Manage unique IDs via new IDManagerMixin that uses class variables

This commit is contained in:
Paul Romano 2017-06-02 13:25:34 -05:00
parent c9e2e4337b
commit ca009e211e
52 changed files with 3830 additions and 3976 deletions

View file

@ -1,7 +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 *
from openmc.nuclide import *
@ -14,6 +13,7 @@ from openmc.source import *
from openmc.settings import *
from openmc.surface import *
from openmc.universe import *
from openmc.lattice import *
from openmc.filter import *
from openmc.trigger import *
from openmc.tally_derivative import *

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@ -13,19 +13,10 @@ import openmc
import openmc.checkvalue as cv
from openmc.surface import Halfspace
from openmc.region import Region, Intersection, Complement
from .mixin import IDManagerMixin
# A static variable for auto-generated Cell IDs
AUTO_CELL_ID = 10000
def reset_auto_cell_id():
"""Reset counter for auto-generated cell IDs."""
global AUTO_CELL_ID
AUTO_CELL_ID = 10000
class Cell(object):
class Cell(IDManagerMixin):
r"""A region of space defined as the intersection of half-space created by
quadric surfaces.
@ -93,6 +84,9 @@ class Cell(object):
"""
next_id = 1
used_ids = set()
def __init__(self, cell_id=None, name='', fill=None, region=None):
# Initialize Cell class attributes
self.id = cell_id
@ -164,10 +158,6 @@ class Cell(object):
return string
@property
def id(self):
return self._id
@property
def name(self):
return self._name
@ -236,17 +226,6 @@ class Cell(object):
'Geometry.determine_paths() method.')
return self._num_instances
@id.setter
def id(self, cell_id):
if cell_id is None:
global AUTO_CELL_ID
self._id = AUTO_CELL_ID
AUTO_CELL_ID += 1
else:
cv.check_type('cell ID', cell_id, Integral)
cv.check_greater_than('cell ID', cell_id, 0, equality=True)
self._id = cell_id
@name.setter
def name(self, name):
if name is not None:

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@ -12,11 +12,9 @@ import pandas as pd
import openmc
import openmc.checkvalue as cv
from .mixin import IDManagerMixin
# "Static" variable for auto-generated Filter IDs
AUTO_FILTER_ID = 10000
_FILTER_TYPES = ['universe', 'material', 'cell', 'cellborn', 'surface',
'mesh', 'energy', 'energyout', 'mu', 'polar', 'azimuthal',
'distribcell', 'delayedgroup', 'energyfunction']
@ -29,12 +27,6 @@ _CURRENT_NAMES = {1: 'x-min out', 2: 'x-min in',
11: 'z-max out', 12: 'z-max in'}
def reset_auto_filter_id():
"""Reset counter for auto-generated filter IDs."""
global AUTO_FILTER_ID
AUTO_FILTER_ID = 10000
class FilterMeta(ABCMeta):
def __new__(cls, name, bases, namespace, **kwargs):
# Check the class name.
@ -74,7 +66,7 @@ class FilterMeta(ABCMeta):
@add_metaclass(FilterMeta)
class Filter(object):
class Filter(IDManagerMixin):
"""Tally modifier that describes phase-space and other characteristics.
Parameters
@ -100,6 +92,9 @@ class Filter(object):
"""
next_id = 1
used_ids = set()
def __init__(self, bins, filter_id=None):
self.bins = bins
self.id = filter_id
@ -195,10 +190,6 @@ class Filter(object):
def bins(self):
return self._bins
@property
def id(self):
return self._id
@property
def num_bins(self):
return self._num_bins
@ -217,17 +208,6 @@ class Filter(object):
self._bins = bins
@id.setter
def id(self, filter_id):
if filter_id is None:
global AUTO_FILTER_ID
self._id = AUTO_FILTER_ID
AUTO_FILTER_ID += 1
else:
cv.check_type('filter ID', filter_id, Integral)
cv.check_greater_than('filter ID', filter_id, 0, equality=True)
self._id = filter_id
@num_bins.setter
def num_bins(self, num_bins):
cv.check_type('filter num_bins', num_bins, Integral)

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@ -7,14 +7,14 @@ from six import string_types
import openmc
from openmc.clean_xml import sort_xml_elements, clean_xml_indentation
from openmc.checkvalue import check_type
from openmc.mixin import IDManagerMixin
def reset_auto_ids():
"""Reset counters for all auto-generated IDs"""
openmc.reset_auto_material_id()
openmc.reset_auto_surface_id()
openmc.reset_auto_cell_id()
openmc.reset_auto_universe_id()
for cls in IDManagerMixin.__subclasses__():
cls.used_ids.clear()
cls.next_id = 1
class Geometry(object):

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@ -12,10 +12,11 @@ import numpy as np
import openmc.checkvalue as cv
import openmc
from openmc.mixin import IDManagerMixin
@add_metaclass(ABCMeta)
class Lattice(object):
class Lattice(IDManagerMixin):
"""A repeating structure wherein each element is a universe.
Parameters
@ -41,6 +42,10 @@ class Lattice(object):
of the lattice
"""
next_id = 1
used_ids = openmc.Universe.used_ids
def __init__(self, lattice_id=None, name=''):
# Initialize Lattice class attributes
self.id = lattice_id
@ -68,10 +73,6 @@ class Lattice(object):
def __ne__(self, other):
return not self == other
@property
def id(self):
return self._id
@property
def name(self):
return self._name
@ -88,16 +89,6 @@ class Lattice(object):
def universes(self):
return self._universes
@id.setter
def id(self, lattice_id):
if lattice_id is None:
self._id = openmc.universe.AUTO_UNIVERSE_ID
openmc.universe.AUTO_UNIVERSE_ID += 1
else:
cv.check_type('lattice ID', lattice_id, Integral)
cv.check_greater_than('lattice ID', lattice_id, 0, equality=True)
self._id = lattice_id
@name.setter
def name(self, name):
if name is not None:

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@ -11,16 +11,7 @@ import openmc
import openmc.data
import openmc.checkvalue as cv
from openmc.clean_xml import sort_xml_elements, clean_xml_indentation
# A static variable for auto-generated Material IDs
AUTO_MATERIAL_ID = 10000
def reset_auto_material_id():
"""Reset counter for auto-generated material IDs."""
global AUTO_MATERIAL_ID
AUTO_MATERIAL_ID = 10000
from .mixin import IDManagerMixin
# Units for density supported by OpenMC
@ -28,7 +19,7 @@ DENSITY_UNITS = ['g/cm3', 'g/cc', 'kg/cm3', 'atom/b-cm', 'atom/cm3', 'sum',
'macro']
class Material(object):
class Material(IDManagerMixin):
"""A material composed of a collection of nuclides/elements.
To create a material, one should create an instance of this class, add
@ -89,6 +80,9 @@ class Material(object):
"""
next_id = 1
used_ids = set()
def __init__(self, material_id=None, name='', temperature=None):
# Initialize class attributes
self.id = material_id
@ -184,10 +178,6 @@ class Material(object):
return string
@property
def id(self):
return self._id
@property
def name(self):
return self._name
@ -264,18 +254,6 @@ class Material(object):
def volume(self):
return self._volume
@id.setter
def id(self, material_id):
if material_id is None:
global AUTO_MATERIAL_ID
self._id = AUTO_MATERIAL_ID
AUTO_MATERIAL_ID += 1
else:
cv.check_type('material ID', material_id, Integral)
cv.check_greater_than('material ID', material_id, 0, equality=True)
self._id = material_id
@name.setter
def name(self, name):
if name is not None:

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@ -8,20 +8,10 @@ import numpy as np
import openmc.checkvalue as cv
import openmc
from openmc.mixin import EqualityMixin
from openmc.mixin import EqualityMixin, IDManagerMixin
# "Static" variable for auto-generated and Mesh IDs
AUTO_MESH_ID = 10000
def reset_auto_mesh_id():
"""Reset counter for auto-generated mesh IDs."""
global AUTO_MESH_ID
AUTO_MESH_ID = 10000
class Mesh(EqualityMixin):
class Mesh(EqualityMixin, IDManagerMixin):
"""A structured Cartesian mesh in one, two, or three dimensions
Parameters
@ -52,6 +42,9 @@ class Mesh(EqualityMixin):
"""
next_id = 1
used_ids = set()
def __init__(self, mesh_id=None, name=''):
# Initialize Mesh class attributes
self.id = mesh_id
@ -62,10 +55,6 @@ class Mesh(EqualityMixin):
self._upper_right = None
self._width = None
@property
def id(self):
return self._id
@property
def name(self):
return self._name
@ -94,17 +83,6 @@ class Mesh(EqualityMixin):
def num_mesh_cells(self):
return np.prod(self._dimension)
@id.setter
def id(self, mesh_id):
if mesh_id is None:
global AUTO_MESH_ID
self._id = AUTO_MESH_ID
AUTO_MESH_ID += 1
else:
cv.check_type('mesh ID', mesh_id, Integral)
cv.check_greater_than('mesh ID', mesh_id, 0, equality=True)
self._id = mesh_id
@name.setter
def name(self, name):
if name is not None:

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@ -1,5 +1,10 @@
from numbers import Integral
from warnings import warn
import numpy as np
import openmc.checkvalue as cv
class EqualityMixin(object):
"""A Class which provides generic __eq__ and __ne__ functionality which
@ -18,3 +23,37 @@ class EqualityMixin(object):
def __ne__(self, other):
return not self.__eq__(other)
class IDManagerMixin(object):
"""A Class which automatically manages unique IDs.
This mixin gives any subclass the ability to assign unique IDs through an
'id' property and keeps track of which ones have already been
assigned. Crucially, each subclass must define class variables 'next_id' and
'used_ids' as they are used in the 'id' property that is supplied here.
"""
@property
def id(self):
return self._id
@id.setter
def id(self, uid):
cls = type(self)
name = cls.__name__
if uid is None:
while cls.next_id in cls.used_ids:
cls.next_id += 1
self._id = cls.next_id
cls.used_ids.add(cls.next_id)
else:
cv.check_type('{} ID'.format(name), uid, Integral)
cv.check_greater_than('{} ID'.format(name), uid, 0, equality=True)
if uid in cls.used_ids:
warn('Another {} instance already exists with id={}.'.format(
name, uid))
else:
cls.used_ids.add(uid)
self._id = uid

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@ -10,16 +10,7 @@ import numpy as np
import openmc
import openmc.checkvalue as cv
from openmc.clean_xml import clean_xml_indentation
# A static variable for auto-generated Plot IDs
AUTO_PLOT_ID = 10000
def reset_auto_plot_id():
"""Reset counter for auto-generated plot IDs."""
global AUTO_PLOT_ID
AUTO_PLOT_ID = 10000
from openmc.mixin import IDManagerMixin
_BASES = ['xy', 'xz', 'yz']
@ -175,7 +166,7 @@ _SVG_COLORS = {
}
class Plot(object):
class Plot(IDManagerMixin):
"""Definition of a finite region of space to be plotted.
OpenMC is capable of generating two-dimensional slice plots and
@ -227,6 +218,9 @@ class Plot(object):
"""
next_id = 1
used_ids = set()
def __init__(self, plot_id=None, name=''):
# Initialize Plot class attributes
self.id = plot_id
@ -245,10 +239,6 @@ class Plot(object):
self._level = None
self._meshlines = None
@property
def id(self):
return self._id
@property
def name(self):
return self._name
@ -305,17 +295,6 @@ class Plot(object):
def meshlines(self):
return self._meshlines
@id.setter
def id(self, plot_id):
if plot_id is None:
global AUTO_PLOT_ID
self._id = AUTO_PLOT_ID
AUTO_PLOT_ID += 1
else:
cv.check_type('plot ID', plot_id, Integral)
cv.check_greater_than('plot ID', plot_id, 0, equality=True)
self._id = plot_id
@name.setter
def name(self, name):
cv.check_type('plot name', name, string_types)

View file

@ -356,71 +356,76 @@ class StatePoint(object):
else:
tally_ids = []
# Iterate over all tallies
for tally_id in tally_ids:
group = tallies_group['tally {}'.format(tally_id)]
# Ignore warnings about duplicate IDs
with warnings.catch_warnings():
warnings.simplefilter('ignore', UserWarning)
# Read the number of realizations
n_realizations = group['n_realizations'].value
# Iterate over all tallies
for tally_id in tally_ids:
group = tallies_group['tally {}'.format(tally_id)]
# Create Tally object and assign basic properties
tally = openmc.Tally(tally_id)
tally._sp_filename = self._f.filename
tally.name = group['name'].value.decode() if 'name' in group else ''
tally.estimator = group['estimator'].value.decode()
tally.num_realizations = n_realizations
# Read the number of realizations
n_realizations = group['n_realizations'].value
# Read derivative information.
if 'derivative' in group:
deriv_id = group['derivative'].value
tally.derivative = self.tally_derivatives[deriv_id]
# Create Tally object and assign basic properties
tally = openmc.Tally(tally_id)
tally._sp_filename = self._f.filename
tally.name = group['name'].value.decode() if 'name' in group else ''
tally.estimator = group['estimator'].value.decode()
tally.num_realizations = n_realizations
# Read all filters
n_filters = group['n_filters'].value
if n_filters > 0:
filter_ids = group['filters'].value
filters_group = self._f['tallies/filters']
for filter_id in filter_ids:
filter_group = filters_group['filter {}'.format(filter_id)]
new_filter = openmc.Filter.from_hdf5(filter_group,
meshes=self.meshes)
tally.filters.append(new_filter)
# Read derivative information.
if 'derivative' in group:
deriv_id = group['derivative'].value
tally.derivative = self.tally_derivatives[deriv_id]
# Read nuclide bins
nuclide_names = group['nuclides'].value
# Read all filters
n_filters = group['n_filters'].value
if n_filters > 0:
filter_ids = group['filters'].value
filters_group = self._f['tallies/filters']
for filter_id in filter_ids:
filter_group = filters_group['filter {}'.format(
filter_id)]
new_filter = openmc.Filter.from_hdf5(
filter_group, meshes=self.meshes)
tally.filters.append(new_filter)
# Add all nuclides to the Tally
for name in nuclide_names:
nuclide = openmc.Nuclide(name.decode().strip())
tally.nuclides.append(nuclide)
# Read nuclide bins
nuclide_names = group['nuclides'].value
scores = group['score_bins'].value
n_score_bins = group['n_score_bins'].value
# Add all nuclides to the Tally
for name in nuclide_names:
nuclide = openmc.Nuclide(name.decode().strip())
tally.nuclides.append(nuclide)
# Compute and set the filter strides
for i in range(n_filters):
tally_filter = tally.filters[i]
tally_filter.stride = n_score_bins * len(nuclide_names)
scores = group['score_bins'].value
n_score_bins = group['n_score_bins'].value
for j in range(i+1, n_filters):
tally_filter.stride *= tally.filters[j].num_bins
# Compute and set the filter strides
for i in range(n_filters):
tally_filter = tally.filters[i]
tally_filter.stride = n_score_bins * len(nuclide_names)
# Read scattering moment order strings (e.g., P3, Y1,2, etc.)
moments = group['moment_orders'].value
for j in range(i+1, n_filters):
tally_filter.stride *= tally.filters[j].num_bins
# Add the scores to the Tally
for j, score in enumerate(scores):
score = score.decode()
# Read scattering moment order strings (e.g., P3, Y1,2, etc.)
moments = group['moment_orders'].value
# If this is a moment, use generic moment order
pattern = r'-n$|-pn$|-yn$'
score = re.sub(pattern, '-' + moments[j].decode(), score)
# Add the scores to the Tally
for j, score in enumerate(scores):
score = score.decode()
tally.scores.append(score)
# If this is a moment, use generic moment order
pattern = r'-n$|-pn$|-yn$'
score = re.sub(pattern, '-' + moments[j].decode(), score)
# Add Tally to the global dictionary of all Tallies
tally.sparse = self.sparse
self._tallies[tally_id] = tally
tally.scores.append(score)
# Add Tally to the global dictionary of all Tallies
tally.sparse = self.sparse
self._tallies[tally_id] = tally
self._tallies_read = True

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@ -1,5 +1,6 @@
from collections import Iterable
import re
import warnings
import numpy as np
import h5py
@ -31,8 +32,6 @@ class Summary(object):
"""
def __init__(self, filename):
openmc.reset_auto_ids()
if not filename.endswith(('.h5', '.hdf5')):
msg = 'Unable to open "{0}" which is not an HDF5 summary file'
raise ValueError(msg)
@ -52,7 +51,9 @@ class Summary(object):
self._nuclides = {}
self._read_nuclides()
self._read_geometry()
with warnings.catch_warnings():
warnings.simplefilter("ignore", UserWarning)
self._read_geometry()
@property
def date_and_time(self):
@ -69,7 +70,7 @@ class Summary(object):
@property
def nuclides(self):
return self._nuclides
@property
def version(self):
return tuple(self._f.attrs['openmc_version'])

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@ -12,6 +12,7 @@ import numpy as np
from openmc.checkvalue import check_type, check_value, check_greater_than
from openmc.region import Region, Intersection, Union
from openmc.mixin import IDManagerMixin
# A static variable for auto-generated Surface IDs
@ -20,13 +21,7 @@ AUTO_SURFACE_ID = 10000
_BOUNDARY_TYPES = ['transmission', 'vacuum', 'reflective', 'periodic']
def reset_auto_surface_id():
"""Reset counters for all auto-generated surface IDs"""
global AUTO_SURFACE_ID
AUTO_SURFACE_ID = 10000
class Surface(object):
class Surface(IDManagerMixin):
"""An implicit surface with an associated boundary condition.
An implicit surface is defined as the set of zeros of a function of the
@ -64,6 +59,9 @@ class Surface(object):
"""
next_id = 1
used_ids = set()
def __init__(self, surface_id=None, boundary_type='transmission', name=''):
self.id = surface_id
self.name = name
@ -105,10 +103,6 @@ class Surface(object):
return string
@property
def id(self):
return self._id
@property
def name(self):
return self._name
@ -125,17 +119,6 @@ class Surface(object):
def coefficients(self):
return self._coefficients
@id.setter
def id(self, surface_id):
if surface_id is None:
global AUTO_SURFACE_ID
self._id = AUTO_SURFACE_ID
AUTO_SURFACE_ID += 1
else:
check_type('surface ID', surface_id, Integral)
check_greater_than('surface ID', surface_id, 0, equality=True)
self._id = surface_id
@name.setter
def name(self, name):
if name is not None:

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@ -18,11 +18,9 @@ import h5py
import openmc
import openmc.checkvalue as cv
from openmc.clean_xml import clean_xml_indentation
from .mixin import IDManagerMixin
# "Static" variable for auto-generated Tally IDs
AUTO_TALLY_ID = 10000
# The tally arithmetic product types. The tensor product performs the full
# cross product of the data in two tallies with respect to a specified axis
# (filters, nuclides, or scores). The entrywise product performs the arithmetic
@ -41,13 +39,7 @@ _FILTER_CLASSES = (openmc.Filter, openmc.CrossFilter, openmc.AggregateFilter)
ESTIMATOR_TYPES = ['tracklength', 'collision', 'analog']
def reset_auto_tally_id():
"""Reset counter for auto-generated tally IDs."""
global AUTO_TALLY_ID
AUTO_TALLY_ID = 10000
class Tally(object):
class Tally(IDManagerMixin):
"""A tally defined by a set of scores that are accumulated for a list of
nuclides given a set of filters.
@ -109,6 +101,9 @@ class Tally(object):
"""
next_id = 1
used_ids = set()
def __init__(self, tally_id=None, name=''):
# Initialize Tally class attributes
self.id = tally_id
@ -204,10 +199,6 @@ class Tally(object):
return string
@property
def id(self):
return self._id
@property
def name(self):
return self._name
@ -416,17 +407,6 @@ class Tally(object):
DeprecationWarning)
self.triggers.append(trigger)
@id.setter
def id(self, tally_id):
if tally_id is None:
global AUTO_TALLY_ID
self._id = AUTO_TALLY_ID
AUTO_TALLY_ID += 1
else:
cv.check_type('tally ID', tally_id, Integral)
cv.check_greater_than('tally ID', tally_id, 0, equality=True)
self._id = tally_id
@name.setter
def name(self, name):
if name is not None:

View file

@ -7,18 +7,10 @@ from xml.etree import ElementTree as ET
from six import string_types
import openmc.checkvalue as cv
from openmc.mixin import EqualityMixin
from openmc.mixin import EqualityMixin, IDManagerMixin
# "Static" variable for auto-generated TallyDerivative IDs
AUTO_TALLY_DERIV_ID = 10000
def reset_auto_tally_deriv_id():
global AUTO_TALLY_ID
AUTO_TALLY_DERIV_ID = 10000
class TallyDerivative(EqualityMixin):
class TallyDerivative(EqualityMixin, IDManagerMixin):
"""A material perturbation derivative to apply to a tally.
Parameters
@ -48,6 +40,9 @@ class TallyDerivative(EqualityMixin):
"""
next_id = 1
used_ids = set()
def __init__(self, derivative_id=None, variable=None, material=None,
nuclide=None):
# Initialize Tally class attributes
@ -74,10 +69,6 @@ class TallyDerivative(EqualityMixin):
return string
@property
def id(self):
return self._id
@property
def variable(self):
return self._variable
@ -90,18 +81,6 @@ class TallyDerivative(EqualityMixin):
def nuclide(self):
return self._nuclide
@id.setter
def id(self, deriv_id):
if deriv_id is None:
global AUTO_TALLY_DERIV_ID
self._id = AUTO_TALLY_DERIV_ID
AUTO_TALLY_DERIV_ID += 1
else:
cv.check_type('tally derivative ID', deriv_id, Integral)
cv.check_greater_than('tally derivative ID', deriv_id, 0,
equality=True)
self._id = deriv_id
@variable.setter
def variable(self, var):
if var is not None:

View file

@ -11,19 +11,10 @@ import numpy as np
import openmc
import openmc.checkvalue as cv
from openmc.plots import _SVG_COLORS
from openmc.mixin import IDManagerMixin
# A static variable for auto-generated Lattice (Universe) IDs
AUTO_UNIVERSE_ID = 10000
def reset_auto_universe_id():
"""Reset counter for auto-generated universe IDs."""
global AUTO_UNIVERSE_ID
AUTO_UNIVERSE_ID = 10000
class Universe(object):
class Universe(IDManagerMixin):
"""A collection of cells that can be repeated.
Parameters
@ -55,6 +46,9 @@ class Universe(object):
"""
next_id = 1
used_ids = set()
def __init__(self, universe_id=None, name='', cells=None):
# Initialize Cell class attributes
self.id = universe_id
@ -95,10 +89,6 @@ class Universe(object):
list(self._cells.keys()))
return string
@property
def id(self):
return self._id
@property
def name(self):
return self._name
@ -121,17 +111,6 @@ class Universe(object):
# Infinite bounding box
return openmc.Intersection().bounding_box
@id.setter
def id(self, universe_id):
if universe_id is None:
global AUTO_UNIVERSE_ID
self._id = AUTO_UNIVERSE_ID
AUTO_UNIVERSE_ID += 1
else:
cv.check_type('universe ID', universe_id, Integral)
cv.check_greater_than('universe ID', universe_id, 0, equality=True)
self._id = universe_id
@name.setter
def name(self, name):
if name is not None:

View file

@ -1,7 +1,7 @@
from collections import Iterable, Mapping, OrderedDict
from numbers import Real, Integral
from xml.etree import ElementTree as ET
from warnings import warn
import warnings
import numpy as np
import pandas as pd
@ -85,9 +85,10 @@ class VolumeCalculation(object):
continue
if (np.any(np.asarray(lower_left) > ll) or
np.any(np.asarray(upper_right) < ur)):
warn("Specified bounding box is smaller than computed "
"bounding box for cell {}. Volume calculation may "
"be incorrect!".format(c.id))
warnings.warn(
"Specified bounding box is smaller than computed "
"bounding box for cell {}. Volume calculation may "
"be incorrect!".format(c.id))
self.lower_left = lower_left
self.upper_right = upper_right
@ -221,12 +222,14 @@ class VolumeCalculation(object):
# Instantiate some throw-away domains that are used by the constructor
# to assign IDs
if domain_type == 'cell':
domains = [openmc.Cell(uid) for uid in ids]
elif domain_type == 'material':
domains = [openmc.Material(uid) for uid in ids]
elif domain_type == 'universe':
domains = [openmc.Universe(uid) for uid in ids]
with warnings.catch_warnings():
warnings.simplefilter('ignore', UserWarning)
if domain_type == 'cell':
domains = [openmc.Cell(uid) for uid in ids]
elif domain_type == 'material':
domains = [openmc.Material(uid) for uid in ids]
elif domain_type == 'universe':
domains = [openmc.Universe(uid) for uid in ids]
# Instantiate the class and assign results
vol = cls(domains, samples, lower_left, upper_right)

View file

@ -1,6 +1,6 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell fill="202" id="1" region="10000 -10001 10002 -10003 10004 -10005" universe="0" />
<cell fill="202" id="1" region="9 -10 11 -12 13 -14" 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" />
@ -42,17 +42,17 @@
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 boundary="reflective" coeffs="32.13" id="10" type="x-plane" />
<surface boundary="reflective" coeffs="-32.13" id="11" type="y-plane" />
<surface boundary="reflective" coeffs="32.13" id="12" type="y-plane" />
<surface boundary="reflective" coeffs="0" id="13" type="z-plane" />
<surface boundary="reflective" coeffs="32.13" id="14" 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" />
<surface boundary="reflective" coeffs="-32.13" id="9" type="x-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
@ -217,11 +217,11 @@
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="10000" type="distribcell">
<filter id="1" type="distribcell">
<bins>27</bins>
</filter>
<tally id="27" name="distribcell tally">
<filters>10000</filters>
<filters>1</filters>
<scores>nu-fission</scores>
</tally>
</tallies>

View file

@ -310,123 +310,123 @@
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="10000" type="material">
<filter id="1" type="material">
<bins>1 3</bins>
</filter>
<filter id="10001" type="energyout">
<filter id="2" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<tally id="10000">
<filters>10000</filters>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
<derivative>1</derivative>
</tally>
<tally id="10001">
<filters>10000</filters>
<tally id="2">
<filters>1</filters>
<scores>flux</scores>
<derivative>2</derivative>
</tally>
<tally id="10002">
<filters>10000</filters>
<tally id="3">
<filters>1</filters>
<scores>flux</scores>
<derivative>3</derivative>
</tally>
<tally id="10003">
<filters>10000</filters>
<tally id="4">
<filters>1</filters>
<scores>flux</scores>
<derivative>4</derivative>
</tally>
<tally id="10004">
<filters>10000</filters>
<tally id="5">
<filters>1</filters>
<scores>flux</scores>
<derivative>5</derivative>
</tally>
<tally id="10005">
<filters>10000</filters>
<tally id="6">
<filters>1</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>1</derivative>
</tally>
<tally id="10006">
<filters>10000</filters>
<tally id="7">
<filters>1</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>2</derivative>
</tally>
<tally id="10007">
<filters>10000</filters>
<tally id="8">
<filters>1</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>3</derivative>
</tally>
<tally id="10008">
<filters>10000</filters>
<tally id="9">
<filters>1</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>4</derivative>
</tally>
<tally id="10009">
<filters>10000</filters>
<tally id="10">
<filters>1</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>5</derivative>
</tally>
<tally id="10010">
<filters>10000</filters>
<tally id="11">
<filters>1</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>1</derivative>
</tally>
<tally id="10011">
<filters>10000</filters>
<tally id="12">
<filters>1</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>2</derivative>
</tally>
<tally id="10012">
<filters>10000</filters>
<tally id="13">
<filters>1</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>3</derivative>
</tally>
<tally id="10013">
<filters>10000</filters>
<tally id="14">
<filters>1</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>4</derivative>
</tally>
<tally id="10014">
<filters>10000</filters>
<tally id="15">
<filters>1</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>5</derivative>
</tally>
<tally id="10015">
<filters>10000 10001</filters>
<tally id="16">
<filters>1 2</filters>
<nuclides>total U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>1</derivative>
</tally>
<tally id="10016">
<filters>10000 10001</filters>
<tally id="17">
<filters>1 2</filters>
<nuclides>total U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>2</derivative>
</tally>
<tally id="10017">
<filters>10000 10001</filters>
<tally id="18">
<filters>1 2</filters>
<nuclides>U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>3</derivative>
</tally>
<tally id="10018">
<filters>10000 10001</filters>
<tally id="19">
<filters>1 2</filters>
<nuclides>U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>4</derivative>
</tally>
<tally id="10019">
<filters>10000 10001</filters>
<tally id="20">
<filters>1 2</filters>
<nuclides>U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>5</derivative>

View file

@ -1,44 +1,4 @@
d_material,d_nuclide,d_variable,score,mean,std. dev.
1,,density,nu-fission,0.0000000e+00,0.0000000e+00
1,,density,scatter,3.9903014e-02,9.1258569e-03
1,,density,nu-fission,0.0000000e+00,0.0000000e+00
1,,density,scatter,9.8213753e-04,9.8213753e-04
1,,density,nu-fission,2.7945436e-02,2.0999385e-02
1,,density,scatter,4.0626164e-01,1.7017647e-02
1,,density,nu-fission,2.4595326e-02,2.1224461e-02
1,,density,scatter,2.6505966e-03,2.3698970e-03
1,,density,nu-fission,0.0000000e+00,0.0000000e+00
1,,density,scatter,-1.2721691e-01,1.8810988e-01
1,,density,nu-fission,0.0000000e+00,0.0000000e+00
1,,density,scatter,0.0000000e+00,0.0000000e+00
1,,density,nu-fission,0.0000000e+00,0.0000000e+00
1,,density,scatter,4.1950837e-02,7.3679973e-02
1,,density,nu-fission,0.0000000e+00,0.0000000e+00
1,,density,scatter,0.0000000e+00,0.0000000e+00
1,O16,nuclide_density,nu-fission,0.0000000e+00,0.0000000e+00
1,O16,nuclide_density,scatter,-1.9798569e-02,1.9798569e-02
1,O16,nuclide_density,nu-fission,9.3633316e-01,2.0322303e+00
1,O16,nuclide_density,scatter,-2.2042880e-01,1.6781769e-01
1,O16,nuclide_density,nu-fission,0.0000000e+00,0.0000000e+00
1,O16,nuclide_density,scatter,0.0000000e+00,0.0000000e+00
1,O16,nuclide_density,nu-fission,0.0000000e+00,0.0000000e+00
1,O16,nuclide_density,scatter,0.0000000e+00,0.0000000e+00
1,U235,nuclide_density,nu-fission,0.0000000e+00,0.0000000e+00
1,U235,nuclide_density,scatter,2.3761278e+00,2.3761278e+00
1,U235,nuclide_density,nu-fission,7.7441706e+02,8.6460966e+01
1,U235,nuclide_density,scatter,9.6917110e+01,1.0750583e+01
1,U235,nuclide_density,nu-fission,0.0000000e+00,0.0000000e+00
1,U235,nuclide_density,scatter,0.0000000e+00,0.0000000e+00
1,U235,nuclide_density,nu-fission,0.0000000e+00,0.0000000e+00
1,U235,nuclide_density,scatter,0.0000000e+00,0.0000000e+00
1,,temperature,nu-fission,0.0000000e+00,0.0000000e+00
1,,temperature,scatter,-2.0607997e-06,2.0607997e-06
1,,temperature,nu-fission,3.8846012e-06,3.5405078e-05
1,,temperature,scatter,-6.6772461e-07,2.0750790e-07
1,,temperature,nu-fission,0.0000000e+00,0.0000000e+00
1,,temperature,scatter,0.0000000e+00,0.0000000e+00
1,,temperature,nu-fission,0.0000000e+00,0.0000000e+00
1,,temperature,scatter,0.0000000e+00,0.0000000e+00
3,,density,flux,-7.6179773e+00,5.0326448e+00
3,,density,flux,-1.6242019e+01,6.6231769e+00
1,,density,flux,-2.2394711e-01,5.4534246e-02
@ -175,3 +135,43 @@ d_material,d_nuclide,d_variable,score,mean,std. dev.
3,,density,scatter,4.0762347e-01,3.8504133e+00
3,,density,nu-fission,0.0000000e+00,0.0000000e+00
3,,density,scatter,0.0000000e+00,0.0000000e+00
1,,density,nu-fission,0.0000000e+00,0.0000000e+00
1,,density,scatter,3.9903014e-02,9.1258569e-03
1,,density,nu-fission,0.0000000e+00,0.0000000e+00
1,,density,scatter,9.8213753e-04,9.8213753e-04
1,,density,nu-fission,2.7945436e-02,2.0999385e-02
1,,density,scatter,4.0626164e-01,1.7017647e-02
1,,density,nu-fission,2.4595326e-02,2.1224461e-02
1,,density,scatter,2.6505966e-03,2.3698970e-03
1,,density,nu-fission,0.0000000e+00,0.0000000e+00
1,,density,scatter,-1.2721691e-01,1.8810988e-01
1,,density,nu-fission,0.0000000e+00,0.0000000e+00
1,,density,scatter,0.0000000e+00,0.0000000e+00
1,,density,nu-fission,0.0000000e+00,0.0000000e+00
1,,density,scatter,4.1950837e-02,7.3679973e-02
1,,density,nu-fission,0.0000000e+00,0.0000000e+00
1,,density,scatter,0.0000000e+00,0.0000000e+00
1,O16,nuclide_density,nu-fission,0.0000000e+00,0.0000000e+00
1,O16,nuclide_density,scatter,-1.9798569e-02,1.9798569e-02
1,O16,nuclide_density,nu-fission,9.3633316e-01,2.0322303e+00
1,O16,nuclide_density,scatter,-2.2042880e-01,1.6781769e-01
1,O16,nuclide_density,nu-fission,0.0000000e+00,0.0000000e+00
1,O16,nuclide_density,scatter,0.0000000e+00,0.0000000e+00
1,O16,nuclide_density,nu-fission,0.0000000e+00,0.0000000e+00
1,O16,nuclide_density,scatter,0.0000000e+00,0.0000000e+00
1,U235,nuclide_density,nu-fission,0.0000000e+00,0.0000000e+00
1,U235,nuclide_density,scatter,2.3761278e+00,2.3761278e+00
1,U235,nuclide_density,nu-fission,7.7441706e+02,8.6460966e+01
1,U235,nuclide_density,scatter,9.6917110e+01,1.0750583e+01
1,U235,nuclide_density,nu-fission,0.0000000e+00,0.0000000e+00
1,U235,nuclide_density,scatter,0.0000000e+00,0.0000000e+00
1,U235,nuclide_density,nu-fission,0.0000000e+00,0.0000000e+00
1,U235,nuclide_density,scatter,0.0000000e+00,0.0000000e+00
1,,temperature,nu-fission,0.0000000e+00,0.0000000e+00
1,,temperature,scatter,-2.0607997e-06,2.0607997e-06
1,,temperature,nu-fission,3.8846012e-06,3.5405078e-05
1,,temperature,scatter,-6.6772461e-07,2.0750790e-07
1,,temperature,nu-fission,0.0000000e+00,0.0000000e+00
1,,temperature,scatter,0.0000000e+00,0.0000000e+00
1,,temperature,nu-fission,0.0000000e+00,0.0000000e+00
1,,temperature,scatter,0.0000000e+00,0.0000000e+00

View file

@ -1,9 +1,9 @@
<?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" />
<cell fill="101" id="101" region="10 -11 12 -13" universe="0" />
<cell id="11" material="2 3 void 2" region="-9" universe="11" />
<cell id="12" material="1" region="9" universe="11" />
<lattice id="101">
<pitch>2.0 2.0</pitch>
<outer>1</outer>
@ -13,11 +13,11 @@
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" />
<surface boundary="reflective" coeffs="-3.0" id="10" type="x-plane" />
<surface boundary="reflective" coeffs="3.0" id="11" type="x-plane" />
<surface boundary="reflective" coeffs="-3.0" id="12" type="y-plane" />
<surface boundary="reflective" coeffs="3.0" id="13" type="y-plane" />
<surface coeffs="0.0 0.0 0.3" id="9" type="z-cylinder" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>

View file

@ -4,6 +4,6 @@ Cell
ID = 11
Name =
Fill = [2, 3, None, 2]
Region = -10000
Region = -9
Rotation = None
Translation = None

View file

@ -32,11 +32,11 @@
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="10000" type="energy">
<filter id="1" type="energy">
<bins>0.0 4.0</bins>
</filter>
<tally id="1">
<filters>10000</filters>
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>

View file

@ -310,16 +310,16 @@
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="10000" type="energyfunction">
<filter id="1" type="energyfunction">
<energy>1e-05 0.369 1000.0 100000.0 600000.0 1000000.0 2000000.0 4000000.0 30000000.0</energy>
<y>0.1 0.1 0.1333 0.158 0.18467 0.25618 0.4297 0.48 0.48</y>
</filter>
<tally id="10000">
<tally id="1">
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<tally id="10001">
<filters>10000</filters>
<tally id="2">
<filters>1</filters>
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>

View file

@ -1,2 +1,2 @@
energyfunction nuclide score mean std. dev.
0 ac03185c35fac8 Am241 (n,gamma) 1.00e-01 6.22e-03
0 02180f5f310ee4 Am241 (n,gamma) 1.00e-01 6.22e-03

View file

@ -29,7 +29,7 @@ class FilterEnergyFunHarness(PyAPITestHarness):
assert filt1 == filt2, 'Error with the .from_tabulated1d constructor'
# Make tallies.
tallies = [openmc.Tally(), openmc.Tally()]
tallies = [openmc.Tally(1), openmc.Tally(2)]
for t in tallies:
t.scores = ['(n,gamma)']
t.nuclides = ['Am241']
@ -42,7 +42,7 @@ class FilterEnergyFunHarness(PyAPITestHarness):
sp = openmc.StatePoint(statepoint)
# Use tally arithmetic to compute the branching ratio.
br_tally = sp.tallies[10001] / sp.tallies[10000]
br_tally = sp.tallies[2] / sp.tallies[1]
# Output the tally in a Pandas DataFrame.
return br_tally.get_pandas_dataframe().to_string() + '\n'

View file

@ -324,37 +324,37 @@
<lower_left>-182.07 -182.07 -183.0</lower_left>
<upper_right>182.07 182.07 183.0</upper_right>
</mesh>
<filter id="10000" type="mesh">
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="10001" type="mesh">
<filter id="2" type="mesh">
<bins>2</bins>
</filter>
<filter id="10002" type="mesh">
<filter id="3" type="mesh">
<bins>3</bins>
</filter>
<tally id="10000" name="tally 1">
<filters>10000</filters>
<tally id="1" name="tally 1">
<filters>1</filters>
<scores>total</scores>
</tally>
<tally id="10001" name="tally 2">
<filters>10000</filters>
<tally id="2" name="tally 2">
<filters>1</filters>
<scores>current</scores>
</tally>
<tally id="10002" name="tally 3">
<filters>10001</filters>
<tally id="3" name="tally 3">
<filters>2</filters>
<scores>total</scores>
</tally>
<tally id="10003" name="tally 4">
<filters>10001</filters>
<tally id="4" name="tally 4">
<filters>2</filters>
<scores>current</scores>
</tally>
<tally id="10004" name="tally 5">
<filters>10002</filters>
<tally id="5" name="tally 5">
<filters>3</filters>
<scores>total</scores>
</tally>
<tally id="10005" name="tally 6">
<filters>10002</filters>
<tally id="6" name="tally 6">
<filters>3</filters>
<scores>current</scores>
</tally>
</tallies>

View file

@ -1,86 +1,86 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="10000" material="10000" region="10000 -10001 10002 -10003 10004 -10005" universe="10000" />
<cell id="10001" material="10001" region="10000 -10001 10002 -10003 10005 -10006" universe="10000" />
<cell id="10002" material="10002" region="10000 -10001 10002 -10003 10006 -10007" universe="10000" />
<cell id="10003" material="10003" region="10000 -10001 10002 -10003 10007 -10008" universe="10000" />
<cell id="10004" material="10004" region="10000 -10001 10002 -10003 10008 -10009" universe="10000" />
<cell id="10005" material="10005" region="10000 -10001 10002 -10003 10009 -10010" universe="10000" />
<cell id="10006" material="10006" region="10000 -10001 10002 -10003 10010 -10011" universe="10000" />
<cell id="10007" material="10007" region="10000 -10001 10002 -10003 10011 -10012" universe="10000" />
<cell id="10008" material="10008" region="10000 -10001 10002 -10003 10012 -10013" universe="10000" />
<cell id="10009" material="10009" region="10000 -10001 10002 -10003 10013 -10014" universe="10000" />
<cell id="10010" material="10010" region="10000 -10001 10002 -10003 10014 -10015" universe="10000" />
<cell id="10011" material="10011" region="10000 -10001 10002 -10003 10015 -10016" universe="10000" />
<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" />
<cell id="1" material="1" region="1 -2 3 -4 5 -6" universe="1" />
<cell id="10" material="10" region="1 -2 3 -4 14 -15" universe="1" />
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View file

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View file

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View file

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<filter id="10006" type="energyout">
<filter id="7" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="10013" type="material">
<bins>10001</bins>
<filter id="14" type="material">
<bins>2</bins>
</filter>
<filter id="10026" type="material">
<bins>10002</bins>
<filter id="27" type="material">
<bins>3</bins>
</filter>
<tally id="10000">
<filters>10000 10001</filters>
<tally id="1">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10001">
<filters>10000 10001</filters>
<tally id="2">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10002">
<filters>10000 10001</filters>
<tally id="3">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10003">
<filters>10000 10001</filters>
<tally id="4">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10004">
<filters>10000 10001</filters>
<tally id="5">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10005">
<filters>10000 10001 10006</filters>
<tally id="6">
<filters>1 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10006">
<filters>10000 10001</filters>
<tally id="7">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10007">
<filters>10000 10001 10006</filters>
<tally id="8">
<filters>1 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10008">
<filters>10000 10001 10006</filters>
<tally id="9">
<filters>1 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10009">
<filters>10000 10001 10006</filters>
<tally id="10">
<filters>1 2 7</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10010">
<filters>10013 10001</filters>
<tally id="11">
<filters>14 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10011">
<filters>10013 10001</filters>
<tally id="12">
<filters>14 2</filters>
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10012">
<filters>10013 10001</filters>
<tally id="13">
<filters>14 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10013">
<filters>10013 10001</filters>
<tally id="14">
<filters>14 2</filters>
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10014">
<filters>10013 10001</filters>
<tally id="15">
<filters>14 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10015">
<filters>10013 10001 10006</filters>
<tally id="16">
<filters>14 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10016">
<filters>10013 10001</filters>
<tally id="17">
<filters>14 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10017">
<filters>10013 10001 10006</filters>
<tally id="18">
<filters>14 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10018">
<filters>10013 10001 10006</filters>
<tally id="19">
<filters>14 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10019">
<filters>10013 10001 10006</filters>
<tally id="20">
<filters>14 2 7</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10020">
<filters>10026 10001</filters>
<tally id="21">
<filters>27 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10021">
<filters>10026 10001</filters>
<tally id="22">
<filters>27 2</filters>
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10022">
<filters>10026 10001</filters>
<tally id="23">
<filters>27 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10023">
<filters>10026 10001</filters>
<tally id="24">
<filters>27 2</filters>
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10024">
<filters>10026 10001</filters>
<tally id="25">
<filters>27 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10025">
<filters>10026 10001 10006</filters>
<tally id="26">
<filters>27 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10026">
<filters>10026 10001</filters>
<tally id="27">
<filters>27 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10027">
<filters>10026 10001 10006</filters>
<tally id="28">
<filters>27 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10028">
<filters>10026 10001 10006</filters>
<tally id="29">
<filters>27 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10029">
<filters>10026 10001 10006</filters>
<tally id="30">
<filters>27 2 7</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>

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@ -1,273 +1,273 @@
material group in nuclide mean std. dev.
0 10000 1 total 0.453624 0.021053
0 1 1 total 0.453624 0.021053
material group in nuclide mean std. dev.
0 10000 1 total 0.4074 0.021863
0 1 1 total 0.4074 0.021863
material group in nuclide mean std. dev.
0 10000 1 total 0.4074 0.021863
0 1 1 total 0.4074 0.021863
material group in nuclide mean std. dev.
0 10000 1 total 0.064903 0.004313
0 1 1 total 0.064903 0.004313
material group in nuclide mean std. dev.
0 10000 1 total 0.028048 0.00458
0 1 1 total 0.028048 0.00458
material group in nuclide mean std. dev.
0 10000 1 total 0.036855 0.002622
0 1 1 total 0.036855 0.002622
material group in nuclide mean std. dev.
0 10000 1 total 0.090649 0.00641
0 1 1 total 0.090649 0.00641
material group in nuclide mean std. dev.
0 10000 1 total 7.137954e+06 507363.468222
0 1 1 total 7.137954e+06 507363.468222
material group in nuclide mean std. dev.
0 10000 1 total 0.388721 0.01783
0 1 1 total 0.388721 0.01783
material group in nuclide mean std. dev.
0 10000 1 total 0.389304 0.023076
0 1 1 total 0.389304 0.023076
material group in group out nuclide moment mean std. dev.
0 10000 1 1 total P0 0.389304 0.023146
1 10000 1 1 total P1 0.046224 0.005907
2 10000 1 1 total P2 0.017984 0.002883
3 10000 1 1 total P3 0.006628 0.002457
0 1 1 1 total P0 0.389304 0.023146
1 1 1 1 total P1 0.046224 0.005907
2 1 1 1 total P2 0.017984 0.002883
3 1 1 1 total P3 0.006628 0.002457
material group in group out nuclide moment mean std. dev.
0 10000 1 1 total P0 0.389304 0.023146
1 10000 1 1 total P1 0.046224 0.005907
2 10000 1 1 total P2 0.017984 0.002883
3 10000 1 1 total P3 0.006628 0.002457
0 1 1 1 total P0 0.389304 0.023146
1 1 1 1 total P1 0.046224 0.005907
2 1 1 1 total P2 0.017984 0.002883
3 1 1 1 total P3 0.006628 0.002457
material group in group out nuclide mean std. dev.
0 10000 1 1 total 1.0 0.066111
0 1 1 1 total 1.0 0.066111
material group in group out nuclide mean std. dev.
0 10000 1 1 total 0.085835 0.005592
0 1 1 1 total 0.085835 0.005592
material group in group out nuclide mean std. dev.
0 10000 1 1 total 1.0 0.066111
0 1 1 1 total 1.0 0.066111
material group in group out nuclide moment mean std. dev.
0 10000 1 1 total P0 0.388721 0.031279
1 10000 1 1 total P1 0.046155 0.006407
2 10000 1 1 total P2 0.017957 0.003039
3 10000 1 1 total P3 0.006618 0.002480
0 1 1 1 total P0 0.388721 0.031279
1 1 1 1 total P1 0.046155 0.006407
2 1 1 1 total P2 0.017957 0.003039
3 1 1 1 total P3 0.006618 0.002480
material group in group out nuclide moment mean std. dev.
0 10000 1 1 total P0 0.388721 0.040482
1 10000 1 1 total P1 0.046155 0.007097
2 10000 1 1 total P2 0.017957 0.003262
3 10000 1 1 total P3 0.006618 0.002518
0 1 1 1 total P0 0.388721 0.040482
1 1 1 1 total P1 0.046155 0.007097
2 1 1 1 total P2 0.017957 0.003262
3 1 1 1 total P3 0.006618 0.002518
material group out nuclide mean std. dev.
0 10000 1 total 1.0 0.046071
0 1 1 total 1.0 0.046071
material group out nuclide mean std. dev.
0 10000 1 total 1.0 0.051471
0 1 1 total 1.0 0.051471
material group in nuclide mean std. dev.
0 10000 1 total 4.996730e-07 3.650633e-08
0 1 1 total 4.996730e-07 3.650633e-08
material group in nuclide mean std. dev.
0 10000 1 total 0.090004 0.006367
0 1 1 total 0.090004 0.006367
material group in group out nuclide mean std. dev.
0 10000 1 1 total 0.084542 0.005716
0 1 1 1 total 0.084542 0.005716
material delayedgroup group in nuclide mean std. dev.
0 10000 1 1 total 0.000021 0.000001
1 10000 2 1 total 0.000110 0.000008
2 10000 3 1 total 0.000107 0.000007
3 10000 4 1 total 0.000249 0.000017
4 10000 5 1 total 0.000112 0.000007
5 10000 6 1 total 0.000046 0.000003
0 1 1 1 total 0.000021 0.000001
1 1 2 1 total 0.000110 0.000008
2 1 3 1 total 0.000107 0.000007
3 1 4 1 total 0.000249 0.000017
4 1 5 1 total 0.000112 0.000007
5 1 6 1 total 0.000046 0.000003
material delayedgroup group out nuclide mean std. dev.
0 10000 1 1 total 0.0 0.000000
1 10000 2 1 total 1.0 0.869128
2 10000 3 1 total 1.0 1.414214
3 10000 4 1 total 1.0 0.360359
4 10000 5 1 total 0.0 0.000000
5 10000 6 1 total 0.0 0.000000
0 1 1 1 total 0.0 0.000000
1 1 2 1 total 1.0 0.869128
2 1 3 1 total 1.0 1.414214
3 1 4 1 total 1.0 0.360359
4 1 5 1 total 0.0 0.000000
5 1 6 1 total 0.0 0.000000
material delayedgroup group in nuclide mean std. dev.
0 10000 1 1 total 0.000227 0.000020
1 10000 2 1 total 0.001214 0.000108
2 10000 3 1 total 0.001184 0.000104
3 10000 4 1 total 0.002752 0.000240
4 10000 5 1 total 0.001231 0.000105
5 10000 6 1 total 0.000512 0.000044
0 1 1 1 total 0.000227 0.000020
1 1 2 1 total 0.001214 0.000108
2 1 3 1 total 0.001184 0.000104
3 1 4 1 total 0.002752 0.000240
4 1 5 1 total 0.001231 0.000105
5 1 6 1 total 0.000512 0.000044
material delayedgroup group in nuclide mean std. dev.
0 10000 1 1 total 0.013355 0.001207
1 10000 2 1 total 0.032600 0.002866
2 10000 3 1 total 0.121083 0.010442
3 10000 4 1 total 0.305910 0.025627
4 10000 5 1 total 0.861934 0.068281
5 10000 6 1 total 2.895065 0.230223
0 1 1 1 total 0.013355 0.001207
1 1 2 1 total 0.032600 0.002866
2 1 3 1 total 0.121083 0.010442
3 1 4 1 total 0.305910 0.025627
4 1 5 1 total 0.861934 0.068281
5 1 6 1 total 2.895065 0.230223
material delayedgroup group in group out nuclide mean std. dev.
0 10000 1 1 1 total 0.000000 0.000000
1 10000 2 1 1 total 0.000384 0.000236
2 10000 3 1 1 total 0.000179 0.000180
3 10000 4 1 1 total 0.000730 0.000188
4 10000 5 1 1 total 0.000000 0.000000
5 10000 6 1 1 total 0.000000 0.000000
0 1 1 1 1 total 0.000000 0.000000
1 1 2 1 1 total 0.000384 0.000236
2 1 3 1 1 total 0.000179 0.000180
3 1 4 1 1 total 0.000730 0.000188
4 1 5 1 1 total 0.000000 0.000000
5 1 6 1 1 total 0.000000 0.000000
material group in nuclide mean std. dev.
0 10001 1 total 0.311594 0.013793
0 2 1 total 0.311594 0.013793
material group in nuclide mean std. dev.
0 10001 1 total 0.280977 0.015683
0 2 1 total 0.280977 0.015683
material group in nuclide mean std. dev.
0 10001 1 total 0.280977 0.015683
0 2 1 total 0.280977 0.015683
material group in nuclide mean std. dev.
0 10001 1 total 0.00221 0.000286
0 2 1 total 0.00221 0.000286
material group in nuclide mean std. dev.
0 10001 1 total 0.00221 0.000286
0 2 1 total 0.00221 0.000286
material group in nuclide mean std. dev.
0 10001 1 total 0.0 0.0
0 2 1 total 0.0 0.0
material group in nuclide mean std. dev.
0 10001 1 total 0.0 0.0
0 2 1 total 0.0 0.0
material group in nuclide mean std. dev.
0 10001 1 total 0.0 0.0
0 2 1 total 0.0 0.0
material group in nuclide mean std. dev.
0 10001 1 total 0.309384 0.013551
0 2 1 total 0.309384 0.013551
material group in nuclide mean std. dev.
0 10001 1 total 0.307987 0.029308
0 2 1 total 0.307987 0.029308
material group in group out nuclide moment mean std. dev.
0 10001 1 1 total P0 0.307987 0.029308
1 10001 1 1 total P1 0.030617 0.007464
2 10001 1 1 total P2 0.018911 0.004323
3 10001 1 1 total P3 0.006235 0.003338
0 2 1 1 total P0 0.307987 0.029308
1 2 1 1 total P1 0.030617 0.007464
2 2 1 1 total P2 0.018911 0.004323
3 2 1 1 total P3 0.006235 0.003338
material group in group out nuclide moment mean std. dev.
0 10001 1 1 total P0 0.307987 0.029308
1 10001 1 1 total P1 0.030617 0.007464
2 10001 1 1 total P2 0.018911 0.004323
3 10001 1 1 total P3 0.006235 0.003338
0 2 1 1 total P0 0.307987 0.029308
1 2 1 1 total P1 0.030617 0.007464
2 2 1 1 total P2 0.018911 0.004323
3 2 1 1 total P3 0.006235 0.003338
material group in group out nuclide mean std. dev.
0 10001 1 1 total 1.0 0.095039
0 2 1 1 total 1.0 0.095039
material group in group out nuclide mean std. dev.
0 10001 1 1 total 0.0 0.0
0 2 1 1 total 0.0 0.0
material group in group out nuclide mean std. dev.
0 10001 1 1 total 1.0 0.095039
0 2 1 1 total 1.0 0.095039
material group in group out nuclide moment mean std. dev.
0 10001 1 1 total P0 0.309384 0.032376
1 10001 1 1 total P1 0.030756 0.007617
2 10001 1 1 total P2 0.018997 0.004420
3 10001 1 1 total P3 0.006263 0.003364
0 2 1 1 total P0 0.309384 0.032376
1 2 1 1 total P1 0.030756 0.007617
2 2 1 1 total P2 0.018997 0.004420
3 2 1 1 total P3 0.006263 0.003364
material group in group out nuclide moment mean std. dev.
0 10001 1 1 total P0 0.309384 0.043735
1 10001 1 1 total P1 0.030756 0.008159
2 10001 1 1 total P2 0.018997 0.004775
3 10001 1 1 total P3 0.006263 0.003417
0 2 1 1 total P0 0.309384 0.043735
1 2 1 1 total P1 0.030756 0.008159
2 2 1 1 total P2 0.018997 0.004775
3 2 1 1 total P3 0.006263 0.003417
material group out nuclide mean std. dev.
0 10001 1 total 0.0 0.0
0 2 1 total 0.0 0.0
material group out nuclide mean std. dev.
0 10001 1 total 0.0 0.0
0 2 1 total 0.0 0.0
material group in nuclide mean std. dev.
0 10001 1 total 5.454762e-07 4.949807e-08
0 2 1 total 5.454762e-07 4.949807e-08
material group in nuclide mean std. dev.
0 10001 1 total 0.0 0.0
0 2 1 total 0.0 0.0
material group in group out nuclide mean std. dev.
0 10001 1 1 total 0.0 0.0
0 2 1 1 total 0.0 0.0
material delayedgroup group in nuclide mean std. dev.
0 10001 1 1 total 0.0 0.0
1 10001 2 1 total 0.0 0.0
2 10001 3 1 total 0.0 0.0
3 10001 4 1 total 0.0 0.0
4 10001 5 1 total 0.0 0.0
5 10001 6 1 total 0.0 0.0
0 2 1 1 total 0.0 0.0
1 2 2 1 total 0.0 0.0
2 2 3 1 total 0.0 0.0
3 2 4 1 total 0.0 0.0
4 2 5 1 total 0.0 0.0
5 2 6 1 total 0.0 0.0
material delayedgroup group out nuclide mean std. dev.
0 10001 1 1 total 0.0 0.0
1 10001 2 1 total 0.0 0.0
2 10001 3 1 total 0.0 0.0
3 10001 4 1 total 0.0 0.0
4 10001 5 1 total 0.0 0.0
5 10001 6 1 total 0.0 0.0
0 2 1 1 total 0.0 0.0
1 2 2 1 total 0.0 0.0
2 2 3 1 total 0.0 0.0
3 2 4 1 total 0.0 0.0
4 2 5 1 total 0.0 0.0
5 2 6 1 total 0.0 0.0
material delayedgroup group in nuclide mean std. dev.
0 10001 1 1 total 0.0 0.0
1 10001 2 1 total 0.0 0.0
2 10001 3 1 total 0.0 0.0
3 10001 4 1 total 0.0 0.0
4 10001 5 1 total 0.0 0.0
5 10001 6 1 total 0.0 0.0
0 2 1 1 total 0.0 0.0
1 2 2 1 total 0.0 0.0
2 2 3 1 total 0.0 0.0
3 2 4 1 total 0.0 0.0
4 2 5 1 total 0.0 0.0
5 2 6 1 total 0.0 0.0
material delayedgroup group in nuclide mean std. dev.
0 10001 1 1 total 0.0 0.0
1 10001 2 1 total 0.0 0.0
2 10001 3 1 total 0.0 0.0
3 10001 4 1 total 0.0 0.0
4 10001 5 1 total 0.0 0.0
5 10001 6 1 total 0.0 0.0
0 2 1 1 total 0.0 0.0
1 2 2 1 total 0.0 0.0
2 2 3 1 total 0.0 0.0
3 2 4 1 total 0.0 0.0
4 2 5 1 total 0.0 0.0
5 2 6 1 total 0.0 0.0
material delayedgroup group in group out nuclide mean std. dev.
0 10001 1 1 1 total 0.0 0.0
1 10001 2 1 1 total 0.0 0.0
2 10001 3 1 1 total 0.0 0.0
3 10001 4 1 1 total 0.0 0.0
4 10001 5 1 1 total 0.0 0.0
5 10001 6 1 1 total 0.0 0.0
0 2 1 1 1 total 0.0 0.0
1 2 2 1 1 total 0.0 0.0
2 2 3 1 1 total 0.0 0.0
3 2 4 1 1 total 0.0 0.0
4 2 5 1 1 total 0.0 0.0
5 2 6 1 1 total 0.0 0.0
material group in nuclide mean std. dev.
0 10002 1 total 0.904999 0.043964
0 3 1 total 0.904999 0.043964
material group in nuclide mean std. dev.
0 10002 1 total 0.494581 0.046763
0 3 1 total 0.494581 0.046763
material group in nuclide mean std. dev.
0 10002 1 total 0.494581 0.046763
0 3 1 total 0.494581 0.046763
material group in nuclide mean std. dev.
0 10002 1 total 0.00606 0.000555
0 3 1 total 0.00606 0.000555
material group in nuclide mean std. dev.
0 10002 1 total 0.00606 0.000555
0 3 1 total 0.00606 0.000555
material group in nuclide mean std. dev.
0 10002 1 total 0.0 0.0
0 3 1 total 0.0 0.0
material group in nuclide mean std. dev.
0 10002 1 total 0.0 0.0
0 3 1 total 0.0 0.0
material group in nuclide mean std. dev.
0 10002 1 total 0.0 0.0
0 3 1 total 0.0 0.0
material group in nuclide mean std. dev.
0 10002 1 total 0.898938 0.043493
0 3 1 total 0.898938 0.043493
material group in nuclide mean std. dev.
0 10002 1 total 0.903415 0.043959
0 3 1 total 0.903415 0.043959
material group in group out nuclide moment mean std. dev.
0 10002 1 1 total P0 0.903415 0.043586
1 10002 1 1 total P1 0.410417 0.015877
2 10002 1 1 total P2 0.143301 0.007187
3 10002 1 1 total P3 0.008739 0.003571
0 3 1 1 total P0 0.903415 0.043586
1 3 1 1 total P1 0.410417 0.015877
2 3 1 1 total P2 0.143301 0.007187
3 3 1 1 total P3 0.008739 0.003571
material group in group out nuclide moment mean std. dev.
0 10002 1 1 total P0 0.903415 0.043586
1 10002 1 1 total P1 0.410417 0.015877
2 10002 1 1 total P2 0.143301 0.007187
3 10002 1 1 total P3 0.008739 0.003571
0 3 1 1 total P0 0.903415 0.043586
1 3 1 1 total P1 0.410417 0.015877
2 3 1 1 total P2 0.143301 0.007187
3 3 1 1 total P3 0.008739 0.003571
material group in group out nuclide mean std. dev.
0 10002 1 1 total 1.0 0.056867
0 3 1 1 total 1.0 0.056867
material group in group out nuclide mean std. dev.
0 10002 1 1 total 0.0 0.0
0 3 1 1 total 0.0 0.0
material group in group out nuclide mean std. dev.
0 10002 1 1 total 1.0 0.056867
0 3 1 1 total 1.0 0.056867
material group in group out nuclide moment mean std. dev.
0 10002 1 1 total P0 0.898938 0.067118
1 10002 1 1 total P1 0.408384 0.028127
2 10002 1 1 total P2 0.142591 0.010824
3 10002 1 1 total P3 0.008696 0.003588
0 3 1 1 total P0 0.898938 0.067118
1 3 1 1 total P1 0.408384 0.028127
2 3 1 1 total P2 0.142591 0.010824
3 3 1 1 total P3 0.008696 0.003588
material group in group out nuclide moment mean std. dev.
0 10002 1 1 total P0 0.898938 0.084369
1 10002 1 1 total P1 0.408384 0.036475
2 10002 1 1 total P2 0.142591 0.013525
3 10002 1 1 total P3 0.008696 0.003622
0 3 1 1 total P0 0.898938 0.084369
1 3 1 1 total P1 0.408384 0.036475
2 3 1 1 total P2 0.142591 0.013525
3 3 1 1 total P3 0.008696 0.003622
material group out nuclide mean std. dev.
0 10002 1 total 0.0 0.0
0 3 1 total 0.0 0.0
material group out nuclide mean std. dev.
0 10002 1 total 0.0 0.0
0 3 1 total 0.0 0.0
material group in nuclide mean std. dev.
0 10002 1 total 5.773007e-07 5.322133e-08
0 3 1 total 5.773007e-07 5.322133e-08
material group in nuclide mean std. dev.
0 10002 1 total 0.0 0.0
0 3 1 total 0.0 0.0
material group in group out nuclide mean std. dev.
0 10002 1 1 total 0.0 0.0
0 3 1 1 total 0.0 0.0
material delayedgroup group in nuclide mean std. dev.
0 10002 1 1 total 0.0 0.0
1 10002 2 1 total 0.0 0.0
2 10002 3 1 total 0.0 0.0
3 10002 4 1 total 0.0 0.0
4 10002 5 1 total 0.0 0.0
5 10002 6 1 total 0.0 0.0
0 3 1 1 total 0.0 0.0
1 3 2 1 total 0.0 0.0
2 3 3 1 total 0.0 0.0
3 3 4 1 total 0.0 0.0
4 3 5 1 total 0.0 0.0
5 3 6 1 total 0.0 0.0
material delayedgroup group out nuclide mean std. dev.
0 10002 1 1 total 0.0 0.0
1 10002 2 1 total 0.0 0.0
2 10002 3 1 total 0.0 0.0
3 10002 4 1 total 0.0 0.0
4 10002 5 1 total 0.0 0.0
5 10002 6 1 total 0.0 0.0
0 3 1 1 total 0.0 0.0
1 3 2 1 total 0.0 0.0
2 3 3 1 total 0.0 0.0
3 3 4 1 total 0.0 0.0
4 3 5 1 total 0.0 0.0
5 3 6 1 total 0.0 0.0
material delayedgroup group in nuclide mean std. dev.
0 10002 1 1 total 0.0 0.0
1 10002 2 1 total 0.0 0.0
2 10002 3 1 total 0.0 0.0
3 10002 4 1 total 0.0 0.0
4 10002 5 1 total 0.0 0.0
5 10002 6 1 total 0.0 0.0
0 3 1 1 total 0.0 0.0
1 3 2 1 total 0.0 0.0
2 3 3 1 total 0.0 0.0
3 3 4 1 total 0.0 0.0
4 3 5 1 total 0.0 0.0
5 3 6 1 total 0.0 0.0
material delayedgroup group in nuclide mean std. dev.
0 10002 1 1 total 0.0 0.0
1 10002 2 1 total 0.0 0.0
2 10002 3 1 total 0.0 0.0
3 10002 4 1 total 0.0 0.0
4 10002 5 1 total 0.0 0.0
5 10002 6 1 total 0.0 0.0
0 3 1 1 total 0.0 0.0
1 3 2 1 total 0.0 0.0
2 3 3 1 total 0.0 0.0
3 3 4 1 total 0.0 0.0
4 3 5 1 total 0.0 0.0
5 3 6 1 total 0.0 0.0
material delayedgroup group in group out nuclide mean std. dev.
0 10002 1 1 1 total 0.0 0.0
1 10002 2 1 1 total 0.0 0.0
2 10002 3 1 1 total 0.0 0.0
3 10002 4 1 1 total 0.0 0.0
4 10002 5 1 1 total 0.0 0.0
5 10002 6 1 1 total 0.0 0.0
0 3 1 1 1 total 0.0 0.0
1 3 2 1 1 total 0.0 0.0
2 3 3 1 1 total 0.0 0.0
3 3 4 1 1 total 0.0 0.0
4 3 5 1 1 total 0.0 0.0
5 3 6 1 1 total 0.0 0.0

View file

@ -1,52 +1,52 @@
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<cell id="10004" material="10001" name="guide tube clad" region="10000 -10001" universe="10001" />
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10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 10000 </universes>
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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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
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1 1 1 1 1 1 1 1 1 1 1 1 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>
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<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" />
<surface coeffs="0 0 0.39218" id="1" name="Fuel OR" type="z-cylinder" />
<surface coeffs="0 0 0.4572" id="2" name="Clad OR" type="z-cylinder" />
<surface boundary="reflective" coeffs="-10.71" id="3" type="x-plane" />
<surface boundary="reflective" coeffs="10.71" id="4" type="x-plane" />
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<surface boundary="reflective" coeffs="10.71" id="6" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="10000" name="Fuel">
<material id="1" 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">
<material id="2" name="Cladding">
<density units="g/cm3" value="6.55" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
@ -54,7 +54,7 @@
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="10002" name="Hot borated water">
<material id="3" name="Hot borated water">
<density units="g/cm3" value="0.740582" />
<nuclide ao="0.049457" name="H1" />
<nuclide ao="0.024672" name="O16" />
@ -77,386 +77,386 @@
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<tally id="14">
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<tally id="10014">
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<tally id="15">
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<tally id="18">
<filters>1 2</filters>
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<tally id="10018">
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<tally id="19">
<filters>1 2</filters>
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<tally id="10019">
<filters>10000 10001</filters>
<tally id="20">
<filters>1 2</filters>
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<tally id="10020">
<filters>10000 10001</filters>
<tally id="21">
<filters>1 2</filters>
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<tally id="22">
<filters>1 2</filters>
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<tally id="23">
<filters>1 2</filters>
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<filters>10000 10001</filters>
<tally id="24">
<filters>1 2</filters>
<nuclides>total</nuclides>
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<filters>10000 10001</filters>
<tally id="25">
<filters>1 2</filters>
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<filters>10000 10001</filters>
<tally id="26">
<filters>1 2</filters>
<nuclides>total</nuclides>
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<tally id="10026">
<filters>10000 10001 10004</filters>
<tally id="27">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
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<estimator>analog</estimator>
</tally>
<tally id="10027">
<filters>10000 10001</filters>
<tally id="28">
<filters>1 2</filters>
<nuclides>total</nuclides>
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<tally id="10028">
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<tally id="29">
<filters>1 2 5</filters>
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<tally id="52">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10052">
<filters>10000 10001</filters>
<tally id="53">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10053">
<filters>10000 10058 10001</filters>
<tally id="54">
<filters>1 59 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10054">
<filters>10000 10058 10001</filters>
<tally id="55">
<filters>1 59 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10055">
<filters>10000 10058 10004</filters>
<tally id="56">
<filters>1 59 5</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10056">
<filters>10000 10001</filters>
<tally id="57">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10057">
<filters>10000 10058 10001</filters>
<tally id="58">
<filters>1 59 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10058">
<filters>10000 10058 10001</filters>
<tally id="59">
<filters>1 59 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10059">
<filters>10000 10058 10001</filters>
<tally id="60">
<filters>1 59 2</filters>
<nuclides>total</nuclides>
<scores>decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10060">
<filters>10000 10001</filters>
<tally id="61">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10061">
<filters>10000 10058 10001 10004</filters>
<tally id="62">
<filters>1 59 2 5</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>

File diff suppressed because it is too large Load diff

View file

@ -1,34 +1,34 @@
domain=10000 type=total
domain=1 type=total
[4.14825464e-01 6.60169863e-01]
[2.27929105e-02 4.75188999e-02]
domain=10000 type=transport
domain=1 type=transport
[3.63092031e-01 6.44850709e-01]
[2.38384843e-02 4.76746408e-02]
domain=10000 type=nu-transport
domain=1 type=nu-transport
[3.63092031e-01 6.44850709e-01]
[2.38384843e-02 4.76746408e-02]
domain=10000 type=absorption
domain=1 type=absorption
[2.74078431e-02 2.64510714e-01]
[2.69249666e-03 2.33670618e-02]
domain=10000 type=capture
domain=1 type=capture
[1.98445483e-02 7.17193458e-02]
[2.64330389e-03 2.52078411e-02]
domain=10000 type=fission
domain=1 type=fission
[7.56329483e-03 1.92791369e-01]
[5.08483896e-04 1.71059103e-02]
domain=10000 type=nu-fission
domain=1 type=nu-fission
[1.94317397e-02 4.69774728e-01]
[1.32297611e-03 4.16819716e-02]
domain=10000 type=kappa-fission
domain=1 type=kappa-fission
[1.47456979e+06 3.72868925e+07]
[9.92353629e+04 3.30837549e+06]
domain=10000 type=scatter
domain=1 type=scatter
[3.87417621e-01 3.95659148e-01]
[2.06257343e-02 2.51250447e-02]
domain=10000 type=nu-scatter
domain=1 type=nu-scatter
[3.85188361e-01 4.12389370e-01]
[2.69456191e-02 1.54252759e-02]
domain=10000 type=scatter matrix
domain=1 type=scatter matrix
[[[3.84199430e-01 5.18702806e-02 2.00688439e-02 9.47771503e-03]
[9.88930322e-04 -2.07234582e-04 -1.03366173e-04 2.34290606e-04]]
@ -39,7 +39,7 @@ domain=10000 type=scatter matrix
[[9.24883397e-04 7.67907131e-04 4.93918903e-04 1.71542390e-04]
[1.52449343e-02 4.50172764e-03 1.05507486e-02 1.04381870e-02]]]
domain=10000 type=nu-scatter matrix
domain=1 type=nu-scatter matrix
[[[3.84199430e-01 5.18702806e-02 2.00688439e-02 9.47771503e-03]
[9.88930322e-04 -2.07234582e-04 -1.03366173e-04 2.34290606e-04]]
@ -50,22 +50,22 @@ domain=10000 type=nu-scatter matrix
[[9.24883397e-04 7.67907131e-04 4.93918903e-04 1.71542390e-04]
[1.52449343e-02 4.50172764e-03 1.05507486e-02 1.04381870e-02]]]
domain=10000 type=multiplicity matrix
domain=1 type=multiplicity matrix
[[1.00000000e+00 1.00000000e+00]
[1.00000000e+00 1.00000000e+00]]
[[7.85164550e-02 6.87184271e-01]
[1.41421356e+00 4.11303488e-02]]
domain=10000 type=nu-fission matrix
domain=1 type=nu-fission matrix
[[2.01424221e-02 0.00000000e+00]
[4.54366342e-01 0.00000000e+00]]
[[3.14909051e-03 0.00000000e+00]
[2.74255162e-02 0.00000000e+00]]
domain=10000 type=scatter probability matrix
domain=1 type=scatter probability matrix
[[9.97432606e-01 2.56739409e-03]
[2.24215247e-03 9.97757848e-01]]
[[7.82243018e-02 1.25560869e-03]
[2.24310192e-03 4.10531468e-02]]
domain=10000 type=consistent scatter matrix
domain=1 type=consistent scatter matrix
[[[3.86422967e-01 5.21704775e-02 2.01849914e-02 9.53256688e-03]
[9.94653712e-04 -2.08433942e-04 -1.03964400e-04 2.35646553e-04]]
@ -76,7 +76,7 @@ domain=10000 type=consistent scatter matrix
[[8.89289900e-04 7.38354757e-04 4.74910776e-04 1.64940700e-04]
[2.98710064e-02 4.44330993e-03 1.01307463e-02 1.00367467e-02]]]
domain=10000 type=consistent nu-scatter matrix
domain=1 type=consistent nu-scatter matrix
[[[3.86422967e-01 5.21704775e-02 2.01849914e-02 9.53256688e-03]
[9.94653712e-04 -2.08433942e-04 -1.03964400e-04 2.35646553e-04]]
@ -87,24 +87,24 @@ domain=10000 type=consistent nu-scatter matrix
[[1.53780011e-03 1.27679627e-03 8.21237084e-04 2.85222881e-04]
[3.39988352e-02 4.49065920e-03 1.01338659e-02 1.00452944e-02]]]
domain=10000 type=chi
domain=1 type=chi
[1.00000000e+00 0.00000000e+00]
[4.60705493e-02 0.00000000e+00]
domain=10000 type=chi-prompt
domain=1 type=chi-prompt
[1.00000000e+00 0.00000000e+00]
[5.14714845e-02 0.00000000e+00]
domain=10000 type=inverse-velocity
domain=1 type=inverse-velocity
[5.70932437e-08 2.85573948e-06]
[4.68793810e-09 2.44216368e-07]
domain=10000 type=prompt-nu-fission
domain=1 type=prompt-nu-fission
[1.92392209e-02 4.66718979e-01]
[1.30950644e-03 4.14108424e-02]
domain=10000 type=prompt-nu-fission matrix
domain=1 type=prompt-nu-fission matrix
[[2.01424221e-02 0.00000000e+00]
[4.45819055e-01 0.00000000e+00]]
[[3.14909051e-03 0.00000000e+00]
[2.86750878e-02 0.00000000e+00]]
domain=10000 type=delayed-nu-fission
domain=1 type=delayed-nu-fission
[[4.31687649e-06 1.06974147e-04]
[2.69760050e-05 5.52167849e-04]
[2.84366794e-05 5.27147626e-04]
@ -117,7 +117,7 @@ domain=10000 type=delayed-nu-fission
[5.22610330e-06 1.04867938e-04]
[2.99830756e-06 4.29944539e-05]
[1.22654681e-06 1.80102228e-05]]
domain=10000 type=chi-delayed
domain=1 type=chi-delayed
[[0.00000000e+00 0.00000000e+00]
[1.00000000e+00 0.00000000e+00]
[1.00000000e+00 0.00000000e+00]
@ -130,7 +130,7 @@ domain=10000 type=chi-delayed
[3.60359016e-01 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
domain=10000 type=beta
domain=1 type=beta
[[2.22155945e-04 2.27713711e-04]
[1.38824446e-03 1.17538858e-03]
[1.46341397e-03 1.12212853e-03]
@ -143,7 +143,7 @@ domain=10000 type=beta
[3.21434953e-04 2.72840272e-04]
[1.82980531e-04 1.11860871e-04]
[7.48900067e-05 4.68581181e-05]]
domain=10000 type=decay-rate
domain=1 type=decay-rate
[[1.34450193e-02 1.33360001e-02]
[3.20638663e-02 3.27389978e-02]
[1.22136025e-01 1.20780007e-01]
@ -156,7 +156,7 @@ domain=10000 type=decay-rate
[2.71748572e-02 3.28353145e-02]
[7.93682892e-02 9.21238900e-02]
[2.66253284e-01 3.09396760e-01]]
domain=10000 type=delayed-nu-fission matrix
domain=1 type=delayed-nu-fission matrix
[[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
@ -191,37 +191,37 @@ domain=10000 type=delayed-nu-fission matrix
[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]]
domain=10001 type=total
domain=2 type=total
[3.13737666e-01 3.00821380e-01]
[1.55819223e-02 2.80524816e-02]
domain=10001 type=transport
domain=2 type=transport
[2.75508079e-01 3.12035015e-01]
[1.77418855e-02 3.23843473e-02]
domain=10001 type=nu-transport
domain=2 type=nu-transport
[2.75508079e-01 3.12035015e-01]
[1.77418855e-02 3.23843473e-02]
domain=10001 type=absorption
domain=2 type=absorption
[1.57499139e-03 5.40037826e-03]
[3.22547919e-04 6.18139027e-04]
domain=10001 type=capture
domain=2 type=capture
[1.57499139e-03 5.40037826e-03]
[3.22547919e-04 6.18139027e-04]
domain=10001 type=fission
domain=2 type=fission
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
domain=10001 type=nu-fission
domain=2 type=nu-fission
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
domain=10001 type=kappa-fission
domain=2 type=kappa-fission
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
domain=10001 type=scatter
domain=2 type=scatter
[3.12162675e-01 2.95421002e-01]
[1.53219430e-02 2.74455213e-02]
domain=10001 type=nu-scatter
domain=2 type=nu-scatter
[3.10120713e-01 2.96264249e-01]
[3.37881037e-02 4.37922226e-02]
domain=10001 type=scatter matrix
domain=2 type=scatter matrix
[[[3.10120713e-01 3.82295876e-02 2.07449405e-02 7.96429620e-03]
[0.00000000e+00 0.00000000e+00 0.00000000e+00 0.00000000e+00]]
@ -232,7 +232,7 @@ domain=10001 type=scatter matrix
[[0.00000000e+00 0.00000000e+00 0.00000000e+00 0.00000000e+00]
[4.37922226e-02 1.61803653e-02 1.15039636e-02 7.32884528e-03]]]
domain=10001 type=nu-scatter matrix
domain=2 type=nu-scatter matrix
[[[3.10120713e-01 3.82295876e-02 2.07449405e-02 7.96429620e-03]
[0.00000000e+00 0.00000000e+00 0.00000000e+00 0.00000000e+00]]
@ -243,22 +243,22 @@ domain=10001 type=nu-scatter matrix
[[0.00000000e+00 0.00000000e+00 0.00000000e+00 0.00000000e+00]
[4.37922226e-02 1.61803653e-02 1.15039636e-02 7.32884528e-03]]]
domain=10001 type=multiplicity matrix
domain=2 type=multiplicity matrix
[[1.00000000e+00 0.00000000e+00]
[0.00000000e+00 1.00000000e+00]]
[[1.08778697e-01 0.00000000e+00]
[0.00000000e+00 1.42427173e-01]]
domain=10001 type=nu-fission matrix
domain=2 type=nu-fission matrix
[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
domain=10001 type=scatter probability matrix
domain=2 type=scatter probability matrix
[[1.00000000e+00 0.00000000e+00]
[0.00000000e+00 1.00000000e+00]]
[[1.08778697e-01 0.00000000e+00]
[0.00000000e+00 1.42427173e-01]]
domain=10001 type=consistent scatter matrix
domain=2 type=consistent scatter matrix
[[[3.12162675e-01 3.84813069e-02 2.08815337e-02 8.01673640e-03]
[0.00000000e+00 0.00000000e+00 0.00000000e+00 0.00000000e+00]]
@ -269,7 +269,7 @@ domain=10001 type=consistent scatter matrix
[[0.00000000e+00 0.00000000e+00 0.00000000e+00 0.00000000e+00]
[5.02358893e-02 1.61616720e-02 1.14951123e-02 7.31312479e-03]]]
domain=10001 type=consistent nu-scatter matrix
domain=2 type=consistent nu-scatter matrix
[[[3.12162675e-01 3.84813069e-02 2.08815337e-02 8.01673640e-03]
[0.00000000e+00 0.00000000e+00 0.00000000e+00 0.00000000e+00]]
@ -280,24 +280,24 @@ domain=10001 type=consistent nu-scatter matrix
[[0.00000000e+00 0.00000000e+00 0.00000000e+00 0.00000000e+00]
[6.55288678e-02 1.62399493e-02 1.15634161e-02 7.32785650e-03]]]
domain=10001 type=chi
domain=2 type=chi
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
domain=10001 type=chi-prompt
domain=2 type=chi-prompt
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
domain=10001 type=inverse-velocity
domain=2 type=inverse-velocity
[5.99597929e-08 2.98549016e-06]
[4.55308445e-09 3.41701982e-07]
domain=10001 type=prompt-nu-fission
domain=2 type=prompt-nu-fission
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
domain=10001 type=prompt-nu-fission matrix
domain=2 type=prompt-nu-fission matrix
[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
domain=10001 type=delayed-nu-fission
domain=2 type=delayed-nu-fission
[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
@ -310,7 +310,7 @@ domain=10001 type=delayed-nu-fission
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
domain=10001 type=chi-delayed
domain=2 type=chi-delayed
[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
@ -323,7 +323,7 @@ domain=10001 type=chi-delayed
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
domain=10001 type=beta
domain=2 type=beta
[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
@ -336,7 +336,7 @@ domain=10001 type=beta
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
domain=10001 type=decay-rate
domain=2 type=decay-rate
[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
@ -349,7 +349,7 @@ domain=10001 type=decay-rate
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
domain=10001 type=delayed-nu-fission matrix
domain=2 type=delayed-nu-fission matrix
[[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
@ -384,37 +384,37 @@ domain=10001 type=delayed-nu-fission matrix
[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]]
domain=10002 type=total
domain=3 type=total
[6.64572195e-01 2.05238389e+00]
[3.12147473e-02 2.24342891e-01]
domain=10002 type=transport
domain=3 type=transport
[2.83322749e-01 1.49973953e+00]
[3.52061127e-02 2.30902118e-01]
domain=10002 type=nu-transport
domain=3 type=nu-transport
[2.83322749e-01 1.49973953e+00]
[3.52061127e-02 2.30902118e-01]
domain=10002 type=absorption
domain=3 type=absorption
[6.90399495e-04 3.16872549e-02]
[4.41475663e-05 3.74655831e-03]
domain=10002 type=capture
domain=3 type=capture
[6.90399495e-04 3.16872549e-02]
[4.41475663e-05 3.74655831e-03]
domain=10002 type=fission
domain=3 type=fission
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
domain=10002 type=nu-fission
domain=3 type=nu-fission
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
domain=10002 type=kappa-fission
domain=3 type=kappa-fission
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
domain=10002 type=scatter
domain=3 type=scatter
[6.63881795e-01 2.02069663e+00]
[3.11726794e-02 2.20604438e-01]
domain=10002 type=nu-scatter
domain=3 type=nu-scatter
[6.71269157e-01 2.03538818e+00]
[2.61863693e-02 2.58060310e-01]
domain=10002 type=scatter matrix
domain=3 type=scatter matrix
[[[6.39901439e-01 3.81167422e-01 1.52391887e-01 9.14802163e-03]
[3.13677176e-02 8.75772258e-03 -2.56790088e-03 -3.78480261e-03]]
@ -425,7 +425,7 @@ domain=10002 type=scatter matrix
[[4.44850361e-04 4.01320154e-04 3.20649120e-04 2.14573982e-04]
[2.57799870e-01 5.12359026e-02 1.30198161e-02 8.31235197e-03]]]
domain=10002 type=nu-scatter matrix
domain=3 type=nu-scatter matrix
[[[6.39901439e-01 3.81167422e-01 1.52391887e-01 9.14802163e-03]
[3.13677176e-02 8.75772258e-03 -2.56790088e-03 -3.78480261e-03]]
@ -436,22 +436,22 @@ domain=10002 type=nu-scatter matrix
[[4.44850361e-04 4.01320154e-04 3.20649120e-04 2.14573982e-04]
[2.57799870e-01 5.12359026e-02 1.30198161e-02 8.31235197e-03]]]
domain=10002 type=multiplicity matrix
domain=3 type=multiplicity matrix
[[1.00000000e+00 1.00000000e+00]
[1.00000000e+00 1.00000000e+00]]
[[3.86091908e-02 6.76673480e-02]
[1.41421356e+00 1.35929207e-01]]
domain=10002 type=nu-fission matrix
domain=3 type=nu-fission matrix
[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
domain=10002 type=scatter probability matrix
domain=3 type=scatter probability matrix
[[9.53271028e-01 4.67289720e-02]
[2.17817469e-04 9.99782183e-01]]
[[3.60184962e-02 2.54736726e-03]
[2.18820864e-04 1.35884974e-01]]
domain=10002 type=consistent scatter matrix
domain=3 type=consistent scatter matrix
[[[6.32859281e-01 3.76972649e-01 1.50714804e-01 9.04734705e-03]
[3.10225138e-02 8.66134326e-03 -2.53964096e-03 -3.74315061e-03]]
@ -462,7 +462,7 @@ domain=10002 type=consistent scatter matrix
[[4.44773843e-04 4.01251123e-04 3.20593966e-04 2.14537073e-04]
[3.52193929e-01 7.91402819e-02 1.84875925e-02 8.77085752e-03]]]
domain=10002 type=consistent nu-scatter matrix
domain=3 type=consistent nu-scatter matrix
[[[6.32859281e-01 3.76972649e-01 1.50714804e-01 9.04734705e-03]
[3.10225138e-02 8.66134326e-03 -2.53964096e-03 -3.74315061e-03]]
@ -473,24 +473,24 @@ domain=10002 type=consistent nu-scatter matrix
[[7.65033031e-04 6.90171798e-04 5.51437493e-04 3.69014387e-04]
[4.46600759e-01 1.04874946e-01 2.38091367e-02 9.39676938e-03]]]
domain=10002 type=chi
domain=3 type=chi
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
domain=10002 type=chi-prompt
domain=3 type=chi-prompt
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
domain=10002 type=inverse-velocity
domain=3 type=inverse-velocity
[6.02207835e-08 3.04495548e-06]
[3.78043705e-09 3.60007679e-07]
domain=10002 type=prompt-nu-fission
domain=3 type=prompt-nu-fission
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
domain=10002 type=prompt-nu-fission matrix
domain=3 type=prompt-nu-fission matrix
[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
domain=10002 type=delayed-nu-fission
domain=3 type=delayed-nu-fission
[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
@ -503,7 +503,7 @@ domain=10002 type=delayed-nu-fission
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
domain=10002 type=chi-delayed
domain=3 type=chi-delayed
[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
@ -516,7 +516,7 @@ domain=10002 type=chi-delayed
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
domain=10002 type=beta
domain=3 type=beta
[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
@ -529,7 +529,7 @@ domain=10002 type=beta
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
domain=10002 type=decay-rate
domain=3 type=decay-rate
[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
@ -542,7 +542,7 @@ domain=10002 type=decay-rate
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]
domain=10002 type=delayed-nu-fission matrix
domain=3 type=delayed-nu-fission matrix
[[[0.00000000e+00 0.00000000e+00]
[0.00000000e+00 0.00000000e+00]]

View file

@ -314,386 +314,386 @@
<lower_left>-100.0 -100.0</lower_left>
<width>100.0 100.0</width>
</mesh>
<filter id="10000" type="mesh">
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<filter id="10001" type="energy">
<filter id="2" type="energy">
<bins>0.0 20000000.0</bins>
</filter>
<filter id="10004" type="energyout">
<filter id="5" type="energyout">
<bins>0.0 20000000.0</bins>
</filter>
<filter id="10058" type="delayedgroup">
<filter id="59" type="delayedgroup">
<bins>1 2 3 4 5 6</bins>
</filter>
<tally id="10000">
<filters>10000 10001</filters>
<tally id="1">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10001">
<filters>10000 10001</filters>
<tally id="2">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10002">
<filters>10000 10001</filters>
<tally id="3">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10003">
<filters>10000 10001</filters>
<tally id="4">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10004">
<filters>10000 10001</filters>
<tally id="5">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10005">
<filters>10000 10004</filters>
<tally id="6">
<filters>1 5</filters>
<nuclides>total</nuclides>
<scores>scatter-1</scores>
<estimator>analog</estimator>
</tally>
<tally id="10006">
<filters>10000 10001</filters>
<tally id="7">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10007">
<filters>10000 10001</filters>
<tally id="8">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10008">
<filters>10000 10001</filters>
<tally id="9">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10009">
<filters>10000 10004</filters>
<tally id="10">
<filters>1 5</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-1</scores>
<estimator>analog</estimator>
</tally>
<tally id="10010">
<filters>10000 10001</filters>
<tally id="11">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10011">
<filters>10000 10001</filters>
<tally id="12">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10012">
<filters>10000 10001</filters>
<tally id="13">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10013">
<filters>10000 10001</filters>
<tally id="14">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10014">
<filters>10000 10001</filters>
<tally id="15">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10015">
<filters>10000 10001</filters>
<tally id="16">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10016">
<filters>10000 10001</filters>
<tally id="17">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10017">
<filters>10000 10001</filters>
<tally id="18">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10018">
<filters>10000 10001</filters>
<tally id="19">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10019">
<filters>10000 10001</filters>
<tally id="20">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10020">
<filters>10000 10001</filters>
<tally id="21">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>kappa-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10021">
<filters>10000 10001</filters>
<tally id="22">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10022">
<filters>10000 10001</filters>
<tally id="23">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10023">
<filters>10000 10001</filters>
<tally id="24">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10024">
<filters>10000 10001</filters>
<tally id="25">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10025">
<filters>10000 10001</filters>
<tally id="26">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10026">
<filters>10000 10001 10004</filters>
<tally id="27">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10027">
<filters>10000 10001</filters>
<tally id="28">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10028">
<filters>10000 10001 10004</filters>
<tally id="29">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10029">
<filters>10000 10001 10004</filters>
<tally id="30">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10030">
<filters>10000 10001 10004</filters>
<tally id="31">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10031">
<filters>10000 10001</filters>
<tally id="32">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10032">
<filters>10000 10001 10004</filters>
<tally id="33">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10033">
<filters>10000 10001 10004</filters>
<tally id="34">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10034">
<filters>10000 10001</filters>
<tally id="35">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10035">
<filters>10000 10001</filters>
<tally id="36">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10036">
<filters>10000 10001 10004</filters>
<tally id="37">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10037">
<filters>10000 10001</filters>
<tally id="38">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10038">
<filters>10000 10001</filters>
<tally id="39">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10039">
<filters>10000 10001 10004</filters>
<tally id="40">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10040">
<filters>10000 10001 10004</filters>
<tally id="41">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="10041">
<filters>10000 10001 10004</filters>
<tally id="42">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>scatter-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="10042">
<filters>10000 10001</filters>
<tally id="43">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10043">
<filters>10000 10004</filters>
<tally id="44">
<filters>1 5</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10044">
<filters>10000 10001</filters>
<tally id="45">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10045">
<filters>10000 10004</filters>
<tally id="46">
<filters>1 5</filters>
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10046">
<filters>10000 10001</filters>
<tally id="47">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10047">
<filters>10000 10001</filters>
<tally id="48">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>inverse-velocity</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10048">
<filters>10000 10001</filters>
<tally id="49">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10049">
<filters>10000 10001</filters>
<tally id="50">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10050">
<filters>10000 10001</filters>
<tally id="51">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10051">
<filters>10000 10001 10004</filters>
<tally id="52">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10052">
<filters>10000 10001</filters>
<tally id="53">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10053">
<filters>10000 10058 10001</filters>
<tally id="54">
<filters>1 59 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10054">
<filters>10000 10058 10001</filters>
<tally id="55">
<filters>1 59 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10055">
<filters>10000 10058 10004</filters>
<tally id="56">
<filters>1 59 5</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10056">
<filters>10000 10001</filters>
<tally id="57">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10057">
<filters>10000 10058 10001</filters>
<tally id="58">
<filters>1 59 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10058">
<filters>10000 10058 10001</filters>
<tally id="59">
<filters>1 59 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10059">
<filters>10000 10058 10001</filters>
<tally id="60">
<filters>1 59 2</filters>
<nuclides>total</nuclides>
<scores>decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10060">
<filters>10000 10001</filters>
<tally id="61">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10061">
<filters>10000 10058 10001 10004</filters>
<tally id="62">
<filters>1 59 2 5</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>

File diff suppressed because it is too large Load diff

File diff suppressed because it is too large Load diff

File diff suppressed because it is too large Load diff

View file

@ -1 +1 @@
ea1c7567cb5399ab26297b5df0c1c21b52863303746d04f1698760d88b1aafb625d5743969ad30b194c353d106ed4287a8bc755ea6404c2f5dafb2ea930444a7
174d1593a15de41e2aba88cc4c48fc3a400314b400571a0328dfdf7482df111b3ac9701dbd196d06668b49d3acaa67d766702db0942c03140e9e004942f7bdfd

View file

@ -1,9 +1,9 @@
<?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" />
<cell fill="101" id="101" region="2 -3 4 -5" universe="0" />
<cell id="11" material="2" region="-1" temperature="500 0 700 800" universe="11" />
<cell id="12" material="1" region="1" universe="11" />
<lattice id="101">
<pitch>2.0 2.0</pitch>
<outer>1</outer>
@ -13,11 +13,11 @@
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" />
<surface coeffs="0.0 0.0 0.3" id="1" type="z-cylinder" />
<surface boundary="reflective" coeffs="-3.0" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="3.0" id="3" type="x-plane" />
<surface boundary="reflective" coeffs="-3.0" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="3.0" id="5" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
@ -48,7 +48,7 @@
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<tally id="10000">
<tally id="1">
<nuclides>U235 O16 total</nuclides>
<scores>total fission (n,gamma) elastic (n,p)</scores>
</tally>

View file

@ -35,7 +35,7 @@ Cell
ID = 11
Name =
Fill = Material 2
Region = -10000
Region = -1
Rotation = None
Temperature = [ 500. 0. 700. 800.]
Translation = None

View file

@ -1,7 +1,7 @@
<?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" />
<cell id="1" material="1" region="-9" universe="0" />
<surface boundary="reflective" coeffs="100" id="9" type="x-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>

View file

@ -314,192 +314,192 @@
<lower_left>-182.07 -182.07</lower_left>
<upper_right>182.07 182.07</upper_right>
</mesh>
<filter id="10000" type="azimuthal">
<filter id="1" type="azimuthal">
<bins>-3.14159 -1.885 -0.6283 0.6283 1.885 3.14159</bins>
</filter>
<filter id="10001" type="mesh">
<filter id="2" type="mesh">
<bins>1</bins>
</filter>
<filter id="10002" type="cellborn">
<filter id="3" type="cellborn">
<bins>10 21 22 23</bins>
</filter>
<filter id="10003" type="delayedgroup">
<filter id="4" type="delayedgroup">
<bins>1 2 3 4 5 6</bins>
</filter>
<filter id="10004" type="energy">
<filter id="5" type="energy">
<bins>0.0 0.253 1000.0 1000000.0 20000000.0</bins>
</filter>
<filter id="10005" type="energyout">
<filter id="6" type="energyout">
<bins>0.0 0.253 1000.0 1000000.0 20000000.0</bins>
</filter>
<filter id="10006" type="material">
<filter id="7" type="material">
<bins>1 2 3 4</bins>
</filter>
<filter id="10007" type="mu">
<filter id="8" type="mu">
<bins>-1.0 -0.5 0.0 0.5 1.0</bins>
</filter>
<filter id="10008" type="polar">
<filter id="9" type="polar">
<bins>0.0 0.6283 1.2566 1.885 2.5132 3.14159</bins>
</filter>
<filter id="10009" type="universe">
<filter id="10" type="universe">
<bins>1 2 3 4 6 8</bins>
</filter>
<filter id="10010" type="cell">
<filter id="11" type="cell">
<bins>10 21 22 23 60</bins>
</filter>
<filter id="10011" type="cell">
<filter id="12" type="cell">
<bins>21 22 23 27 28 29 60</bins>
</filter>
<tally id="10000">
<filters>10000</filters>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10001">
<filters>10000</filters>
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View file

@ -309,14 +309,14 @@
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View file

@ -314,25 +314,25 @@
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View file

@ -310,37 +310,37 @@
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View file

@ -1,428 +1,428 @@
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