ENDF_FLOAT_RE.sub(r'\1e\2', datastr)
xss = np.fromstring(datastr, sep=' ')
assert xss.size == nxs[1] + 1

34
openmc/data/data.py
View file

@ -1,10 +1,9 @@
import itertools
from math import sqrt
import os
import re
from warnings import warn
from numpy import sqrt
# Isotopic abundances from Meija J, Coplen T B, et al, "Isotopic compositions
# of the elements 2013 (IUPAC Technical Report)", Pure. Appl. Chem. 88 (3),
@ -136,23 +135,24 @@ ATOMIC_NUMBER = {value: key for key, value in ATOMIC_SYMBOL.items()}
_ATOMIC_MASS = {}
_GND_NAME_RE = re.compile(r'([A-Zn][a-z]*)(\d+)((?:_[em]\d+)?)')
def atomic_mass(isotope):
"""Return atomic mass of isotope in atomic mass units.
Atomic mass data comes from the Atomic Mass Evaluation 2012, published in
Chinese Physics C 36 (2012), 1287--1602.
Atomic mass data comes from the `Atomic Mass Evaluation 2012
<https://www-nds.iaea.org/amdc/ame2012/AME2012-1.pdf>`_.
Parameters
----------
isotope : str
Name of isotope, e.g. 'Pu239'
Name of isotope, e.g., 'Pu239'
Returns
-------
float or None
Atomic mass of isotope in atomic mass units. If the isotope listed does
not have a known atomic mass, None is returned.
float
Atomic mass of isotope in [amu]
"""
if not _ATOMIC_MASS:
@ -183,7 +183,7 @@ def atomic_mass(isotope):
if '_' in isotope:
isotope = isotope[:isotope.find('_')]
return _ATOMIC_MASS.get(isotope.lower())
return _ATOMIC_MASS[isotope.lower()]
def atomic_weight(element):
@ -199,16 +199,19 @@ def atomic_weight(element):
Returns
-------
float or None
Atomic weight of element in atomic mass units. If the element listed does
not exist, None is returned.
float
Atomic weight of element in [amu]
"""
weight = 0.
for nuclide, abundance in NATURAL_ABUNDANCE.items():
if re.match(r'{}\d+'.format(element), nuclide):
weight += atomic_mass(nuclide) * abundance
return None if weight == 0. else weight
if weight > 0.:
return weight
else:
raise ValueError("No naturally-occurring isotopes for element '{}'."
.format(element))
def water_density(temperature, pressure=0.1013):
@ -234,7 +237,7 @@ def water_density(temperature, pressure=0.1013):
Returns
-------
float
Water density in units of [g / cm^3]
Water density in units of [g/cm^3]
"""
@ -352,8 +355,7 @@ def zam(name):
"""
try:
symbol, A, state = re.match(r'([A-Zn][a-z]*)(\d+)((?:_[em]\d+)?)',
name).groups()
symbol, A, state = _GND_NAME_RE.match(name).groups()
except AttributeError:
raise ValueError("'{}' does not appear to be a nuclide name in GND "
"format.".format(name))

5
openmc/data/decay.py
View file

@ -7,10 +7,7 @@ import re
from warnings import warn
import numpy as np
try:
from uncertainties import ufloat, unumpy, UFloat
except ImportError:
ufloat = UFloat = namedtuple('UFloat', ['nominal_value', 'std_dev'])
from uncertainties import ufloat, unumpy, UFloat
import openmc.checkvalue as cv
from openmc.mixin import EqualityMixin

4
openmc/data/endf.py
View file

@ -45,7 +45,7 @@ SUM_RULES = {1: [2, 3],
106: list(range(750, 800)),
107: list(range(800, 850))}
ENDF_FLOAT_RE = re.compile(r'([\s\-\+]?\d*\.\d+)([\+\-]\d+)')
_ENDF_FLOAT_RE = re.compile(r'([\s\-\+]?\d*\.\d+)([\+\-]\d+)')
def float_endf(s):
@ -68,7 +68,7 @@ def float_endf(s):
The number
"""
return float(ENDF_FLOAT_RE.sub(r'\1e\2', s))
return float(_ENDF_FLOAT_RE.sub(r'\1e\2', s))
def get_text_record(file_obj):

6
openmc/data/neutron.py
View file

@ -15,7 +15,7 @@ import h5py
from . import HDF5_VERSION, HDF5_VERSION_MAJOR
from .ace import Library, Table, get_table
from .data import ATOMIC_SYMBOL, K_BOLTZMANN, EV_PER_MEV
from .data import ATOMIC_SYMBOL, K_BOLTZMANN, EV_PER_MEV, gnd_name
from .endf import Evaluation, SUM_RULES, get_head_record, get_tab1_record
from .fission_energy import FissionEnergyRelease
from .function import Tabulated1D, Sum, ResonancesWithBackground
@ -93,9 +93,7 @@ def _get_metadata(zaid, metastable_scheme='nndc'):
# Determine name
element = ATOMIC_SYMBOL[Z]
name = '{}{}'.format(element, mass_number)
if metastable > 0:
name += '_m{}'.format(metastable)
name = gnd_name(Z, mass_number, metastable)
return (name, element, Z, mass_number, metastable)

50
openmc/filter.py
View file

@ -732,37 +732,40 @@ class MeshFilter(Filter):
# Filter bins for a mesh are an (x,y,z) tuple. Convert (x,y,z) to a
# single bin -- this is similar to subroutine mesh_indices_to_bin in
# openmc/src/mesh.F90.
if len(self.mesh.dimension) == 3:
n_dim = len(self.mesh.dimension)
if n_dim == 3:
i, j, k = filter_bin
nx, ny, nz = self.mesh.dimension
val = (filter_bin[0] - 1) * ny * nz + \
(filter_bin[1] - 1) * nz + \
(filter_bin[2] - 1)
else:
return (i - 1) + (j - 1)*nx + (k - 1)*nx*ny
elif n_dim == 2:
i, j, *_ = filter_bin
nx, ny = self.mesh.dimension
val = (filter_bin[0] - 1) * ny + \
(filter_bin[1] - 1)
return val
return (i - 1) + (j - 1)*nx
else:
return filter_bin[0] - 1
def get_bin(self, bin_index):
cv.check_type('bin_index', bin_index, Integral)
cv.check_greater_than('bin_index', bin_index, 0, equality=True)
cv.check_less_than('bin_index', bin_index, self.num_bins)
# Construct 3-tuple of x,y,z cell indices for a 3D mesh
if len(self.mesh.dimension) == 3:
n_dim = len(self.mesh.dimension)
if n_dim == 3:
# Construct 3-tuple of x,y,z cell indices for a 3D mesh
nx, ny, nz = self.mesh.dimension
x = bin_index / (ny * nz)
y = (bin_index - (x * ny * nz)) / nz
z = bin_index - (x * ny * nz) - (y * nz)
x = (bin_index % nx) + 1
y = (bin_index % (nx * ny)) // nx + 1
z = bin_index // (nx * ny) + 1
return (x, y, z)
# Construct 2-tuple of x,y cell indices for a 2D mesh
else:
elif n_dim == 2:
# Construct 2-tuple of x,y cell indices for a 2D mesh
nx, ny = self.mesh.dimension
x = bin_index / ny
y = bin_index - (x * ny)
x = (bin_index % nx) + 1
y = bin_index // nx + 1
return (x, y)
else:
return (bin_index + 1,)
def get_pandas_dataframe(self, data_size, stride, **kwargs):
"""Builds a Pandas DataFrame for the Filter's bins.
@ -802,9 +805,10 @@ class MeshFilter(Filter):
mesh_key = 'mesh {0}'.format(self.mesh.id)
# Find mesh dimensions - use 3D indices for simplicity
if len(self.mesh.dimension) == 3:
n_dim = len(self.mesh.dimension)
if n_dim == 3:
nx, ny, nz = self.mesh.dimension
elif len(self.mesh.dimension) == 2:
elif n_dim == 2:
nx, ny = self.mesh.dimension
nz = 1
else:
@ -813,7 +817,7 @@ class MeshFilter(Filter):
# Generate multi-index sub-column for x-axis
filter_bins = np.arange(1, nx + 1)
repeat_factor = ny * nz * stride
repeat_factor = stride
filter_bins = np.repeat(filter_bins, repeat_factor)
tile_factor = data_size // len(filter_bins)
filter_bins = np.tile(filter_bins, tile_factor)
@ -821,7 +825,7 @@ class MeshFilter(Filter):
# Generate multi-index sub-column for y-axis
filter_bins = np.arange(1, ny + 1)
repeat_factor = nz * stride
repeat_factor = nx * stride
filter_bins = np.repeat(filter_bins, repeat_factor)
tile_factor = data_size // len(filter_bins)
filter_bins = np.tile(filter_bins, tile_factor)
@ -829,7 +833,7 @@ class MeshFilter(Filter):
# Generate multi-index sub-column for z-axis
filter_bins = np.arange(1, nz + 1)
repeat_factor = stride
repeat_factor = nx * ny * stride
filter_bins = np.repeat(filter_bins, repeat_factor)
tile_factor = data_size // len(filter_bins)
filter_bins = np.tile(filter_bins, tile_factor)

59
openmc/material.py
View file

@ -88,7 +88,7 @@ class Material(IDManagerMixin):
self.name = name
self.temperature = temperature
self._density = None
self._density_units = ''
self._density_units = 'sum'
self._depletable = False
self._paths = None
self._num_instances = None
@ -313,7 +313,7 @@ class Material(IDManagerMixin):
"""
if volume_calc.domain_type == 'material':
if self.id in volume_calc.volumes:
self._volume = volume_calc.volumes[self.id][0]
self._volume = volume_calc.volumes[self.id].n
self._atoms = volume_calc.atoms[self.id]
else:
raise ValueError('No volume information found for this material.')
@ -379,33 +379,31 @@ class Material(IDManagerMixin):
Parameters
----------
nuclide : str
Nuclide to add
Nuclide to add, e.g., 'Mo95'
percent : float
Atom or weight percent
percent_type : {'ao', 'wo'}
'ao' for atom percent and 'wo' for weight percent
"""
cv.check_type('nuclide', nuclide, str)
cv.check_type('percent', percent, Real)
cv.check_value('percent type', percent_type, {'ao', 'wo'})
if self._macroscopic is not None:
msg = 'Unable to add a Nuclide to Material ID="{}" as a ' \
'macroscopic data-set has already been added'.format(self._id)
raise ValueError(msg)
if not isinstance(nuclide, str):
msg = 'Unable to add a Nuclide to Material ID="{}" with a ' \
'non-string value "{}"'.format(self._id, nuclide)
raise ValueError(msg)
elif not isinstance(percent, Real):
msg = 'Unable to add a Nuclide to Material ID="{}" with a ' \
'non-floating point value "{}"'.format(self._id, percent)
raise ValueError(msg)
elif percent_type not in ('ao', 'wo'):
msg = 'Unable to add a Nuclide to Material ID="{}" with a ' \
'percent type "{}"'.format(self._id, percent_type)
raise ValueError(msg)
# If nuclide name doesn't look valid, give a warning
try:
Z, _, _ = openmc.data.zam(nuclide)
except ValueError as e:
warnings.warn(str(e))
else:
# For actinides, have the material be depletable by default
if Z >= 89:
self.depletable = True
self._nuclides.append((nuclide, percent, percent_type))
@ -493,7 +491,7 @@ class Material(IDManagerMixin):
Parameters
----------
element : str
Element to add
Element to add, e.g., 'Zr'
percent : float
Atom or weight percent
percent_type : {'ao', 'wo'}, optional
@ -505,27 +503,15 @@ class Material(IDManagerMixin):
(natural composition).
"""
cv.check_type('nuclide', element, str)
cv.check_type('percent', percent, Real)
cv.check_value('percent type', percent_type, {'ao', 'wo'})
if self._macroscopic is not None:
msg = 'Unable to add an Element to Material ID="{}" as a ' \
'macroscopic data-set has already been added'.format(self._id)
raise ValueError(msg)
if not isinstance(element, str):
msg = 'Unable to add an Element to Material ID="{}" with a ' \
'non-string value "{}"'.format(self._id, element)
raise ValueError(msg)
if not isinstance(percent, Real):
msg = 'Unable to add an Element to Material ID="{}" with a ' \
'non-floating point value "{}"'.format(self._id, percent)
raise ValueError(msg)
if percent_type not in ['ao', 'wo']:
msg = 'Unable to add an Element to Material ID="{}" with a ' \
'percent type "{}"'.format(self._id, percent_type)
raise ValueError(msg)
if enrichment is not None:
if not isinstance(enrichment, Real):
msg = 'Unable to add an Element to Material ID="{}" with a ' \
@ -551,10 +537,15 @@ class Material(IDManagerMixin):
format(enrichment, self._id)
warnings.warn(msg)
# Make sure element name is just that
if not element.isalpha():
raise ValueError("Element name should be given by the "
"element's symbol, e.g., 'Zr'")
# Add naturally-occuring isotopes
element = openmc.Element(element)
for nuclide in element.expand(percent, percent_type, enrichment):
self._nuclides.append(nuclide)
self.add_nuclide(*nuclide)
def add_s_alpha_beta(self, name, fraction=1.0):
r"""Add an :math:`S(\alpha,\beta)` table to the material

18
openmc/mesh.py
View file

@ -82,6 +82,24 @@ class Mesh(IDManagerMixin):
def num_mesh_cells(self):
return np.prod(self._dimension)
@property
def indices(self):
ndim = len(self._dimension)
if ndim == 3:
nx, ny, nz = self.dimension
return ((x, y, z)
for z in range(1, nz + 1)
for y in range(1, ny + 1)
for x in range(1, nx + 1))
elif ndim == 2:
nx, ny = self.dimension
return ((x, y)
for y in range(1, ny + 1)
for x in range(1, nx + 1))
else:
nx, = self.dimension
return ((x,) for x in range(1, nx + 1))
@name.setter
def name(self, name):
if name is not None:

2
openmc/mgxs/library.py
View file

@ -587,7 +587,7 @@ class Library(object):
self._nuclides = statepoint.summary.nuclides
if statepoint.run_mode == 'eigenvalue':
self._keff = statepoint.k_combined[0]
self._keff = statepoint.k_combined.n
# Load tallies for each MGXS for each domain and mgxs type
for domain in self.domains:

16
openmc/mgxs/mgxs.py
View file

@ -4,7 +4,6 @@ import warnings
import os
import copy
from abc import ABCMeta
import itertools
import numpy as np
import h5py
@ -937,8 +936,7 @@ class MGXS(metaclass=ABCMeta):
# NOTE: This is important if tally merging was used
if self.domain_type == 'mesh':
filters = [_DOMAIN_TO_FILTER[self.domain_type]]
xyz = [range(1, x + 1) for x in self.domain.dimension]
filter_bins = [tuple(itertools.product(*xyz))]
filter_bins = [tuple(self.domain.indices)]
elif self.domain_type != 'distribcell':
filters = [_DOMAIN_TO_FILTER[self.domain_type]]
filter_bins = [(self.domain.id,)]
@ -1531,8 +1529,7 @@ class MGXS(metaclass=ABCMeta):
elif self.domain_type == 'distribcell':
subdomains = np.arange(self.num_subdomains, dtype=np.int)
elif self.domain_type == 'mesh':
xyz = [range(1, x + 1) for x in self.domain.dimension]
subdomains = list(itertools.product(*xyz))
subdomains = list(self.domain.indices)
else:
subdomains = [self.domain.id]
@ -1702,8 +1699,7 @@ class MGXS(metaclass=ABCMeta):
domain_filter = self.xs_tally.find_filter('sum(distribcell)')
subdomains = domain_filter.bins
elif self.domain_type == 'mesh':
xyz = [range(1, x+1) for x in self.domain.dimension]
subdomains = list(itertools.product(*xyz))
subdomains = list(self.domain.indices)
else:
subdomains = [self.domain.id]
@ -2342,8 +2338,7 @@ class MatrixMGXS(MGXS):
elif self.domain_type == 'distribcell':
subdomains = np.arange(self.num_subdomains, dtype=np.int)
elif self.domain_type == 'mesh':
xyz = [range(1, x + 1) for x in self.domain.dimension]
subdomains = list(itertools.product(*xyz))
subdomains = list(self.domain.indices)
else:
subdomains = [self.domain.id]
@ -4530,8 +4525,7 @@ class ScatterMatrixXS(MatrixMGXS):
elif self.domain_type == 'distribcell':
subdomains = np.arange(self.num_subdomains, dtype=np.int)
elif self.domain_type == 'mesh':
xyz = [range(1, x + 1) for x in self.domain.dimension]
subdomains = list(itertools.product(*xyz))
subdomains = list(self.domain.indices)
else:
subdomains = [self.domain.id]

2
openmc/model/model.py
View file

@ -210,7 +210,7 @@ class Model(object):
Returns
-------
2-tuple of float
uncertainties.UFloat
Combined estimator of k-effective from the statepoint
"""

44
openmc/plots.py
View file

@ -1,6 +1,7 @@
from collections.abc import Iterable, Mapping
from numbers import Real, Integral
from xml.etree import ElementTree as ET
import subprocess
import sys
import warnings
@ -650,6 +651,49 @@ class Plot(IDManagerMixin):
return element
def to_ipython_image(self, openmc_exec='openmc', cwd='.',
convert_exec='convert'):
"""Render plot as an image
This method runs OpenMC in plotting mode to produce a bitmap image which
is then converted to a .png file and loaded in as an
:class:`IPython.display.Image` object. As such, it requires that your
model geometry, materials, and settings have already been exported to
XML.
Parameters
----------
openmc_exec : str
Path to OpenMC executable
cwd : str, optional
Path to working directory to run in
convert_exec : str, optional
Command that can convert PPM files into PNG files
Returns
-------
IPython.display.Image
Image generated
"""
from IPython.display import Image
# Create plots.xml
Plots([self]).export_to_xml()
# Run OpenMC in geometry plotting mode
openmc.plot_geometry(False, openmc_exec, cwd)
# Convert to .png
if self.filename is not None:
ppm_file = '{}.ppm'.format(self.filename)
else:
ppm_file = 'plot_{}.ppm'.format(self.id)
png_file = ppm_file.replace('.ppm', '.png')
subprocess.check_call([convert_exec, ppm_file, png_file])
return Image(png_file)
class Plots(cv.CheckedList):
"""Collection of Plots used for an OpenMC simulation.

3
openmc/plotter.py
View file

@ -2,7 +2,6 @@ from numbers import Integral, Real
from itertools import chain
import string
import matplotlib.pyplot as plt
import numpy as np
import openmc.checkvalue as cv
@ -125,6 +124,8 @@ def plot_xs(this, types, divisor_types=None, temperature=294., data_type=None,
generated.
"""
import matplotlib.pyplot as plt
cv.check_type("plot_CE", plot_CE, bool)
if data_type is None:

4
openmc/search.py
View file

@ -60,9 +60,9 @@ def _search_keff(guess, target, model_builder, model_args, print_iterations,
if print_iterations:
text = 'Iteration: {}; Guess of {:.2e} produced a keff of ' + \
'{:1.5f} +/- {:1.5f}'
print(text.format(len(guesses), guess, keff[0], keff[1]))
print(text.format(len(guesses), guess, keff.n, keff.s))
return (keff[0] - target)
return keff.n - target
def search_for_keff(model_builder, initial_guess=None, target=1.0,

17
openmc/statepoint.py
View file

@ -1,3 +1,4 @@
from datetime import datetime
import re
import os
import warnings
@ -5,6 +6,7 @@ import glob
import numpy as np
import h5py
from uncertainties import ufloat
import openmc
import openmc.checkvalue as cv
@ -47,8 +49,8 @@ class StatePoint(object):
CMFD fission source distribution over all mesh cells and energy groups.
current_batch : int
Number of batches simulated
date_and_time : str
Date and time when simulation began
date_and_time : datetime.datetime
Date and time at which statepoint was written
entropy : numpy.ndarray
Shannon entropy of fission source at each batch
filters : dict
@ -59,8 +61,8 @@ class StatePoint(object):
global_tallies : numpy.ndarray of compound datatype
Global tallies for k-effective estimates and leakage. The compound
datatype has fields 'name', 'sum', 'sum_sq', 'mean', and 'std_dev'.
k_combined : list
Combined estimator for k-effective and its uncertainty
k_combined : uncertainties.UFloat
Combined estimator for k-effective
k_col_abs : float
Cross-product of collision and absorption estimates of k-effective
k_col_tra : float
@ -187,7 +189,8 @@ class StatePoint(object):
@property
def date_and_time(self):
return self._f.attrs['date_and_time'].decode()
s = self._f.attrs['date_and_time'].decode()
return datetime.strptime(s, '%Y-%m-%d %H:%M:%S')
@property
def entropy(self):
@ -255,7 +258,7 @@ class StatePoint(object):
@property
def k_combined(self):
if self.run_mode == 'eigenvalue':
return self._f['k_combined'].value
return ufloat(*self._f['k_combined'].value)
else:
return None
@ -457,7 +460,7 @@ class StatePoint(object):
@property
def version(self):
return tuple(self._f.attrs['version'])
return tuple(self._f.attrs['openmc_version'])
@property
def summary(self):

19
openmc/tallies.py
View file

@ -1164,9 +1164,7 @@ class Tally(IDManagerMixin):
if not user_filter:
# Create list of 2- or 3-tuples tuples for mesh cell bins
if isinstance(self_filter, openmc.MeshFilter):
dimension = self_filter.mesh.dimension
xyz = [range(1, x+1) for x in dimension]
bins = list(product(*xyz))
bins = list(self_filter.mesh.indices)
# Create list of 2-tuples for energy boundary bins
elif isinstance(self_filter, (openmc.EnergyFilter,
@ -1676,19 +1674,22 @@ class Tally(IDManagerMixin):
new_tally._std_dev = np.sqrt(data['self']['std. dev.']**2 +
data['other']['std. dev.']**2)
elif binary_op == '*':
self_rel_err = data['self']['std. dev.'] / data['self']['mean']
other_rel_err = data['other']['std. dev.'] / data['other']['mean']
with np.errstate(divide='ignore', invalid='ignore'):
self_rel_err = data['self']['std. dev.'] / data['self']['mean']
other_rel_err = data['other']['std. dev.'] / data['other']['mean']
new_tally._mean = data['self']['mean'] * data['other']['mean']
new_tally._std_dev = np.abs(new_tally.mean) * \
np.sqrt(self_rel_err**2 + other_rel_err**2)
elif binary_op == '/':
self_rel_err = data['self']['std. dev.'] / data['self']['mean']
other_rel_err = data['other']['std. dev.'] / data['other']['mean']
new_tally._mean = data['self']['mean'] / data['other']['mean']
with np.errstate(divide='ignore', invalid='ignore'):
self_rel_err = data['self']['std. dev.'] / data['self']['mean']
other_rel_err = data['other']['std. dev.'] / data['other']['mean']
new_tally._mean = data['self']['mean'] / data['other']['mean']
new_tally._std_dev = np.abs(new_tally.mean) * \
np.sqrt(self_rel_err**2 + other_rel_err**2)
elif binary_op == '^':
mean_ratio = data['other']['mean'] / data['self']['mean']
with np.errstate(divide='ignore', invalid='ignore'):
mean_ratio = data['other']['mean'] / data['self']['mean']
first_term = mean_ratio * data['self']['std. dev.']
second_term = \
np.log(data['self']['mean']) * data['other']['std. dev.']

31
openmc/universe.py
View file

@ -4,7 +4,6 @@ from numbers import Integral, Real
import random
import sys
import matplotlib.pyplot as plt
import numpy as np
import openmc
@ -146,7 +145,7 @@ class Universe(IDManagerMixin):
"""
if volume_calc.domain_type == 'universe':
if self.id in volume_calc.volumes:
self._volume = volume_calc.volumes[self.id][0]
self._volume = volume_calc.volumes[self.id].n
self._atoms = volume_calc.atoms[self.id]
else:
raise ValueError('No volume information found for this universe.')
@ -184,10 +183,14 @@ class Universe(IDManagerMixin):
return []
def plot(self, origin=(0., 0., 0.), width=(1., 1.), pixels=(200, 200),
basis='xy', color_by='cell', colors=None, filename=None, seed=None,
basis='xy', color_by='cell', colors=None, seed=None,
**kwargs):
"""Display a slice plot of the universe.
To display or save the plot, call :func:`matplotlib.pyplot.show` or
:func:`matplotlib.pyplot.savefig`. In a Jupyter notebook, enabling the
matplotlib inline backend will show the plot inline.
Parameters
----------
origin : Iterable of float
@ -212,9 +215,6 @@ class Universe(IDManagerMixin):
water = openmc.Cell(fill=h2o)
universe.plot(..., colors={water: (0., 0., 1.))
filename : str or None
Filename to save plot to. If no filename is given, the plot will be
displayed using the currently enabled matplotlib backend.
seed : hashable object or None
Hashable object which is used to seed the random number generator
used to select colors. If None, the generator is seeded from the
@ -223,7 +223,14 @@ class Universe(IDManagerMixin):
All keyword arguments are passed to
:func:`matplotlib.pyplot.imshow`.
Returns
-------
matplotlib.image.AxesImage
Resulting image
"""
import matplotlib.pyplot as plt
# Seed the random number generator
if seed is not None:
random.seed(seed)
@ -298,14 +305,8 @@ class Universe(IDManagerMixin):
img[j, i, :] = colors[obj]
# Display image
plt.imshow(img, extent=(x_min, x_max, y_min, y_max),
interpolation='nearest', **kwargs)
# Show or save the plot
if filename is None:
plt.show()
else:
plt.savefig(filename)
return plt.imshow(img, extent=(x_min, x_max, y_min, y_max),
interpolation='nearest', **kwargs)
def add_cell(self, cell):
"""Add a cell to the universe.
@ -405,7 +406,7 @@ class Universe(IDManagerMixin):
volume = self.volume
for name, atoms in self._atoms.items():
nuclide = openmc.Nuclide(name)
density = 1.0e-24 * atoms[0]/volume # density in atoms/b-cm
density = 1.0e-24 * atoms.n/volume # density in atoms/b-cm
nuclides[name] = (nuclide, density)
else:
raise RuntimeError(

10
openmc/volume.py
View file

@ -7,6 +7,7 @@ import warnings
import numpy as np
import pandas as pd
import h5py
from uncertainties import ufloat
import openmc
import openmc.checkvalue as cv
@ -137,11 +138,10 @@ class VolumeCalculation(object):
@property
def atoms_dataframe(self):
items = []
columns = [self.domain_type.capitalize(), 'Nuclide', 'Atoms',
'Uncertainty']
columns = [self.domain_type.capitalize(), 'Nuclide', 'Atoms']
for uid, atoms_dict in self.atoms.items():
for name, atoms in atoms_dict.items():
items.append((uid, name, atoms[0], atoms[1]))
items.append((uid, name, atoms))
return pd.DataFrame.from_records(items, columns=columns)
@ -211,13 +211,13 @@ class VolumeCalculation(object):
domain_id = int(obj_name[7:])
ids.append(domain_id)
group = f[obj_name]
volume = tuple(group['volume'].value)
volume = ufloat(*group['volume'].value)
nucnames = group['nuclides'].value
atoms_ = group['atoms'].value
atom_dict = OrderedDict()
for name_i, atoms_i in zip(nucnames, atoms_):
atom_dict[name_i.decode()] = tuple(atoms_i)
atom_dict[name_i.decode()] = ufloat(*atoms_i)
volumes[domain_id] = volume
atoms[domain_id] = atom_dict

2
scripts/openmc-get-jeff-data
View file

@ -41,7 +41,7 @@ parser.add_argument('-b', '--batch', action='store_true',
parser.add_argument('-d', '--destination', default='jeff-3.2-hdf5',
help='Directory to create new library in')
parser.add_argument('--libver', choices=['earliest', 'latest'],
default='earliest', help="Output HDF5 versioning. Use "
default='latest', help="Output HDF5 versioning. Use "
"'earliest' for backwards compatibility or 'latest' for "
"performance")
args = parser.parse_args()

4
src/output.F90
View file

@ -165,12 +165,12 @@ contains
subroutine print_version()
if (master) then
write(UNIT=OUTPUT_UNIT, FMT='(1X,A,1X,I1,".",I1,".",I1)') &
write(UNIT=OUTPUT_UNIT, FMT='(1X,A,1X,I1,".",I2,".",I1)') &
"OpenMC version", VERSION_MAJOR, VERSION_MINOR, VERSION_RELEASE
#ifdef GIT_SHA1
write(UNIT=OUTPUT_UNIT, FMT='(1X,A,A)') "Git SHA1: ", GIT_SHA1
#endif
write(UNIT=OUTPUT_UNIT, FMT=*) "Copyright (c) 2011-2015 &
write(UNIT=OUTPUT_UNIT, FMT=*) "Copyright (c) 2011-2018 &
&Massachusetts Institute of Technology"
write(UNIT=OUTPUT_UNIT, FMT=*) "MIT/X license at &
&<http://openmc.readthedocs.io/en/latest/license.html>"

9
src/tallies/tally_filter_energy.F90
View file

@ -211,6 +211,10 @@ contains
energies = C_LOC(f % bins)
n = size(f % bins)
err = 0
type is (EnergyoutFilter)
energies = C_LOC(f % bins)
n = size(f % bins)
err = 0
class default
err = E_INVALID_TYPE
call set_errmsg("Tried to get energy bins on a non-energy filter.")
@ -242,6 +246,11 @@ contains
if (allocated(f % bins)) deallocate(f % bins)
allocate(f % bins(n))
f % bins(:) = energies
type is (EnergyoutFilter)
f % n_bins = n - 1
if (allocated(f % bins)) deallocate(f % bins)
allocate(f % bins(n))
f % bins(:) = energies
class default
err = E_INVALID_TYPE
call set_errmsg("Tried to get energy bins on a non-energy filter.")

2
tests/regression_tests/asymmetric_lattice/inputs_true.dat
View file

@ -56,7 +56,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />

2
tests/regression_tests/create_fission_neutrons/inputs_true.dat
View file

@ -10,7 +10,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="mat">
<material depletable="true" id="1" name="mat">
<density units="atom/b-cm" value="0.069335" />
<nuclide ao="40.0" name="H1" />
<nuclide ao="1.0" name="U235" />

2
tests/regression_tests/diff_tally/inputs_true.dat
View file

@ -148,7 +148,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />

4
tests/regression_tests/distribmat/inputs_true.dat
View file

@ -26,11 +26,11 @@
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
<material id="2">
<material depletable="true" id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="3">
<material depletable="true" id="3">
<density units="g/cc" value="2.0" />
<nuclide ao="1.0" name="U235" />
</material>

4
tests/regression_tests/entropy/test.py
View file

@ -14,11 +14,11 @@ class EntropyTestHarness(TestHarness):
with StatePoint(statepoint) as sp:
# Write out k-combined.
outstr = 'k-combined:\n'
outstr += '{0:12.6E} {1:12.6E}\n'.format(*sp.k_combined)
outstr += '{:12.6E} {:12.6E}\n'.format(sp.k_combined.n, sp.k_combined.s)
# Write out entropy data.
outstr += 'entropy:\n'
results = ['{0:12.6E}'.format(x) for x in sp.entropy]
results = ['{:12.6E}'.format(x) for x in sp.entropy]
outstr += '\n'.join(results) + '\n'
return outstr

4
tests/regression_tests/filter_energyfun/inputs_true.dat
View file

@ -148,7 +148,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
@ -156,7 +156,7 @@
<nuclide ao="1.0801e-08" name="Xe135" />
<nuclide ao="0.045737" name="O16" />
</material>
<material id="2" name="Zircaloy">
<material depletable="true" id="2" name="Zircaloy">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />

2
tests/regression_tests/filter_mesh/inputs_true.dat
View file

@ -148,7 +148,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />

2
tests/regression_tests/fixed_source/inputs_true.dat
View file

@ -5,7 +5,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1">
<material depletable="true" id="1">
<density units="g/cc" value="7.5" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.0001" name="U238" />

2
tests/regression_tests/iso_in_lab/inputs_true.dat
View file

@ -148,7 +148,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />

4
tests/regression_tests/mg_convert/test.py
View file

@ -144,8 +144,8 @@ class MGXSTestHarness(PyAPITestHarness):
with openmc.StatePoint('statepoint.{}.h5'.format(batches)) as sp:
# Write out k-combined.
outstr += 'k-combined:\n'
form = '{0:12.6E} {1:12.6E}\n'
outstr += form.format(sp.k_combined[0], sp.k_combined[1])
form = '{:12.6E} {:12.6E}\n'
outstr += form.format(sp.k_combined.n, sp.k_combined.s)
return outstr

2
tests/regression_tests/mgxs_library_ce_to_mg/inputs_true.dat
View file

@ -12,7 +12,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UO2 (2.4%)">
<material depletable="true" id="1" name="UO2 (2.4%)">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />

2
tests/regression_tests/mgxs_library_condense/inputs_true.dat
View file

@ -12,7 +12,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UO2 (2.4%)">
<material depletable="true" id="1" name="UO2 (2.4%)">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />

2
tests/regression_tests/mgxs_library_distribcell/inputs_true.dat
View file

@ -39,7 +39,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="Fuel">
<material depletable="true" id="1" name="Fuel">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />

2
tests/regression_tests/mgxs_library_hdf5/inputs_true.dat
View file

@ -12,7 +12,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UO2 (2.4%)">
<material depletable="true" id="1" name="UO2 (2.4%)">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />

2
tests/regression_tests/mgxs_library_mesh/inputs_true.dat
View file

@ -148,7 +148,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />

256
tests/regression_tests/mgxs_library_mesh/results_true.dat
View file

@ -1,62 +1,62 @@
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.762544 0.085298
1 1 2 1 1 total 0.653375 0.153317
2 2 1 1 1 total 0.644837 0.088457
2 1 2 1 1 total 0.644837 0.088457
1 2 1 1 1 total 0.653375 0.153317
3 2 2 1 1 total 0.676480 0.094215
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.473988 0.088732
1 1 2 1 1 total 0.379821 0.167092
2 2 1 1 1 total 0.399254 0.091318
2 1 2 1 1 total 0.399254 0.091318
1 2 1 1 1 total 0.379821 0.167092
3 2 2 1 1 total 0.424265 0.099551
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.473988 0.088732
1 1 2 1 1 total 0.379821 0.167092
2 2 1 1 1 total 0.399254 0.091318
2 1 2 1 1 total 0.399254 0.091318
1 2 1 1 1 total 0.379821 0.167092
3 2 2 1 1 total 0.424265 0.099551
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.027288 0.005813
1 1 2 1 1 total 0.019449 0.004420
2 2 1 1 1 total 0.020262 0.003701
2 1 2 1 1 total 0.020262 0.003701
1 2 1 1 1 total 0.019449 0.004420
3 2 2 1 1 total 0.021266 0.002869
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.016037 0.006339
1 1 2 1 1 total 0.012153 0.003804
2 2 1 1 1 total 0.013018 0.003521
2 1 2 1 1 total 0.013018 0.003521
1 2 1 1 1 total 0.012153 0.003804
3 2 2 1 1 total 0.012965 0.002454
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.011251 0.003050
1 1 2 1 1 total 0.007296 0.001795
2 2 1 1 1 total 0.007243 0.001219
2 1 2 1 1 total 0.007243 0.001219
1 2 1 1 1 total 0.007296 0.001795
3 2 2 1 1 total 0.008301 0.001066
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.027498 0.007445
1 1 2 1 1 total 0.017912 0.004426
2 2 1 1 1 total 0.017954 0.003077
2 1 2 1 1 total 0.017954 0.003077
1 2 1 1 1 total 0.017912 0.004426
3 2 2 1 1 total 0.020469 0.002617
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 2.177345e+06 589804.299388
1 1 2 1 1 total 1.413154e+06 347806.623417
2 2 1 1 1 total 1.404096e+06 236476.851953
2 1 2 1 1 total 1.404096e+06 236476.851953
1 2 1 1 1 total 1.413154e+06 347806.623417
3 2 2 1 1 total 1.608259e+06 206502.707865
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.735256 0.080216
1 1 2 1 1 total 0.633925 0.149098
2 2 1 1 1 total 0.624575 0.084974
2 1 2 1 1 total 0.624575 0.084974
1 2 1 1 1 total 0.633925 0.149098
3 2 2 1 1 total 0.655214 0.091422
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.763779 0.070696
1 1 2 1 1 total 0.640809 0.158369
2 2 1 1 1 total 0.628158 0.064356
2 1 2 1 1 total 0.628158 0.064356
1 2 1 1 1 total 0.640809 0.158369
3 2 2 1 1 total 0.645171 0.080467
mesh 1 group in group out nuclide moment mean std. dev.
x y z
@ -64,14 +64,14 @@
1 1 1 1 1 1 total P1 0.288556 0.024446
2 1 1 1 1 1 total P2 0.082441 0.011443
3 1 1 1 1 1 total P3 -0.005627 0.012638
4 1 2 1 1 1 total P0 0.640809 0.158369
5 1 2 1 1 1 total P1 0.273553 0.066437
6 1 2 1 1 1 total P2 0.108446 0.024435
7 1 2 1 1 1 total P3 0.012229 0.003785
8 2 1 1 1 1 total P0 0.628158 0.064356
9 2 1 1 1 1 total P1 0.245583 0.022676
10 2 1 1 1 1 total P2 0.086370 0.007833
11 2 1 1 1 1 total P3 0.019590 0.005345
8 1 2 1 1 1 total P0 0.628158 0.064356
9 1 2 1 1 1 total P1 0.245583 0.022676
10 1 2 1 1 1 total P2 0.086370 0.007833
11 1 2 1 1 1 total P3 0.019590 0.005345
4 2 1 1 1 1 total P0 0.640809 0.158369
5 2 1 1 1 1 total P1 0.273553 0.066437
6 2 1 1 1 1 total P2 0.108446 0.024435
7 2 1 1 1 1 total P3 0.012229 0.003785
12 2 2 1 1 1 total P0 0.645171 0.080467
13 2 2 1 1 1 total P1 0.252215 0.032154
14 2 2 1 1 1 total P2 0.089251 0.009734
@ -82,14 +82,14 @@
1 1 1 1 1 1 total P1 0.288556 0.024446
2 1 1 1 1 1 total P2 0.082441 0.011443
3 1 1 1 1 1 total P3 -0.005627 0.012638
4 1 2 1 1 1 total P0 0.640809 0.158369
5 1 2 1 1 1 total P1 0.273553 0.066437
6 1 2 1 1 1 total P2 0.108446 0.024435
7 1 2 1 1 1 total P3 0.012229 0.003785
8 2 1 1 1 1 total P0 0.628158 0.064356
9 2 1 1 1 1 total P1 0.245583 0.022676
10 2 1 1 1 1 total P2 0.086370 0.007833
11 2 1 1 1 1 total P3 0.019590 0.005345
8 1 2 1 1 1 total P0 0.628158 0.064356
9 1 2 1 1 1 total P1 0.245583 0.022676
10 1 2 1 1 1 total P2 0.086370 0.007833
11 1 2 1 1 1 total P3 0.019590 0.005345
4 2 1 1 1 1 total P0 0.640809 0.158369
5 2 1 1 1 1 total P1 0.273553 0.066437
6 2 1 1 1 1 total P2 0.108446 0.024435
7 2 1 1 1 1 total P3 0.012229 0.003785
12 2 2 1 1 1 total P0 0.645171 0.080467
13 2 2 1 1 1 total P1 0.252215 0.032154
14 2 2 1 1 1 total P2 0.089251 0.009734
@ -97,20 +97,20 @@
mesh 1 group in group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 1.0 0.108337
1 1 2 1 1 1 total 1.0 0.238517
2 2 1 1 1 1 total 1.0 0.113128
2 1 2 1 1 1 total 1.0 0.113128
1 2 1 1 1 1 total 1.0 0.238517
3 2 2 1 1 1 total 1.0 0.132597
mesh 1 group in group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 0.015584 0.003404
1 1 2 1 1 1 total 0.014200 0.003676
2 2 1 1 1 1 total 0.017684 0.002499
2 1 2 1 1 1 total 0.017684 0.002499
1 2 1 1 1 1 total 0.014200 0.003676
3 2 2 1 1 1 total 0.022409 0.002481
mesh 1 group in group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 1.0 0.108337
1 1 2 1 1 1 total 1.0 0.238517
2 2 1 1 1 1 total 1.0 0.113128
2 1 2 1 1 1 total 1.0 0.113128
1 2 1 1 1 1 total 1.0 0.238517
3 2 2 1 1 1 total 1.0 0.132597
mesh 1 group in group out nuclide moment mean std. dev.
x y z
@ -118,14 +118,14 @@
1 1 1 1 1 1 total P1 0.277780 0.041434
2 1 1 1 1 1 total P2 0.079362 0.014706
3 1 1 1 1 1 total P3 -0.005417 0.012184
4 1 2 1 1 1 total P0 0.633925 0.212349
5 1 2 1 1 1 total P1 0.270615 0.089799
6 1 2 1 1 1 total P2 0.107281 0.034246
7 1 2 1 1 1 total P3 0.012098 0.004637
8 2 1 1 1 1 total P0 0.624575 0.110512
9 2 1 1 1 1 total P1 0.244182 0.041824
10 2 1 1 1 1 total P2 0.085877 0.014634
11 2 1 1 1 1 total P3 0.019478 0.006012
8 1 2 1 1 1 total P0 0.624575 0.110512
9 1 2 1 1 1 total P1 0.244182 0.041824
10 1 2 1 1 1 total P2 0.085877 0.014634
11 1 2 1 1 1 total P3 0.019478 0.006012
4 2 1 1 1 1 total P0 0.633925 0.212349
5 2 1 1 1 1 total P1 0.270615 0.089799
6 2 1 1 1 1 total P2 0.107281 0.034246
7 2 1 1 1 1 total P3 0.012098 0.004637
12 2 2 1 1 1 total P0 0.655214 0.126119
13 2 2 1 1 1 total P1 0.256141 0.049765
14 2 2 1 1 1 total P2 0.090641 0.016563
@ -136,14 +136,14 @@
1 1 1 1 1 1 total P1 0.277780 0.051210
2 1 1 1 1 1 total P2 0.079362 0.017035
3 1 1 1 1 1 total P3 -0.005417 0.012198
4 1 2 1 1 1 total P0 0.633925 0.260681
5 1 2 1 1 1 total P1 0.270615 0.110590
6 1 2 1 1 1 total P2 0.107281 0.042750
7 1 2 1 1 1 total P3 0.012098 0.005462
8 2 1 1 1 1 total P0 0.624575 0.131169
9 2 1 1 1 1 total P1 0.244182 0.050123
10 2 1 1 1 1 total P2 0.085877 0.017565
11 2 1 1 1 1 total P3 0.019478 0.006403
8 1 2 1 1 1 total P0 0.624575 0.131169
9 1 2 1 1 1 total P1 0.244182 0.050123
10 1 2 1 1 1 total P2 0.085877 0.017565
11 1 2 1 1 1 total P3 0.019478 0.006403
4 2 1 1 1 1 total P0 0.633925 0.260681
5 2 1 1 1 1 total P1 0.270615 0.110590
6 2 1 1 1 1 total P2 0.107281 0.042750
7 2 1 1 1 1 total P3 0.012098 0.005462
12 2 2 1 1 1 total P0 0.655214 0.153147
13 2 2 1 1 1 total P1 0.256141 0.060250
14 2 2 1 1 1 total P2 0.090641 0.020464
@ -151,32 +151,32 @@
mesh 1 group out nuclide mean std. dev.
x y z
0 1 1 1 1 total 1.0 0.300047
1 1 2 1 1 total 1.0 0.262180
2 2 1 1 1 total 1.0 0.178169
2 1 2 1 1 total 1.0 0.178169
1 2 1 1 1 total 1.0 0.262180
3 2 2 1 1 total 1.0 0.104797
mesh 1 group out nuclide mean std. dev.
x y z
0 1 1 1 1 total 1.0 0.300047
1 1 2 1 1 total 1.0 0.262180
2 2 1 1 1 total 1.0 0.178169
2 1 2 1 1 total 1.0 0.178169
1 2 1 1 1 total 1.0 0.262180
3 2 2 1 1 total 1.0 0.108931
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 7.097008e-07 1.458546e-07
1 1 2 1 1 total 3.984535e-07 1.157576e-07
2 2 1 1 1 total 4.407745e-07 7.903907e-08
2 1 2 1 1 total 4.407745e-07 7.903907e-08
1 2 1 1 1 total 3.984535e-07 1.157576e-07
3 2 2 1 1 total 4.750476e-07 6.207437e-08
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.027311 0.007397
1 1 2 1 1 total 0.017783 0.004394
2 2 1 1 1 total 0.017820 0.003054
2 1 2 1 1 total 0.017820 0.003054
1 2 1 1 1 total 0.017783 0.004394
3 2 2 1 1 total 0.020320 0.002598
mesh 1 group in group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 0.015584 0.003404
1 1 2 1 1 1 total 0.014200 0.003676
2 2 1 1 1 1 total 0.017684 0.002499
2 1 2 1 1 1 total 0.017684 0.002499
1 2 1 1 1 1 total 0.014200 0.003676
3 2 2 1 1 1 total 0.022259 0.002508
mesh 1 delayedgroup group in nuclide mean std. dev.
x y z
@ -186,18 +186,18 @@
3 1 1 1 4 1 total 0.000072 1.866015e-05
4 1 1 1 5 1 total 0.000031 7.654909e-06
5 1 1 1 6 1 total 0.000013 3.206343e-06
6 1 2 1 1 1 total 0.000004 1.003100e-06
7 1 2 1 2 1 total 0.000022 5.425275e-06
8 1 2 1 3 1 total 0.000021 5.324236e-06
9 1 2 1 4 1 total 0.000050 1.251572e-05
10 1 2 1 5 1 total 0.000022 5.762184e-06
11 1 2 1 6 1 total 0.000009 2.391676e-06
12 2 1 1 1 1 total 0.000004 6.723192e-07
13 2 1 1 2 1 total 0.000022 3.706235e-06
14 2 1 1 3 1 total 0.000022 3.674263e-06
15 2 1 1 4 1 total 0.000052 8.774048e-06
16 2 1 1 5 1 total 0.000024 4.168024e-06
17 2 1 1 6 1 total 0.000010 1.726268e-06
12 1 2 1 1 1 total 0.000004 6.723192e-07
13 1 2 1 2 1 total 0.000022 3.706235e-06
14 1 2 1 3 1 total 0.000022 3.674263e-06
15 1 2 1 4 1 total 0.000052 8.774048e-06
16 1 2 1 5 1 total 0.000024 4.168024e-06
17 1 2 1 6 1 total 0.000010 1.726268e-06
6 2 1 1 1 1 total 0.000004 1.003100e-06
7 2 1 1 2 1 total 0.000022 5.425275e-06
8 2 1 1 3 1 total 0.000021 5.324236e-06
9 2 1 1 4 1 total 0.000050 1.251572e-05
10 2 1 1 5 1 total 0.000022 5.762184e-06
11 2 1 1 6 1 total 0.000009 2.391676e-06
18 2 2 1 1 1 total 0.000005 5.962367e-07
19 2 2 1 2 1 total 0.000025 3.200900e-06
20 2 2 1 3 1 total 0.000025 3.127442e-06
@ -212,18 +212,18 @@
3 1 1 1 4 1 total 0.0 0.000000
4 1 1 1 5 1 total 0.0 0.000000
5 1 1 1 6 1 total 0.0 0.000000
6 1 2 1 1 1 total 0.0 0.000000
7 1 2 1 2 1 total 0.0 0.000000
8 1 2 1 3 1 total 0.0 0.000000
9 1 2 1 4 1 total 0.0 0.000000
10 1 2 1 5 1 total 0.0 0.000000
11 1 2 1 6 1 total 0.0 0.000000
12 2 1 1 1 1 total 0.0 0.000000
13 2 1 1 2 1 total 0.0 0.000000
14 2 1 1 3 1 total 0.0 0.000000
15 2 1 1 4 1 total 0.0 0.000000
16 2 1 1 5 1 total 0.0 0.000000
17 2 1 1 6 1 total 0.0 0.000000
12 1 2 1 1 1 total 0.0 0.000000
13 1 2 1 2 1 total 0.0 0.000000
14 1 2 1 3 1 total 0.0 0.000000
15 1 2 1 4 1 total 0.0 0.000000
16 1 2 1 5 1 total 0.0 0.000000
17 1 2 1 6 1 total 0.0 0.000000
6 2 1 1 1 1 total 0.0 0.000000
7 2 1 1 2 1 total 0.0 0.000000
8 2 1 1 3 1 total 0.0 0.000000
9 2 1 1 4 1 total 0.0 0.000000
10 2 1 1 5 1 total 0.0 0.000000
11 2 1 1 6 1 total 0.0 0.000000
18 2 2 1 1 1 total 0.0 0.000000
19 2 2 1 2 1 total 0.0 0.000000
20 2 2 1 3 1 total 1.0 1.414214
@ -238,18 +238,18 @@
3 1 1 1 4 1 total 0.002629 0.000950
4 1 1 1 5 1 total 0.001125 0.000398
5 1 1 1 6 1 total 0.000470 0.000166
6 1 2 1 1 1 total 0.000228 0.000057
7 1 2 1 2 1 total 0.001222 0.000309
8 1 2 1 3 1 total 0.001193 0.000304
9 1 2 1 4 1 total 0.002780 0.000713
10 1 2 1 5 1 total 0.001250 0.000328
11 1 2 1 6 1 total 0.000520 0.000136
12 2 1 1 1 1 total 0.000225 0.000044
13 2 1 1 2 1 total 0.001232 0.000242
14 2 1 1 3 1 total 0.001216 0.000239
15 2 1 1 4 1 total 0.002882 0.000570
16 2 1 1 5 1 total 0.001345 0.000270
17 2 1 1 6 1 total 0.000558 0.000112
12 1 2 1 1 1 total 0.000225 0.000044
13 1 2 1 2 1 total 0.001232 0.000242
14 1 2 1 3 1 total 0.001216 0.000239
15 1 2 1 4 1 total 0.002882 0.000570
16 1 2 1 5 1 total 0.001345 0.000270
17 1 2 1 6 1 total 0.000558 0.000112
6 2 1 1 1 1 total 0.000228 0.000057
7 2 1 1 2 1 total 0.001222 0.000309
8 2 1 1 3 1 total 0.001193 0.000304
9 2 1 1 4 1 total 0.002780 0.000713
10 2 1 1 5 1 total 0.001250 0.000328
11 2 1 1 6 1 total 0.000520 0.000136
18 2 2 1 1 1 total 0.000227 0.000027
19 2 2 1 2 1 total 0.001225 0.000143
20 2 2 1 3 1 total 0.001201 0.000140
@ -264,18 +264,18 @@
3 1 1 1 4 1 total 0.304289 0.106753
4 1 1 1 5 1 total 0.855760 0.286466
5 1 1 1 6 1 total 2.874120 0.965609
6 1 2 1 1 1 total 0.013357 0.003345
7 1 2 1 2 1 total 0.032590 0.008273
8 1 2 1 3 1 total 0.121103 0.031074
9 1 2 1 4 1 total 0.306111 0.080011
10 1 2 1 5 1 total 0.862660 0.235694
11 1 2 1 6 1 total 2.897534 0.788926
12 2 1 1 1 1 total 0.013367 0.002548
13 2 1 1 2 1 total 0.032520 0.006266
14 2 1 1 3 1 total 0.121250 0.023544
15 2 1 1 4 1 total 0.307552 0.060464
16 2 1 1 5 1 total 0.867665 0.175131
17 2 1 1 6 1 total 2.914635 0.587161
12 1 2 1 1 1 total 0.013367 0.002548
13 1 2 1 2 1 total 0.032520 0.006266
14 1 2 1 3 1 total 0.121250 0.023544
15 1 2 1 4 1 total 0.307552 0.060464
16 1 2 1 5 1 total 0.867665 0.175131
17 1 2 1 6 1 total 2.914635 0.587161
6 2 1 1 1 1 total 0.013357 0.003345
7 2 1 1 2 1 total 0.032590 0.008273
8 2 1 1 3 1 total 0.121103 0.031074
9 2 1 1 4 1 total 0.306111 0.080011
10 2 1 1 5 1 total 0.862660 0.235694
11 2 1 1 6 1 total 2.897534 0.788926
18 2 2 1 1 1 total 0.013360 0.001587
19 2 2 1 2 1 total 0.032564 0.003810
20 2 2 1 3 1 total 0.121158 0.014038
@ -290,18 +290,18 @@
3 1 1 1 4 1 1 total 0.00000 0.000000
4 1 1 1 5 1 1 total 0.00000 0.000000
5 1 1 1 6 1 1 total 0.00000 0.000000
6 1 2 1 1 1 1 total 0.00000 0.000000
7 1 2 1 2 1 1 total 0.00000 0.000000
8 1 2 1 3 1 1 total 0.00000 0.000000
9 1 2 1 4 1 1 total 0.00000 0.000000
10 1 2 1 5 1 1 total 0.00000 0.000000
11 1 2 1 6 1 1 total 0.00000 0.000000
12 2 1 1 1 1 1 total 0.00000 0.000000
13 2 1 1 2 1 1 total 0.00000 0.000000
14 2 1 1 3 1 1 total 0.00000 0.000000
15 2 1 1 4 1 1 total 0.00000 0.000000
16 2 1 1 5 1 1 total 0.00000 0.000000
17 2 1 1 6 1 1 total 0.00000 0.000000
12 1 2 1 1 1 1 total 0.00000 0.000000
13 1 2 1 2 1 1 total 0.00000 0.000000
14 1 2 1 3 1 1 total 0.00000 0.000000
15 1 2 1 4 1 1 total 0.00000 0.000000
16 1 2 1 5 1 1 total 0.00000 0.000000
17 1 2 1 6 1 1 total 0.00000 0.000000
6 2 1 1 1 1 1 total 0.00000 0.000000
7 2 1 1 2 1 1 total 0.00000 0.000000
8 2 1 1 3 1 1 total 0.00000 0.000000
9 2 1 1 4 1 1 total 0.00000 0.000000
10 2 1 1 5 1 1 total 0.00000 0.000000
11 2 1 1 6 1 1 total 0.00000 0.000000
18 2 2 1 1 1 1 total 0.00000 0.000000
19 2 2 1 2 1 1 total 0.00000 0.000000
20 2 2 1 3 1 1 total 0.00015 0.000151

2
tests/regression_tests/mgxs_library_no_nuclides/inputs_true.dat
View file

@ -12,7 +12,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UO2 (2.4%)">
<material depletable="true" id="1" name="UO2 (2.4%)">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />

2
tests/regression_tests/mgxs_library_nuclides/inputs_true.dat
View file

@ -12,7 +12,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UO2 (2.4%)">
<material depletable="true" id="1" name="UO2 (2.4%)">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />

2
tests/regression_tests/multipole/inputs_true.dat
View file

@ -27,7 +27,7 @@
<nuclide ao="1.0" name="O16" />
<sab name="c_H_in_H2O" />
</material>
<material id="2">
<material depletable="true" id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>

2
tests/regression_tests/periodic/inputs_true.dat
View file

@ -18,7 +18,7 @@
<nuclide ao="1.0" name="O16" />
<sab name="c_H_in_H2O" />
</material>
<material id="2">
<material depletable="true" id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>

2
tests/regression_tests/resonance_scattering/inputs_true.dat
View file

@ -5,7 +5,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1">
<material depletable="true" id="1">
<density units="g/cc" value="1.0" />
<nuclide ao="1.0" name="U238" />
<nuclide ao="0.02" name="U235" />

8
tests/regression_tests/salphabeta/inputs_true.dat
View file

@ -12,19 +12,19 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1">
<material depletable="true" id="1">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
<nuclide ao="1.0" name="H1" />
<sab fraction="0.5" name="c_H_in_H2O" />
</material>
<material id="2">
<material depletable="true" id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
<nuclide ao="1.0" name="C0" />
<sab name="c_Graphite" />
</material>
<material id="3">
<material depletable="true" id="3">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
<nuclide ao="1.0" name="Be9" />
@ -32,7 +32,7 @@
<sab name="c_Be_in_BeO" />
<sab name="c_O_in_BeO" />
</material>
<material id="4">
<material depletable="true" id="4">
<density units="g/cm3" value="5.90168" />
<nuclide ao="0.3" name="H1" />
<nuclide ao="0.15" name="Zr90" />

2
tests/regression_tests/source/inputs_true.dat
View file

@ -5,7 +5,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1">
<material depletable="true" id="1">
<temperature>294</temperature>
<density units="g/cm3" value="4.5" />
<nuclide ao="1.0" name="U235" />

2
tests/regression_tests/surface_tally/inputs_true.dat
View file

@ -11,7 +11,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="13" name="UO2 fuel at 2.4% wt enrichment">
<material depletable="true" id="13" name="UO2 fuel at 2.4% wt enrichment">
<density units="g/cc" value="10.0" />
<nuclide ao="1.0" name="U238" />
<nuclide ao="0.02" name="U235" />

2
tests/regression_tests/tallies/inputs_true.dat
View file

@ -148,7 +148,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />

2
tests/regression_tests/tally_aggregation/inputs_true.dat
View file

@ -148,7 +148,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />

2
tests/regression_tests/tally_arithmetic/inputs_true.dat
View file

@ -148,7 +148,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />

2
tests/regression_tests/tally_slice_merge/inputs_true.dat
View file

@ -148,7 +148,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<material depletable="true" id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />

34
tests/regression_tests/tally_slice_merge/results_true.dat
View file

@ -48,20 +48,20 @@
13 (500, 5000, 50000) 6.25e-01 2.00e+07 U235 nu-fission 0.00e+00 0.00e+00
14 (500, 5000, 50000) 6.25e-01 2.00e+07 U238 fission 0.00e+00 0.00e+00
15 (500, 5000, 50000) 6.25e-01 2.00e+07 U238 nu-fission 0.00e+00 0.00e+00
sum(mesh) energy low [eV] energy high [eV] nuclide score mean std. dev.
0 ((1, 1, 1), (1, 2, 1)) 0.00e+00 6.25e-01 U235 fission 1.48e-02 3.65e-03
1 ((1, 1, 1), (1, 2, 1)) 0.00e+00 6.25e-01 U235 nu-fission 3.60e-02 8.90e-03
2 ((1, 1, 1), (1, 2, 1)) 0.00e+00 6.25e-01 U238 fission 2.06e-08 4.98e-09
3 ((1, 1, 1), (1, 2, 1)) 0.00e+00 6.25e-01 U238 nu-fission 5.14e-08 1.24e-08
4 ((1, 1, 1), (1, 2, 1)) 6.25e-01 2.00e+07 U235 fission 2.23e-03 3.92e-04
5 ((1, 1, 1), (1, 2, 1)) 6.25e-01 2.00e+07 U235 nu-fission 5.45e-03 9.56e-04
6 ((1, 1, 1), (1, 2, 1)) 6.25e-01 2.00e+07 U238 fission 5.58e-04 2.08e-04
7 ((1, 1, 1), (1, 2, 1)) 6.25e-01 2.00e+07 U238 nu-fission 1.50e-03 5.43e-04
8 ((2, 1, 1), (2, 2, 1)) 0.00e+00 6.25e-01 U235 fission 2.56e-02 5.50e-03
9 ((2, 1, 1), (2, 2, 1)) 0.00e+00 6.25e-01 U235 nu-fission 6.24e-02 1.34e-02
10 ((2, 1, 1), (2, 2, 1)) 0.00e+00 6.25e-01 U238 fission 3.55e-08 7.70e-09
11 ((2, 1, 1), (2, 2, 1)) 0.00e+00 6.25e-01 U238 nu-fission 8.85e-08 1.92e-08
12 ((2, 1, 1), (2, 2, 1)) 6.25e-01 2.00e+07 U235 fission 5.01e-03 1.38e-03
13 ((2, 1, 1), (2, 2, 1)) 6.25e-01 2.00e+07 U235 nu-fission 1.22e-02 3.37e-03
14 ((2, 1, 1), (2, 2, 1)) 6.25e-01 2.00e+07 U238 fission 2.40e-03 2.69e-04
15 ((2, 1, 1), (2, 2, 1)) 6.25e-01 2.00e+07 U238 nu-fission 6.60e-03 7.63e-04
sum(mesh) energy low [eV] energy high [eV] nuclide score mean std. dev.
0 ((1, 1), (1, 2)) 0.00e+00 6.25e-01 U235 fission 0.00e+00 0.00e+00
1 ((1, 1), (1, 2)) 0.00e+00 6.25e-01 U235 nu-fission 0.00e+00 0.00e+00
2 ((1, 1), (1, 2)) 0.00e+00 6.25e-01 U238 fission 0.00e+00 0.00e+00
3 ((1, 1), (1, 2)) 0.00e+00 6.25e-01 U238 nu-fission 0.00e+00 0.00e+00
4 ((1, 1), (1, 2)) 6.25e-01 2.00e+07 U235 fission 1.60e-04 1.60e-04
5 ((1, 1), (1, 2)) 6.25e-01 2.00e+07 U235 nu-fission 3.91e-04 3.91e-04
6 ((1, 1), (1, 2)) 6.25e-01 2.00e+07 U238 fission 5.12e-05 5.12e-05
7 ((1, 1), (1, 2)) 6.25e-01 2.00e+07 U238 nu-fission 1.36e-04 1.36e-04
8 ((2, 1), (2, 2)) 0.00e+00 6.25e-01 U235 fission 4.04e-02 6.60e-03
9 ((2, 1), (2, 2)) 0.00e+00 6.25e-01 U235 nu-fission 9.85e-02 1.61e-02
10 ((2, 1), (2, 2)) 0.00e+00 6.25e-01 U238 fission 5.61e-08 9.18e-09
11 ((2, 1), (2, 2)) 0.00e+00 6.25e-01 U238 nu-fission 1.40e-07 2.29e-08
12 ((2, 1), (2, 2)) 6.25e-01 2.00e+07 U235 fission 7.08e-03 1.43e-03
13 ((2, 1), (2, 2)) 6.25e-01 2.00e+07 U235 nu-fission 1.73e-02 3.48e-03
14 ((2, 1), (2, 2)) 6.25e-01 2.00e+07 U238 fission 2.91e-03 3.36e-04
15 ((2, 1), (2, 2)) 6.25e-01 2.00e+07 U238 nu-fission 7.96e-03 9.27e-04

8
tests/regression_tests/tally_slice_merge/test.py
View file

@ -126,10 +126,10 @@ class TallySliceMergeTestHarness(PyAPITestHarness):
# Sum up a few subdomains from the distribcell tally
sum1 = distribcell_tally.summation(filter_type=openmc.DistribcellFilter,
filter_bins=[0,100,2000,30000])
filter_bins=[0, 100, 2000, 30000])
# Sum up a few subdomains from the distribcell tally
sum2 = distribcell_tally.summation(filter_type=openmc.DistribcellFilter,
filter_bins=[500,5000,50000])
filter_bins=[500, 5000, 50000])
# Merge the distribcell tally slices
merge_tally = sum1.merge(sum2)
@ -143,10 +143,10 @@ class TallySliceMergeTestHarness(PyAPITestHarness):
# Sum up a few subdomains from the mesh tally
sum1 = mesh_tally.summation(filter_type=openmc.MeshFilter,
filter_bins=[(1,1,1), (1,2,1)])
filter_bins=[(1, 1), (1, 2)])
# Sum up a few subdomains from the mesh tally
sum2 = mesh_tally.summation(filter_type=openmc.MeshFilter,
filter_bins=[(2,1,1), (2,2,1)])
filter_bins=[(2, 1), (2, 2)])
# Merge the mesh tally slices
merge_tally = sum1.merge(sum2)

2
tests/regression_tests/triso/inputs_true.dat
View file

@ -393,7 +393,7 @@
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="13">
<material depletable="true" id="13">
<density units="g/cm3" value="10.5" />
<nuclide ao="0.14154" name="U235" />
<nuclide ao="0.85846" name="U238" />

2
tests/regression_tests/volume_calc/inputs_true.dat
View file

@ -18,7 +18,7 @@
<nuclide ao="0.0001" name="B10" />
<sab name="c_H_in_H2O" />
</material>
<material id="2">
<material depletable="true" id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
<nuclide ao="0.1" name="Mo99" />

54
tests/regression_tests/volume_calc/results_true.dat
View file

@ -1,30 +1,30 @@
Volume calculation 0
Domain 1: 31.4693 +/- 0.0721 cm^3
Domain 2: 2.0933 +/- 0.0310 cm^3
Domain 3: 2.0486 +/- 0.0307 cm^3
Cell Nuclide Atoms Uncertainty
0 1 U235 3.481769e+23 7.979991e+20
1 1 Mo99 3.481769e+22 7.979991e+19
2 2 H1 1.399770e+23 2.072914e+21
3 2 O16 6.998852e+22 1.036457e+21
4 2 B10 6.998852e+18 1.036457e+17
5 3 H1 1.369920e+23 2.051689e+21
6 3 O16 6.849599e+22 1.025844e+21
7 3 B10 6.849599e+18 1.025844e+17
Domain 1: 31.47+/-0.07 cm^3
Domain 2: 2.093+/-0.031 cm^3
Domain 3: 2.049+/-0.031 cm^3
Cell Nuclide Atoms
0 1 U235 (3.482+/-0.008)e+23
1 1 Mo99 (3.482+/-0.008)e+22
2 2 H1 (1.400+/-0.021)e+23
3 2 O16 (7.00+/-0.10)e+22
4 2 B10 (7.00+/-0.10)e+18
5 3 H1 (1.370+/-0.021)e+23
6 3 O16 (6.85+/-0.10)e+22
7 3 B10 (6.85+/-0.10)e+18
Volume calculation 1
Domain 1: 4.1419 +/- 0.0426 cm^3
Domain 2: 31.4693 +/- 0.0721 cm^3
Material Nuclide Atoms Uncertainty
0 1 H1 2.769690e+23 2.850067e+21
1 1 O16 1.384845e+23 1.425034e+21
2 1 B10 1.384845e+19 1.425034e+17
3 2 U235 3.481769e+23 7.979991e+20
4 2 Mo99 3.481769e+22 7.979991e+19
Domain 1: 4.14+/-0.04 cm^3
Domain 2: 31.47+/-0.07 cm^3
Material Nuclide Atoms
0 1 H1 (2.770+/-0.029)e+23
1 1 O16 (1.385+/-0.014)e+23
2 1 B10 (1.385+/-0.014)e+19
3 2 U235 (3.482+/-0.008)e+23
4 2 Mo99 (3.482+/-0.008)e+22
Volume calculation 2
Domain 0: 35.6112 +/- 0.0664 cm^3
Universe Nuclide Atoms Uncertainty
0 0 H1 2.769690e+23 2.850067e+21
1 0 O16 1.384845e+23 1.425034e+21
2 0 B10 1.384845e+19 1.425034e+17
3 0 U235 3.481769e+23 7.979991e+20
4 0 Mo99 3.481769e+22 7.979991e+19
Domain 0: 35.61+/-0.07 cm^3
Universe Nuclide Atoms
0 0 H1 (2.770+/-0.029)e+23
1 0 O16 (1.385+/-0.014)e+23
2 0 B10 (1.385+/-0.014)e+19
3 0 U235 (3.482+/-0.008)e+23
4 0 Mo99 (3.482+/-0.008)e+22

3
tests/regression_tests/volume_calc/test.py
View file

@ -64,8 +64,7 @@ class VolumeTest(PyAPITestHarness):
# Write cell volumes and total # of atoms for each nuclide
for uid, volume in sorted(volume_calc.volumes.items()):
outstr += 'Domain {0}: {1[0]:.4f} +/- {1[1]:.4f} cm^3\n'.format(
uid, volume)
outstr += 'Domain {}: {} cm^3\n'.format(uid, volume)
outstr += str(volume_calc.atoms_dataframe) + '\n'
return outstr

2
tests/testing_harness.py
View file

@ -75,7 +75,7 @@ class TestHarness(object):
# Write out k-combined.
outstr = 'k-combined:\n'
form = '{0:12.6E} {1:12.6E}\n'
outstr += form.format(sp.k_combined[0], sp.k_combined[1])
outstr += form.format(sp.k_combined.n, sp.k_combined.s)
# Write out tally data.
for i, tally_ind in enumerate(sp.tallies):

13
tests/unit_tests/test_data_misc.py
View file

@ -50,6 +50,19 @@ def test_thin():
assert f(1.0) == pytest.approx(np.sin(1.0), 0.001)
def test_atomic_mass():
assert openmc.data.atomic_mass('H1') == 1.00782503223
assert openmc.data.atomic_mass('U235') == 235.043930131
with pytest.raises(KeyError):
openmc.data.atomic_mass('U100')
def test_atomic_weight():
assert openmc.data.atomic_weight('C') == 12.011115164862904
with pytest.raises(ValueError):
openmc.data.atomic_weight('Qt')
def test_water_density():
dens = openmc.data.water_density
# These test values are from IAPWS R7-97(2012). They are actually specific

4
tests/unit_tests/test_material.py
View file

@ -15,9 +15,9 @@ def test_nuclides(uo2):
"""Test adding/removing nuclides."""
m = openmc.Material()
m.add_nuclide('U235', 1.0)
with pytest.raises(ValueError):
with pytest.raises(TypeError):
m.add_nuclide('H1', '1.0')
with pytest.raises(ValueError):
with pytest.raises(TypeError):
m.add_nuclide(1.0, 'H1')
with pytest.raises(ValueError):
m.add_nuclide('H1', 1.0, 'oa')

1
tests/unit_tests/test_universe.py
View file

@ -59,7 +59,6 @@ def test_plot(run_in_tmpdir, sphere_model):
pixels=(10, 10),
color_by='material',
colors=colors,
filename='test.png'
)