Merge pull request #892 from paulromano/python-improvements

IDManagerMixin and other miscellaneous Python changes
This commit is contained in:
Sterling Harper 2017-06-15 19:22:23 -04:00 committed by GitHub
commit 0d71494b3e
76 changed files with 11146 additions and 11270 deletions

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@ -401,14 +401,6 @@ distributions.
NumPy is used extensively within the Python API for its powerful
N-dimensional array.
`h5py <http://www.h5py.org/>`_
h5py provides Python bindings to the HDF5 library. Since OpenMC outputs
various HDF5 files, h5py is needed to provide access to data within these
files from Python.
.. admonition:: Optional
:class: note
`SciPy <https://www.scipy.org/>`_
SciPy's special functions, sparse matrices, and spatial data structures
are used for several optional features in the API.
@ -417,6 +409,14 @@ distributions.
Pandas is used to generate tally DataFrames as demonstrated in
:ref:`examples_pandas` example notebook.
`h5py <http://www.h5py.org/>`_
h5py provides Python bindings to the HDF5 library. Since OpenMC outputs
various HDF5 files, h5py is needed to provide access to data within these
files from Python.
.. admonition:: Optional
:class: note
`Matplotlib <http://matplotlib.org/>`_
Matplotlib is used to providing plotting functionality in the API like the
:meth:`Universe.plot` method and the :func:`openmc.plot_xs` function.

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@ -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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@ -4,6 +4,7 @@ from collections import Iterable
from six import string_types
import numpy as np
import pandas as pd
import openmc
from openmc.filter import _FILTER_TYPES
@ -786,9 +787,6 @@ class AggregateFilter(object):
CrossFilter.get_pandas_dataframe()
"""
import pandas as pd
# Create NumPy array of the bin tuples for repeating / tiling
filter_bins = np.empty(self.num_bins, dtype=tuple)
for i, bin in enumerate(self.bins):

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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:
@ -378,7 +357,7 @@ class Cell(object):
self.region = region
else:
if isinstance(self.region, Intersection):
self.region.nodes.append(region)
self.region &= region
else:
self.region = Intersection(self.region, region)
@ -600,7 +579,7 @@ class Cell(object):
elif isinstance(node, Complement):
create_surface_elements(node.node, element)
else:
for subnode in node.nodes:
for subnode in node:
create_surface_elements(subnode, element)
# Call the recursive function from the top node

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@ -45,8 +45,8 @@ def sort_xml_elements(tree):
key = element.get('id')
# If this element has an "ID" tag, append it to the list to sort
if not key is None:
tagged_data.append((key, element))
if key is not None:
tagged_data.append((int(key), element))
# Sort the elements according to the IDs for this tag
tagged_data.sort()
@ -65,7 +65,7 @@ def sort_xml_elements(tree):
tree.extend(sorted_elements)
def clean_xml_indentation(element, level=0, spaces_per_level=4):
def clean_xml_indentation(element, level=0, spaces_per_level=2):
"""
copy and paste from http://effbot.org/zone/elementent-lib.htm#prettyprint
it basically walks your tree and adds spaces and newlines so the tree is

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@ -118,12 +118,12 @@ thermr / %%%%%%%%%%%%%%%% Add thermal scattering data (free gas) %%%%%%%%%%%%%%%
0 23 62
0 {mat} 12 {num_temp} 1 0 {iform} 1 221 1/
{temps}
0.001 4.0
0.001 {energy_max}
thermr / %%%%%%%%%%%%%%%% Add thermal scattering data (bound) %%%%%%%%%%%%%%%%%%
60 62 27
{mat_thermal} {mat} 16 {num_temp} {inelastic} {elastic} {iform} {natom} 222 1/
{temps}
0.001 4.0
0.001 {energy_max}
"""
_ACE_THERMAL_TEMPLATE_ACER = """acer /
@ -347,7 +347,6 @@ def make_ace_thermal(filename, filename_thermal, temperatures=None,
data = _THERMAL_DATA[mat_thermal]
zaids = ' '.join(str(zaid) for zaid in data.zaids[:3])
energy_max = ev_thermal.info['energy_max']
# Determine name of library
library = '{}-{}.{}'.format(*ev_thermal.info['library'])
@ -369,6 +368,7 @@ def make_ace_thermal(filename, filename_thermal, temperatures=None,
file_obj = StringIO(ev_thermal.section[7, 4])
items = endf.get_head_record(file_obj)
items, values = endf.get_list_record(file_obj)
energy_max = values[3]
natom = int(values[5])
# Note that the 'iform' parameter is omitted in NJOY 99. We assume that the

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@ -8,14 +8,13 @@ from xml.etree import ElementTree as ET
from six import add_metaclass
import numpy as np
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']
@ -28,12 +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.
@ -73,7 +66,7 @@ class FilterMeta(ABCMeta):
@add_metaclass(FilterMeta)
class Filter(object):
class Filter(IDManagerMixin):
"""Tally modifier that describes phase-space and other characteristics.
Parameters
@ -99,6 +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
@ -194,10 +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
@ -216,17 +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)
@ -460,9 +441,7 @@ class Filter(object):
Tally.get_pandas_dataframe(), CrossFilter.get_pandas_dataframe()
"""
# Initialize Pandas DataFrame
import pandas as pd
df = pd.DataFrame()
filter_bins = np.repeat(self.bins, self.stride)
@ -715,9 +694,7 @@ class SurfaceFilter(Filter):
Tally.get_pandas_dataframe(), CrossFilter.get_pandas_dataframe()
"""
# Initialize Pandas DataFrame
import pandas as pd
df = pd.DataFrame()
filter_bins = np.repeat(self.bins, self.stride)
@ -875,9 +852,7 @@ class MeshFilter(Filter):
Tally.get_pandas_dataframe(), CrossFilter.get_pandas_dataframe()
"""
# Initialize Pandas DataFrame
import pandas as pd
df = pd.DataFrame()
# Initialize dictionary to build Pandas Multi-index column
@ -1123,9 +1098,7 @@ class EnergyFilter(RealFilter):
Tally.get_pandas_dataframe(), CrossFilter.get_pandas_dataframe()
"""
# Initialize Pandas DataFrame
import pandas as pd
df = pd.DataFrame()
# Extract the lower and upper energy bounds, then repeat and tile
@ -1335,9 +1308,7 @@ class DistribcellFilter(Filter):
Tally.get_pandas_dataframe(), CrossFilter.get_pandas_dataframe()
"""
# Initialize Pandas DataFrame
import pandas as pd
df = pd.DataFrame()
level_df = None
@ -1531,9 +1502,7 @@ class MuFilter(RealFilter):
Tally.get_pandas_dataframe(), CrossFilter.get_pandas_dataframe()
"""
# Initialize Pandas DataFrame
import pandas as pd
df = pd.DataFrame()
# Extract the lower and upper energy bounds, then repeat and tile
@ -1638,9 +1607,7 @@ class PolarFilter(RealFilter):
Tally.get_pandas_dataframe(), CrossFilter.get_pandas_dataframe()
"""
# Initialize Pandas DataFrame
import pandas as pd
df = pd.DataFrame()
# Extract the lower and upper angle bounds, then repeat and tile
@ -1745,9 +1712,7 @@ class AzimuthalFilter(RealFilter):
Tally.get_pandas_dataframe(), CrossFilter.get_pandas_dataframe()
"""
# Initialize Pandas DataFrame
import pandas as pd
df = pd.DataFrame()
# Extract the lower and upper angle bounds, then repeat and tile
@ -2039,8 +2004,6 @@ class EnergyFunctionFilter(Filter):
Tally.get_pandas_dataframe(), CrossFilter.get_pandas_dataframe()
"""
import pandas as pd
df = pd.DataFrame()
# There is no clean way of sticking all the energy, y data into a

View file

@ -9,14 +9,6 @@ from openmc.clean_xml import sort_xml_elements, clean_xml_indentation
from openmc.checkvalue import check_type
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()
class Geometry(object):
"""Geometry representing a collection of surfaces, cells, and universes.

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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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@ -5,6 +5,9 @@ import os
from six import string_types
import numpy as np
import h5py
from scipy.interpolate import interp1d
from scipy.integrate import simps
from scipy.special import eval_legendre
import openmc
import openmc.mgxs
@ -1808,10 +1811,6 @@ class XSdata(object):
"""
from scipy.interpolate import interp1d
from scipy.integrate import simps
from scipy.special import eval_legendre
check_value('target_format', target_format, _SCATTER_TYPES)
check_type('target_order', target_order, Integral)
if target_format == 'legendre':

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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 +23,81 @@ class EqualityMixin(object):
def __ne__(self, other):
return not self.__eq__(other)
class IDWarning(UserWarning):
pass
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:
msg = 'Another {} instance already exists with id={}.'.format(
name, uid)
warn(msg, IDWarning)
else:
cls.used_ids.add(uid)
self._id = uid
def reset_auto_ids():
"""Reset counters for all auto-generated IDs"""
for cls in IDManagerMixin.__subclasses__():
cls.used_ids.clear()
cls.next_id = 1
def reserve_ids(ids, cls=None):
"""Reserve a set of IDs that won't be used for auto-generated IDs.
Parameters
----------
ids : iterable of int
IDs to reserve
cls : type or None
Class for which IDs should be reserved (e.g., :class:`openmc.Cell`). If
None, all classes that have auto-generated IDs will be used.
"""
if cls is None:
for cls in IDManagerMixin.__subclasses__():
cls.used_ids |= set(ids)
else:
cls.used_ids |= set(ids)
def set_auto_id(next_id):
"""Set the next ID for auto-generated IDs.
Parameters
----------
next_id : int
The next ID to assign to objects with auto-generated IDs.
"""
for cls in IDManagerMixin.__subclasses__():
cls.next_id = next_id

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@ -513,7 +513,7 @@ def create_triso_lattice(trisos, lower_left, pitch, shape, background):
universes = np.empty(shape[::-1], dtype=openmc.Universe)
for idx, triso_list in sorted(triso_locations.items()):
if len(triso_list) > 0:
outside_trisos = openmc.Intersection(*[~t.region for t in triso_list])
outside_trisos = openmc.Intersection(~t.region for t in triso_list)
background_cell = openmc.Cell(fill=background, region=outside_trisos)
else:
background_cell = openmc.Cell(fill=background)

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@ -371,11 +371,11 @@ def get_openmoc_region(openmc_region):
openmoc.Halfspace(halfspace, get_openmoc_surface(surface))
elif isinstance(openmc_region, openmc.Intersection):
openmoc_region = openmoc.Intersection()
for openmc_node in openmc_region.nodes:
for openmc_node in openmc_region:
openmoc_region.addNode(get_openmoc_region(openmc_node))
elif isinstance(openmc_region, openmc.Union):
openmoc_region = openmoc.Union()
for openmc_node in openmc_region.nodes:
for openmc_node in openmc_region:
openmoc_region.addNode(get_openmoc_region(openmc_node))
elif isinstance(openmc_region, openmc.Complement):
openmoc_region = openmoc.Complement()
@ -411,12 +411,12 @@ def get_openmc_region(openmoc_region):
openmc_region = openmc.Intersection()
for openmoc_node in openmoc_region.getNodes():
openmc_node = get_openmc_region(openmoc_node)
openmc_region.nodes.append(openmc_node)
openmc_region.append(openmc_node)
elif openmoc_region.getRegionType() == openmoc.UNION:
openmc_region = openmc.Union()
for openmoc_node in openmoc_region.getNodes():
openmc_node = get_openmc_region(openmoc_node)
openmc_region.nodes.append(openmc_node)
openmc_region.append(openmc_node)
elif openmoc_region.getRegionType() == openmoc.COMPLEMENT:
openmoc_nodes = openmoc_region.getNodes()
openmc_node = get_openmc_region(openmoc_nodes[0])

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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

@ -1,5 +1,5 @@
from abc import ABCMeta, abstractmethod
from collections import Iterable, OrderedDict
from collections import Iterable, OrderedDict, MutableSequence
from copy import deepcopy
from six import add_metaclass
@ -20,21 +20,21 @@ class Region(object):
"""
def __and__(self, other):
return Intersection(self, other)
return Intersection((self, other))
def __or__(self, other):
return Union(self, other)
return Union((self, other))
def __invert__(self):
return Complement(self)
@abstractmethod
def __contains__(self, point):
return False
pass
@abstractmethod
def __str__(self):
return ''
pass
def __eq__(self, other):
if not isinstance(other, type(self)):
@ -55,7 +55,7 @@ class Region(object):
----------
surfaces: collections.OrderedDict, optional
Dictionary mapping surface IDs to :class:`openmc.Surface` instances
Returns
-------
surfaces: collections.OrderedDict
@ -150,32 +150,26 @@ class Region(object):
r2 = output.pop()
if operator == ' ':
r1 = output.pop()
if isinstance(r1, Intersection) and can_be_combined(r2):
r1.nodes.append(r2)
if isinstance(r1, Intersection):
r1 &= r2
output.append(r1)
elif isinstance(r2, Intersection) and can_be_combined(r1):
r2.nodes.insert(0, r1)
r2.insert(0, r1)
output.append(r2)
elif isinstance(r1, Intersection) and isinstance(r2, Intersection):
r1.nodes += r2.nodes
output.append(r1)
else:
output.append(Intersection(r1, r2))
output.append(r1 & r2)
elif operator == '|':
r1 = output.pop()
if isinstance(r1, Union) and can_be_combined(r2):
r1.nodes.append(r2)
if isinstance(r1, Union):
r1 |= r2
output.append(r1)
elif isinstance(r2, Union) and can_be_combined(r1):
r2.nodes.insert(0, r1)
r2.insert(0, r1)
output.append(r2)
elif isinstance(r1, Union) and isinstance(r2, Union):
r1.nodes += r2.nodes
output.append(r1)
else:
output.append(Union(r1, r2))
output.append(r1 | r2)
elif operator == '~':
output.append(Complement(r2))
output.append(~r2)
# The following is an implementation of the shunting yard algorithm to
# generate an abstract syntax tree for the region expression.
@ -248,12 +242,12 @@ class Region(object):
'the abstract region class.')
class Intersection(Region):
class Intersection(Region, MutableSequence):
r"""Intersection of two or more regions.
Instances of Intersection are generally created via the __and__ operator
applied to two instances of :class:`openmc.Region`. This is illustrated in
the following example:
Instances of Intersection are generally created via the & operator applied
to two instances of :class:`openmc.Region`. This is illustrated in the
following example:
>>> equator = openmc.ZPlane(z0=0.0)
>>> earth = openmc.Sphere(R=637.1e6)
@ -262,31 +256,51 @@ class Intersection(Region):
>>> type(northern_hemisphere)
<class 'openmc.region.Intersection'>
Instances of this class behave like a mutable sequence, e.g., they can be
indexed and have an append() method.
Parameters
----------
\*nodes
nodes : iterable of openmc.Region
Regions to take the intersection of
Attributes
----------
nodes : list of openmc.Region
Regions to take the intersection of
bounding_box : tuple of numpy.array
Lower-left and upper-right coordinates of an axis-aligned bounding box
"""
def __init__(self, *nodes):
self.nodes = list(nodes)
def __init__(self, nodes):
self._nodes = list(nodes)
def __and__(self, other):
new = Intersection(*self.nodes)
new.nodes.append(other)
new = Intersection(self)
new &= other
return new
def __iter__(self):
for n in self.nodes:
yield n
def __iand__(self, other):
if isinstance(other, Intersection):
self.extend(other)
else:
self.append(other)
return self
# Implement mutable sequence protocol by delegating to list
def __getitem__(self, key):
return self._nodes[key]
def __setitem__(self, key, value):
self._nodes[key] = value
def __delitem__(self, key):
del self._nodes[key]
def __len__(self):
return len(self._nodes)
def insert(self, index, value):
self._nodes.insert(index, value)
def __contains__(self, point):
"""Check whether a point is contained in the region.
@ -302,30 +316,21 @@ class Intersection(Region):
Whether the point is in the region
"""
return all(point in n for n in self.nodes)
return all(point in n for n in self)
def __str__(self):
return '(' + ' '.join(map(str, self.nodes)) + ')'
@property
def nodes(self):
return self._nodes
return '(' + ' '.join(map(str, self)) + ')'
@property
def bounding_box(self):
lower_left = np.array([-np.inf, -np.inf, -np.inf])
upper_right = np.array([np.inf, np.inf, np.inf])
for n in self.nodes:
for n in self:
lower_left_n, upper_right_n = n.bounding_box
lower_left[:] = np.maximum(lower_left, lower_left_n)
upper_right[:] = np.minimum(upper_right, upper_right_n)
return lower_left, upper_right
@nodes.setter
def nodes(self, nodes):
check_type('nodes', nodes, Iterable, Region)
self._nodes = nodes
def clone(self, memo=None):
"""Create a copy of this region - each of the surfaces in the
intersection's nodes will be cloned and will have new unique IDs.
@ -347,47 +352,67 @@ class Intersection(Region):
memo = {}
clone = deepcopy(self)
clone.nodes = [n.clone(memo) for n in self.nodes]
clone[:] = [n.clone(memo) for n in self]
return clone
class Union(Region):
class Union(Region, MutableSequence):
r"""Union of two or more regions.
Instances of Union are generally created via the __or__ operator applied to
two instances of :class:`openmc.Region`. This is illustrated in the
following example:
Instances of Union are generally created via the | operator applied to two
instances of :class:`openmc.Region`. This is illustrated in the following
example:
>>> s1 = openmc.ZPlane(z0=0.0)
>>> s2 = openmc.Sphere(R=637.1e6)
>>> type(-s2 | +s1)
<class 'openmc.region.Union'>
Instances of this class behave like a mutable sequence, e.g., they can be
indexed and have an append() method.
Parameters
----------
\*nodes
nodes : iterable of openmc.Region
Regions to take the union of
Attributes
----------
nodes : tuple of openmc.Region
Regions to take the union of
bounding_box : 2-tuple of numpy.array
Lower-left and upper-right coordinates of an axis-aligned bounding box
"""
def __init__(self, *nodes):
self.nodes = list(nodes)
def __init__(self, nodes):
self._nodes = list(nodes)
def __or__(self, other):
new = Union(*self.nodes)
new.nodes.append(other)
new = Union(self)
new |= other
return new
def __iter__(self):
for n in self.nodes:
yield n
def __ior__(self, other):
if isinstance(other, Union):
self.extend(other)
else:
self.append(other)
return self
# Implement mutable sequence protocol by delegating to list
def __getitem__(self, key):
return self._nodes[key]
def __setitem__(self, key, value):
self._nodes[key] = value
def __delitem__(self, key):
del self._nodes[key]
def __len__(self):
return len(self._nodes)
def insert(self, index, value):
self._nodes.insert(index, value)
def __contains__(self, point):
"""Check whether a point is contained in the region.
@ -403,30 +428,21 @@ class Union(Region):
Whether the point is in the region
"""
return any(point in n for n in self.nodes)
return any(point in n for n in self)
def __str__(self):
return '(' + ' | '.join(map(str, self.nodes)) + ')'
@property
def nodes(self):
return self._nodes
return '(' + ' | '.join(map(str, self)) + ')'
@property
def bounding_box(self):
lower_left = np.array([np.inf, np.inf, np.inf])
upper_right = np.array([-np.inf, -np.inf, -np.inf])
for n in self.nodes:
for n in self:
lower_left_n, upper_right_n = n.bounding_box
lower_left[:] = np.minimum(lower_left, lower_left_n)
upper_right[:] = np.maximum(upper_right, upper_right_n)
return lower_left, upper_right
@nodes.setter
def nodes(self, nodes):
check_type('nodes', nodes, Iterable, Region)
self._nodes = nodes
def clone(self, memo=None):
"""Create a copy of this region - each of the surfaces in the
union's nodes will be cloned and will have new unique IDs.
@ -448,7 +464,7 @@ class Union(Region):
memo = {}
clone = copy.deepcopy(self)
clone.nodes = [n.clone(memo) for n in self.nodes]
clone[:] = [n.clone(memo) for n in self]
return clone
@ -456,7 +472,7 @@ class Complement(Region):
"""Complement of a region.
The Complement of an existing :class:`openmc.Region` can be created by using
the __invert__ operator as the following example demonstrates:
the ~ operator as the following example demonstrates:
>>> xl = openmc.XPlane(x0=-10.0)
>>> xr = openmc.XPlane(x0=10.0)
@ -518,9 +534,9 @@ class Complement(Region):
# only applies to surface half-spaces, thus allowing us to calculate the
# bounding box in the usual recursive manner.
if isinstance(self.node, Union):
temp_region = Intersection(*[~n for n in self.node.nodes])
temp_region = Intersection(~n for n in self.node)
elif isinstance(self.node, Intersection):
temp_region = Union(*[~n for n in self.node.nodes])
temp_region = Union(~n for n in self.node)
elif isinstance(self.node, Complement):
temp_region = self.node.node
else:

View file

@ -1,6 +1,8 @@
from collections import Callable
from numbers import Real
import scipy.optimize as sopt
import openmc
import openmc.model
import openmc.checkvalue as cv
@ -144,8 +146,6 @@ def search_for_keff(model_builder, initial_guess=None, target=1.0,
model = model_builder(initial_guess, **model_args)
cv.check_type('model_builder return', model, openmc.model.Model)
import scipy.optimize as sopt
# Set the iteration data storage variables
guesses = []
results = []

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', openmc.IDWarning)
# 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

View file

@ -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", openmc.IDWarning)
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'])

View file

@ -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:
@ -1860,15 +1843,15 @@ class Halfspace(Region):
def __and__(self, other):
if isinstance(other, Intersection):
return Intersection(self, *other.nodes)
return Intersection([self] + other[:])
else:
return Intersection(self, other)
return Intersection((self, other))
def __or__(self, other):
if isinstance(other, Union):
return Union(self, *other.nodes)
return Union([self] + other[:])
else:
return Union(self, other)
return Union((self, other))
def __invert__(self):
return -self.surface if self.side == '+' else +self.surface

View file

@ -11,16 +11,16 @@ from xml.etree import ElementTree as ET
from six import string_types
import numpy as np
import pandas as pd
import scipy.sparse as sps
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
@ -39,13 +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.
@ -107,6 +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
@ -202,10 +199,6 @@ class Tally(object):
return string
@property
def id(self):
return self._id
@property
def name(self):
return self._name
@ -295,8 +288,6 @@ class Tally(object):
# Convert NumPy arrays to SciPy sparse LIL matrices
if self.sparse:
import scipy.sparse as sps
self._sum = \
sps.lil_matrix(self._sum.flatten(), self._sum.shape)
self._sum_sq = \
@ -337,8 +328,6 @@ class Tally(object):
# Convert NumPy array to SciPy sparse LIL matrix
if self.sparse:
import scipy.sparse as sps
self._mean = \
sps.lil_matrix(self._mean.flatten(), self._mean.shape)
@ -361,8 +350,6 @@ class Tally(object):
# Convert NumPy array to SciPy sparse LIL matrix
if self.sparse:
import scipy.sparse as sps
self._std_dev = \
sps.lil_matrix(self._std_dev.flatten(), self._std_dev.shape)
@ -420,17 +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:
@ -608,8 +584,6 @@ class Tally(object):
# Convert NumPy arrays to SciPy sparse LIL matrices
if sparse and not self.sparse:
import scipy.sparse as sps
if self._sum is not None:
self._sum = \
sps.lil_matrix(self._sum.flatten(), self._sum.shape)
@ -1610,7 +1584,6 @@ class Tally(object):
raise KeyError(msg)
# Initialize a pandas dataframe for the tally data
import pandas as pd
df = pd.DataFrame()
# Find the total length of the tally data array

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
@ -116,22 +106,11 @@ class Universe(object):
regions = [c.region for c in self.cells.values()
if c.region is not None]
if regions:
return openmc.Union(*regions).bounding_box
return openmc.Union(regions).bounding_box
else:
# 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
@ -85,15 +85,16 @@ 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
else:
if self.domain_type == 'cell':
ll, ur = openmc.Union(*[c.region for c in domains]).bounding_box
ll, ur = openmc.Union(c.region for c in domains).bounding_box
if np.any(np.isinf(ll)) or np.any(np.isinf(ur)):
raise ValueError('Could not automatically determine bounding '
'box for stochastic volume calculation.')
@ -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', openmc.IDWarning)
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

@ -45,14 +45,12 @@ kwargs = {'name': 'openmc',
if have_setuptools:
kwargs.update({
# Required dependencies
'install_requires': ['six', 'numpy>=1.9', 'h5py'],
'install_requires': ['six', 'numpy>=1.9', 'h5py', 'scipy', 'pandas>=0.17.0'],
# Optional dependencies
'extras_require': {
'decay': ['uncertainties'],
'pandas': ['pandas>=0.17.0'],
'plot': ['matplotlib', 'ipython'],
'sparse' : ['scipy'],
'vtk': ['vtk', 'silomesh'],
'validate': ['lxml']
},

View file

@ -818,7 +818,6 @@ contains
real(8) :: xs_low ! 0K xs at lowest practical relative energy
real(8) :: xs_up ! 0K xs at highest practical relative energy
real(8) :: m ! slope for interpolation
real(8) :: xi ! pseudorandom number on [0,1)
real(8) :: R ! rejection criterion for DBRC / target speed
real(8) :: cdf_low ! xs cdf at lowest practical relative energy
real(8) :: cdf_up ! xs cdf at highest practical relative energy

View file

@ -1,19 +1,19 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell fill="202" id="1" region="10000 -10001 10002 -10003 10004 -10005" universe="0" />
<cell id="27" material="1" region="-1" universe="3" />
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<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
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<pitch>1.26 1.26</pitch>
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3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
@ -31,197 +31,197 @@
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 </universes>
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<pitch>21.42 21.42</pitch>
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</lattice>
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8 7 7
8 8 8
7 7 7 </universes>
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<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
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</material>
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<sab name="c_H_in_H2O" />
</material>
<material id="11" name="Top of fuel assemblies">
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<sab name="c_H_in_H2O" />
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
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<sab name="c_H_in_H2O" />
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
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<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="Cold borated water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
<nuclide name="Fe54" wo="0.05437098" />
<nuclide name="Fe56" wo="0.88500663" />
<nuclide name="Fe57" wo="0.0208008" />
<nuclide name="Fe58" wo="0.00282159" />
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<nuclide name="Mn55" wo="0.01" />
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<nuclide name="C0" wo="0.0025" />
<nuclide name="Cu63" wo="0.0013696" />
</material>
<material id="6" name="Lower radial reflector">
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<sab name="c_H_in_H2O" />
</material>
<material id="7" name="Upper radial reflector / Top plate region">
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<sab name="c_H_in_H2O" />
</material>
<material id="8" name="Bottom plate region">
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<sab name="c_H_in_H2O" />
</material>
<material id="9" name="Bottom nozzle region">
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</material>
<material id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
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</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="5.77" />
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<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="Cold borated water">
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<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
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<sab name="c_H_in_H2O" />
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H1" />
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<sab name="c_H_in_H2O" />
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
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</material>
<material id="6" name="Lower radial reflector">
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<material id="7" name="Upper radial reflector / Top plate region">
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<material id="9" name="Bottom nozzle region">
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<sab name="c_H_in_H2O" />
</material>
<material id="10" name="Top nozzle region">
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</material>
<material id="11" name="Top of fuel assemblies">
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</material>
<material id="12" name="Bottom of fuel assemblies">
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<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-32 -32 0 32 32 32</parameters>
</space>
</source>
<run_mode>eigenvalue</run_mode>
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</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="10000" type="distribcell">
<bins>27</bins>
</filter>
<tally id="27" name="distribcell tally">
<filters>10000</filters>
<scores>nu-fission</scores>
</tally>
<filter id="1" type="distribcell">
<bins>27</bins>
</filter>
<tally id="27" name="distribcell tally">
<filters>1</filters>
<scores>nu-fission</scores>
</tally>
</tallies>

View file

@ -1 +1 @@
f388c07481a7333bde8044d2e8805954ec41cc3e73d00f1b92b6acff03dad06e62a74e8b7595994e877f69a051ff34d8e498de69ac0efec6e396434007c10b0c
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View file

@ -1,37 +1,37 @@
<?xml version='1.0' encoding='utf-8'?>
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<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>100</particles>
<batches>10</batches>
<source strength="1.0">
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
<energy parameters="988000.0 2.249e-06" type="watt" />
</source>
<create_fission_neutrons>false</create_fission_neutrons>
<run_mode>fixed source</run_mode>
<particles>100</particles>
<batches>10</batches>
<source strength="1.0">
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
<energy parameters="988000.0 2.249e-06" type="watt" />
</source>
<create_fission_neutrons>false</create_fission_neutrons>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<tally id="1">
<scores>flux</scores>
</tally>
<tally id="1">
<scores>flux</scores>
</tally>
</tallies>

View file

@ -1,38 +1,38 @@
<?xml version='1.0' encoding='utf-8'?>
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@ -73,12 +73,12 @@
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<sab name="c_H_in_H2O" />
</material>
<material id="9" name="Bottom nozzle region">
<density units="g/cm3" value="2.53" />
<nuclide name="H1" wo="0.0245014" />
<nuclide name="O16" wo="0.1944274" />
<nuclide name="B10" wo="7.89917e-05" />
<nuclide name="B11" wo="0.000359854" />
<nuclide name="Fe54" wo="0.030411411144" />
<nuclide name="Fe56" wo="0.495012237964" />
<nuclide name="Fe57" wo="0.01163454624" />
<nuclide name="Fe58" wo="0.001578204652" />
<nuclide name="Ni58" wo="0.047211231662" />
<nuclide name="Mn55" wo="0.0156126" />
<nuclide name="Cr52" wo="0.124142524198" />
<sab name="c_H_in_H2O" />
</material>
<material id="10" name="Top nozzle region">
<density units="g/cm3" value="1.746" />
<nuclide name="H1" wo="0.035887" />
<nuclide name="O16" wo="0.2847761" />
<nuclide name="B10" wo="0.000115699" />
<nuclide name="B11" wo="0.000527075" />
<nuclide name="Fe54" wo="0.02644016154" />
<nuclide name="Fe56" wo="0.43037146399" />
<nuclide name="Fe57" wo="0.0101152584" />
<nuclide name="Fe58" wo="0.00137211607" />
<nuclide name="Ni58" wo="0.04104621835" />
<nuclide name="Mn55" wo="0.0135739" />
<nuclide name="Cr52" wo="0.107931450781" />
<sab name="c_H_in_H2O" />
</material>
<material id="11" name="Top of fuel assemblies">
<density units="g/cm3" value="3.044" />
<nuclide name="H1" wo="0.0162913" />
<nuclide name="O16" wo="0.1292776" />
<nuclide name="B10" wo="5.25228e-05" />
<nuclide name="B11" wo="0.000239272" />
<nuclide name="Zr90" wo="0.43313403903" />
<nuclide name="Zr91" wo="0.09549277374" />
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" />
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
<nuclide name="H1" wo="0.0292856" />
<nuclide name="O16" wo="0.2323919" />
<nuclide name="B10" wo="9.44159e-05" />
<nuclide name="B11" wo="0.00043012" />
<nuclide name="Zr90" wo="0.3741373658" />
<nuclide name="Zr91" wo="0.0824858164" />
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>3</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
<temperature_multipole>true</temperature_multipole>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>3</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
<temperature_multipole>true</temperature_multipole>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="10000" type="material">
<bins>1 3</bins>
</filter>
<filter id="10001" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<tally id="10000">
<filters>10000</filters>
<scores>flux</scores>
<derivative>1</derivative>
</tally>
<tally id="10001">
<filters>10000</filters>
<scores>flux</scores>
<derivative>2</derivative>
</tally>
<tally id="10002">
<filters>10000</filters>
<scores>flux</scores>
<derivative>3</derivative>
</tally>
<tally id="10003">
<filters>10000</filters>
<scores>flux</scores>
<derivative>4</derivative>
</tally>
<tally id="10004">
<filters>10000</filters>
<scores>flux</scores>
<derivative>5</derivative>
</tally>
<tally id="10005">
<filters>10000</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>1</derivative>
</tally>
<tally id="10006">
<filters>10000</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>2</derivative>
</tally>
<tally id="10007">
<filters>10000</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>3</derivative>
</tally>
<tally id="10008">
<filters>10000</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>4</derivative>
</tally>
<tally id="10009">
<filters>10000</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>5</derivative>
</tally>
<tally id="10010">
<filters>10000</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>1</derivative>
</tally>
<tally id="10011">
<filters>10000</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>2</derivative>
</tally>
<tally id="10012">
<filters>10000</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>3</derivative>
</tally>
<tally id="10013">
<filters>10000</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>4</derivative>
</tally>
<tally id="10014">
<filters>10000</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>5</derivative>
</tally>
<tally id="10015">
<filters>10000 10001</filters>
<nuclides>total U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>1</derivative>
</tally>
<tally id="10016">
<filters>10000 10001</filters>
<nuclides>total U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>2</derivative>
</tally>
<tally id="10017">
<filters>10000 10001</filters>
<nuclides>U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>3</derivative>
</tally>
<tally id="10018">
<filters>10000 10001</filters>
<nuclides>U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>4</derivative>
</tally>
<tally id="10019">
<filters>10000 10001</filters>
<nuclides>U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>5</derivative>
</tally>
<derivative id="1" material="3" variable="density" />
<derivative id="2" material="1" variable="density" />
<derivative id="3" material="1" nuclide="O16" variable="nuclide_density" />
<derivative id="4" material="1" nuclide="U235" variable="nuclide_density" />
<derivative id="5" material="1" variable="temperature" />
<filter id="1" type="material">
<bins>1 3</bins>
</filter>
<filter id="2" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
<derivative>1</derivative>
</tally>
<tally id="2">
<filters>1</filters>
<scores>flux</scores>
<derivative>2</derivative>
</tally>
<tally id="3">
<filters>1</filters>
<scores>flux</scores>
<derivative>3</derivative>
</tally>
<tally id="4">
<filters>1</filters>
<scores>flux</scores>
<derivative>4</derivative>
</tally>
<tally id="5">
<filters>1</filters>
<scores>flux</scores>
<derivative>5</derivative>
</tally>
<tally id="6">
<filters>1</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>1</derivative>
</tally>
<tally id="7">
<filters>1</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>2</derivative>
</tally>
<tally id="8">
<filters>1</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>3</derivative>
</tally>
<tally id="9">
<filters>1</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>4</derivative>
</tally>
<tally id="10">
<filters>1</filters>
<nuclides>total U235</nuclides>
<scores>total absorption scatter fission nu-fission</scores>
<derivative>5</derivative>
</tally>
<tally id="11">
<filters>1</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>1</derivative>
</tally>
<tally id="12">
<filters>1</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>2</derivative>
</tally>
<tally id="13">
<filters>1</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>3</derivative>
</tally>
<tally id="14">
<filters>1</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>4</derivative>
</tally>
<tally id="15">
<filters>1</filters>
<scores>absorption</scores>
<estimator>analog</estimator>
<derivative>5</derivative>
</tally>
<tally id="16">
<filters>1 2</filters>
<nuclides>total U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>1</derivative>
</tally>
<tally id="17">
<filters>1 2</filters>
<nuclides>total U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>2</derivative>
</tally>
<tally id="18">
<filters>1 2</filters>
<nuclides>U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>3</derivative>
</tally>
<tally id="19">
<filters>1 2</filters>
<nuclides>U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>4</derivative>
</tally>
<tally id="20">
<filters>1 2</filters>
<nuclides>U235</nuclides>
<scores>nu-fission scatter</scores>
<derivative>5</derivative>
</tally>
<derivative id="1" material="3" variable="density" />
<derivative id="2" material="1" variable="density" />
<derivative id="3" material="1" nuclide="O16" variable="nuclide_density" />
<derivative id="4" material="1" nuclide="U235" variable="nuclide_density" />
<derivative id="5" material="1" variable="temperature" />
</tallies>

View file

@ -1,67 +1,27 @@
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
1,,density,flux,-5.7132388e-02,1.6898131e-01
1,O16,nuclide_density,flux,-1.3403627e+01,1.3017120e+01
1,O16,nuclide_density,flux,-1.0499675e+01,2.1684952e+01
1,U235,nuclide_density,flux,-2.4741168e+03,5.7986931e+01
1,U235,nuclide_density,flux,-1.9955529e+03,4.3254814e+02
1,,temperature,flux,1.0601812e-04,3.3076564e-04
1,,temperature,flux,1.6664397e-04,2.8761161e-04
3,,density,total,-3.3161583e+00,2.5615932e+00
3,,density,absorption,-4.3491247e-01,5.1559026e-01
3,,density,scatter,-2.8812458e+00,2.0540304e+00
3,,density,fission,-2.3060366e-01,3.1191112e-01
3,,density,nu-fission,-5.6817321e-01,7.6143397e-01
3,,density,total,-2.8908006e-01,3.9383187e-01
3,,density,absorption,-2.5237484e-01,3.6565057e-01
3,,density,scatter,-3.6705219e-02,2.9275369e-02
3,,density,fission,-2.1271120e-01,3.0873701e-01
3,,density,nu-fission,-5.1866339e-01,7.5235541e-01
3,,density,total,2.7320555e+00,8.7709460e+00
3,,density,absorption,8.4322459e-02,1.2807898e-01
3,,density,scatter,2.6477331e+00,8.6432562e+00
3,,density,flux,-4.5951022e+00,4.0201889e-01
3,,density,flux,-9.9630192e+00,1.8897688e+00
1,,density,flux,-4.2074596e-01,6.8569557e-02
1,,density,flux,-2.8861314e-01,1.0032157e-01
1,O16,nuclide_density,flux,-1.7146771e+01,1.8740496e+01
1,O16,nuclide_density,flux,-1.4411733e+01,1.5986415e+01
1,U235,nuclide_density,flux,-3.1082590e+03,3.5930199e+02
1,U235,nuclide_density,flux,-2.5816702e+03,2.4275334e+02
1,,temperature,flux,-2.2847162e-06,3.5489476e-04
1,,temperature,flux,-8.5566667e-05,4.3023777e-04
3,,density,total,-1.5582276e+00,2.8496759e-01
3,,density,absorption,1.5711173e-01,1.7341244e-01
3,,density,scatter,-1.7153393e+00,1.9431809e-01
3,,density,fission,2.0152323e-01,7.4786095e-02
3,,density,nu-fission,4.8687131e-01,1.8265878e-01
3,,density,total,2.2943608e-01,8.6539576e-02
3,,density,absorption,2.4646330e-01,8.6186628e-02
3,,density,scatter,-1.7027217e-02,3.1732345e-03
3,,density,fission,2.1668870e-01,7.5183313e-02
3,,density,nu-fission,5.2774399e-01,1.8320780e-01
3,,density,total,1.3300225e+01,4.2626034e+00
3,,density,absorption,2.3903751e-01,8.9355264e-02
3,,density,scatter,1.3061188e+01,4.1751261e+00
3,,density,fission,0.0000000e+00,0.0000000e+00
3,,density,nu-fission,0.0000000e+00,0.0000000e+00
3,,density,total,0.0000000e+00,0.0000000e+00
@ -69,19 +29,19 @@ d_material,d_nuclide,d_variable,score,mean,std. dev.
3,,density,scatter,0.0000000e+00,0.0000000e+00
3,,density,fission,0.0000000e+00,0.0000000e+00
3,,density,nu-fission,0.0000000e+00,0.0000000e+00
1,,density,total,4.7523458e-01,2.5651989e-02
1,,density,absorption,3.1301277e-02,7.6793124e-03
1,,density,scatter,4.4393330e-01,1.8023240e-02
1,,density,fission,1.5559382e-02,3.2310296e-03
1,,density,nu-fission,3.8658175e-02,7.8012239e-03
1,,density,total,2.2062973e-02,4.3689056e-03
1,,density,absorption,1.6845658e-02,4.0750597e-03
1,,density,scatter,5.2173154e-03,2.9663441e-04
1,,density,fission,1.3503676e-02,3.2642872e-03
1,,density,nu-fission,3.2945540e-02,7.9507678e-03
1,,density,total,-9.4735075e-02,2.5584662e-01
1,,density,absorption,-4.0246308e-03,5.2111771e-03
1,,density,scatter,-9.0710444e-02,2.5073759e-01
1,,density,total,3.3373495e-01,4.6827421e-02
1,,density,absorption,6.7487092e-04,6.5232977e-03
1,,density,scatter,3.3306008e-01,4.0307583e-02
1,,density,fission,-1.8402784e-03,4.2206212e-03
1,,density,nu-fission,-3.8312038e-03,1.0337874e-02
1,,density,total,-2.4831544e-04,5.5020059e-03
1,,density,absorption,-4.0311629e-03,5.0266899e-03
1,,density,scatter,3.7828475e-03,4.8043964e-04
1,,density,fission,-3.6379968e-03,4.1821819e-03
1,,density,nu-fission,-8.8266852e-03,1.0193373e-02
1,,density,total,-3.6848185e-01,1.9314902e-01
1,,density,absorption,-7.3640407e-03,4.0184508e-03
1,,density,scatter,-3.6111780e-01,1.8936612e-01
1,,density,fission,0.0000000e+00,0.0000000e+00
1,,density,nu-fission,0.0000000e+00,0.0000000e+00
1,,density,total,0.0000000e+00,0.0000000e+00
@ -89,19 +49,19 @@ d_material,d_nuclide,d_variable,score,mean,std. dev.
1,,density,scatter,0.0000000e+00,0.0000000e+00
1,,density,fission,0.0000000e+00,0.0000000e+00
1,,density,nu-fission,0.0000000e+00,0.0000000e+00
1,O16,nuclide_density,total,4.4488235e+01,5.3981552e+00
1,O16,nuclide_density,absorption,-2.9372260e-01,9.3282726e-01
1,O16,nuclide_density,scatter,4.4781958e+01,4.5257514e+00
1,O16,nuclide_density,fission,9.9830021e-02,4.0698873e-01
1,O16,nuclide_density,nu-fission,2.3343404e-01,9.8749080e-01
1,O16,nuclide_density,total,4.0916790e-02,6.2301743e-01
1,O16,nuclide_density,absorption,8.8291907e-02,5.5570859e-01
1,O16,nuclide_density,scatter,-4.7375117e-02,6.7714014e-02
1,O16,nuclide_density,fission,1.3678946e-01,4.4006360e-01
1,O16,nuclide_density,nu-fission,3.3258041e-01,1.0719299e+00
1,O16,nuclide_density,total,-1.6055867e+01,2.3439329e+01
1,O16,nuclide_density,absorption,-3.9601159e-01,3.0131618e-01
1,O16,nuclide_density,scatter,-1.5659856e+01,2.3140401e+01
1,O16,nuclide_density,total,3.9050701e+01,8.5131265e+00
1,O16,nuclide_density,absorption,-7.7573286e-01,7.1182570e-01
1,O16,nuclide_density,scatter,3.9826434e+01,7.8536529e+00
1,O16,nuclide_density,fission,-4.2193390e-01,6.0091792e-01
1,O16,nuclide_density,nu-fission,-1.0411912e+00,1.4662352e+00
1,O16,nuclide_density,total,-5.8976625e-01,7.9559349e-01
1,O16,nuclide_density,absorption,-5.0047331e-01,7.1666177e-01
1,O16,nuclide_density,scatter,-8.9292946e-02,8.9937898e-02
1,O16,nuclide_density,fission,-3.6634959e-01,6.1270658e-01
1,O16,nuclide_density,nu-fission,-8.9338374e-01,1.4932014e+00
1,O16,nuclide_density,total,-3.3511352e+00,2.2365725e+01
1,O16,nuclide_density,absorption,1.5473875e-01,4.3692662e-01
1,O16,nuclide_density,scatter,-3.5058740e+00,2.1928948e+01
1,O16,nuclide_density,fission,0.0000000e+00,0.0000000e+00
1,O16,nuclide_density,nu-fission,0.0000000e+00,0.0000000e+00
1,O16,nuclide_density,total,0.0000000e+00,0.0000000e+00
@ -109,19 +69,19 @@ d_material,d_nuclide,d_variable,score,mean,std. dev.
1,O16,nuclide_density,scatter,0.0000000e+00,0.0000000e+00
1,O16,nuclide_density,fission,0.0000000e+00,0.0000000e+00
1,O16,nuclide_density,nu-fission,0.0000000e+00,0.0000000e+00
1,U235,nuclide_density,total,-6.1444882e+02,6.0111765e+01
1,U235,nuclide_density,absorption,2.3977145e+02,4.5868416e+01
1,U235,nuclide_density,scatter,-8.5422027e+02,2.4877998e+01
1,U235,nuclide_density,fission,3.1319140e+02,3.1465133e+01
1,U235,nuclide_density,nu-fission,7.6415485e+02,7.6501622e+01
1,U235,nuclide_density,total,5.0916190e+02,3.5499332e+01
1,U235,nuclide_density,absorption,3.9477370e+02,3.4326175e+01
1,U235,nuclide_density,scatter,1.1438820e+02,2.7378233e+00
1,U235,nuclide_density,fission,3.1360747e+02,3.2243613e+01
1,U235,nuclide_density,nu-fission,7.6527247e+02,7.8683716e+01
1,U235,nuclide_density,total,-4.1815705e+03,8.7796625e+02
1,U235,nuclide_density,absorption,-1.0563225e+02,2.5308631e+01
1,U235,nuclide_density,scatter,-4.0759382e+03,8.5332198e+02
1,U235,nuclide_density,total,-9.1643805e+02,1.8814046e+02
1,U235,nuclide_density,absorption,1.8114000e+02,4.6345847e+01
1,U235,nuclide_density,scatter,-1.0975781e+03,1.4310981e+02
1,U235,nuclide_density,fission,2.8765342e+02,2.2586319e+01
1,U235,nuclide_density,nu-fission,7.0175585e+02,5.5024716e+01
1,U235,nuclide_density,total,4.6786282e+02,2.8271731e+01
1,U235,nuclide_density,absorption,3.6134508e+02,2.8453765e+01
1,U235,nuclide_density,scatter,1.0651774e+02,1.3120589e+00
1,U235,nuclide_density,fission,2.8859249e+02,2.2522591e+01
1,U235,nuclide_density,nu-fission,7.0430623e+02,5.4858487e+01
1,U235,nuclide_density,total,-5.0586963e+03,6.7151365e+02
1,U235,nuclide_density,absorption,-1.2315731e+02,1.8905184e+01
1,U235,nuclide_density,scatter,-4.9355390e+03,6.5260939e+02
1,U235,nuclide_density,fission,0.0000000e+00,0.0000000e+00
1,U235,nuclide_density,nu-fission,0.0000000e+00,0.0000000e+00
1,U235,nuclide_density,total,0.0000000e+00,0.0000000e+00
@ -129,19 +89,19 @@ d_material,d_nuclide,d_variable,score,mean,std. dev.
1,U235,nuclide_density,scatter,0.0000000e+00,0.0000000e+00
1,U235,nuclide_density,fission,0.0000000e+00,0.0000000e+00
1,U235,nuclide_density,nu-fission,0.0000000e+00,0.0000000e+00
1,,temperature,total,2.1367126e-04,1.8632825e-04
1,,temperature,absorption,6.9456243e-05,3.2199405e-05
1,,temperature,scatter,1.4421502e-04,1.5754186e-04
1,,temperature,fission,3.0674921e-06,1.8048386e-05
1,,temperature,nu-fission,7.4768732e-06,4.3976788e-05
1,,temperature,total,5.8223046e-06,2.3786485e-05
1,,temperature,absorption,5.2142631e-06,2.1901921e-05
1,,temperature,scatter,6.0804154e-07,1.9834897e-06
1,,temperature,fission,3.0674141e-06,1.8048551e-05
1,,temperature,nu-fission,7.4766883e-06,4.3977175e-05
1,,temperature,total,2.1510094e-04,4.6388764e-04
1,,temperature,absorption,2.2409493e-06,8.2901087e-06
1,,temperature,scatter,2.1285999e-04,4.5560092e-04
1,,temperature,total,8.6368265e-05,1.7363899e-04
1,,temperature,absorption,1.9220262e-05,3.4988977e-05
1,,temperature,scatter,6.7148003e-05,1.4635162e-04
1,,temperature,fission,-5.2927287e-06,1.2158338e-05
1,,temperature,nu-fission,-1.2897086e-05,2.9622912e-05
1,,temperature,total,-4.2009323e-06,1.8263855e-05
1,,temperature,absorption,-4.3037914e-06,1.6219907e-05
1,,temperature,scatter,1.0285902e-07,2.0676492e-06
1,,temperature,fission,-5.2953783e-06,1.2158786e-05
1,,temperature,nu-fission,-1.2903531e-05,2.9624000e-05
1,,temperature,total,-1.1160261e-04,6.1705782e-04
1,,temperature,absorption,-2.0394397e-06,8.4055062e-06
1,,temperature,scatter,-1.0956317e-04,6.0869070e-04
1,,temperature,fission,0.0000000e+00,0.0000000e+00
1,,temperature,nu-fission,0.0000000e+00,0.0000000e+00
1,,temperature,total,0.0000000e+00,0.0000000e+00
@ -149,29 +109,69 @@ d_material,d_nuclide,d_variable,score,mean,std. dev.
1,,temperature,scatter,0.0000000e+00,0.0000000e+00
1,,temperature,fission,0.0000000e+00,0.0000000e+00
1,,temperature,nu-fission,0.0000000e+00,0.0000000e+00
3,,density,absorption,-1.6517209e-01,3.0984748e-01
3,,density,absorption,8.0401451e-03,1.4689308e-01
1,,density,absorption,2.9069923e-02,2.2139686e-03
1,,density,absorption,-9.4690017e-03,8.6605404e-03
1,O16,nuclide_density,absorption,7.6912288e-01,4.1945623e-01
1,O16,nuclide_density,absorption,-6.3724748e-01,6.6341497e-01
1,U235,nuclide_density,absorption,1.4109552e+02,1.8518919e+01
1,U235,nuclide_density,absorption,-1.2052821e+02,3.2084005e+01
1,,temperature,absorption,3.9995382e-05,2.1703359e-05
1,,temperature,absorption,2.7274368e-06,8.9339250e-06
3,,density,absorption,1.3594219e-01,1.0122046e-01
3,,density,absorption,2.8656499e-01,3.7923985e-02
1,,density,absorption,-2.2106085e-03,9.8387075e-03
1,,density,absorption,-3.3239716e-03,8.7768141e-03
1,O16,nuclide_density,absorption,-1.2640173e+00,9.1596515e-01
1,O16,nuclide_density,absorption,1.3146714e-01,9.9380272e-01
1,U235,nuclide_density,absorption,1.5677452e+02,8.1085465e+01
1,U235,nuclide_density,absorption,-1.4334804e+02,3.2100956e+01
1,,temperature,absorption,-8.9633351e-06,3.5750907e-05
1,,temperature,absorption,7.0140498e-07,1.1694324e-05
3,,density,nu-fission,0.0000000e+00,0.0000000e+00
3,,density,scatter,-8.7934549e-01,1.0210652e+00
3,,density,scatter,4.7213241e-01,1.6556808e-01
3,,density,nu-fission,0.0000000e+00,0.0000000e+00
3,,density,scatter,-3.5236517e-03,3.5236517e-03
3,,density,nu-fission,7.2952775e-02,2.9725868e-01
3,,density,scatter,-2.2716407e+00,1.2546346e+00
3,,density,nu-fission,8.9171241e-02,3.0634860e-01
3,,density,scatter,-1.0151726e-03,9.6296789e-03
3,,density,scatter,3.4067110e-02,2.1267271e-02
3,,density,nu-fission,4.1265284e-01,1.3891654e-01
3,,density,scatter,-2.1663022e+00,3.2444877e-01
3,,density,nu-fission,4.4524898e-01,1.4098968e-01
3,,density,scatter,-2.1357153e-02,1.7423446e-02
3,,density,nu-fission,0.0000000e+00,0.0000000e+00
3,,density,scatter,2.3163919e+00,4.8766694e+00
3,,density,scatter,8.6343785e+00,2.9292930e+00
3,,density,nu-fission,0.0000000e+00,0.0000000e+00
3,,density,scatter,0.0000000e+00,0.0000000e+00
3,,density,nu-fission,0.0000000e+00,0.0000000e+00
3,,density,scatter,4.0762347e-01,3.8504133e+00
3,,density,scatter,4.3792818e+00,1.9915652e+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,-5.0479210e-03,9.5688761e-03
1,,density,nu-fission,0.0000000e+00,0.0000000e+00
1,,density,scatter,4.4418327e-04,7.8121620e-04
1,,density,nu-fission,-1.9240114e-02,1.4935352e-02
1,,density,scatter,3.4099348e-01,2.8182893e-02
1,,density,nu-fission,-2.4226858e-02,1.4481188e-02
1,,density,scatter,1.1073847e-03,2.7478584e-04
1,,density,nu-fission,0.0000000e+00,0.0000000e+00
1,,density,scatter,-2.7695506e-01,1.3529978e-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,-8.8202815e-02,7.8863942e-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,1.1279170e-01,6.9836765e-02
1,O16,nuclide_density,nu-fission,-1.6695105e+00,1.6777445e+00
1,O16,nuclide_density,scatter,-1.0671543e-01,1.9127943e-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,6.3235790e+00,3.9733167e+00
1,U235,nuclide_density,nu-fission,6.2368225e+02,1.0172850e+02
1,U235,nuclide_density,scatter,3.2601903e+01,6.2672072e+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,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,-2.0884127e-06,1.6684645e-06
1,,temperature,nu-fission,-1.5670247e-05,4.5939944e-05
1,,temperature,scatter,3.9749436e-06,3.9749436e-06
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

@ -1,62 +1,62 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" universe="1" />
<cell fill="101" id="101" region="10001 -10002 10003 -10004" universe="0" />
<cell id="11" material="2 3 void 2" region="-10000" universe="11" />
<cell id="12" material="1" region="10000" universe="11" />
<lattice id="101">
<pitch>2.0 2.0</pitch>
<outer>1</outer>
<dimension>2 2</dimension>
<lower_left>-2.0 -2.0</lower_left>
<universes>
<cell id="1" material="1" universe="1" />
<cell id="11" material="2 3 void 2" region="-9" universe="11" />
<cell id="12" material="1" region="9" universe="11" />
<cell fill="101" id="101" region="10 -11 12 -13" universe="0" />
<lattice id="101">
<pitch>2.0 2.0</pitch>
<outer>1</outer>
<dimension>2 2</dimension>
<lower_left>-2.0 -2.0</lower_left>
<universes>
11 11
11 11 </universes>
</lattice>
<surface coeffs="0.0 0.0 0.3" id="10000" type="z-cylinder" />
<surface boundary="reflective" coeffs="-3.0" id="10001" type="x-plane" />
<surface boundary="reflective" coeffs="3.0" id="10002" type="x-plane" />
<surface boundary="reflective" coeffs="-3.0" id="10003" type="y-plane" />
<surface boundary="reflective" coeffs="3.0" id="10004" type="y-plane" />
</lattice>
<surface coeffs="0.0 0.0 0.3" id="9" type="z-cylinder" />
<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" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1">
<density units="g/cc" value="1.0" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
<material id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="3">
<density units="g/cc" value="2.0" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="1">
<density units="g/cc" value="1.0" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
</material>
<material id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="3">
<density units="g/cc" value="2.0" />
<nuclide ao="1.0" name="U235" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>5</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
</source>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>5</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<plots>
<plot basis="xy" color_by="cell" filename="cellplot" id="1" type="slice">
<origin>0 0 0</origin>
<width>7 7</width>
<pixels>400 400</pixels>
</plot>
<plot basis="xy" color_by="material" filename="matplot" id="2" type="slice">
<origin>0 0 0</origin>
<width>7 7</width>
<pixels>400 400</pixels>
</plot>
<plot basis="xy" color_by="cell" filename="cellplot" id="1" type="slice">
<origin>0 0 0</origin>
<width>7 7</width>
<pixels>400 400</pixels>
</plot>
<plot basis="xy" color_by="material" filename="matplot" id="2" type="slice">
<origin>0 0 0</origin>
<width>7 7</width>
<pixels>400 400</pixels>
</plot>
</plots>

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

@ -1,42 +1,42 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="box" region="1 -2 3 -4 5 -6" universe="0" />
<surface boundary="reflective" coeffs="-1" id="1" type="x-plane" />
<surface boundary="reflective" coeffs="1" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="-1" id="3" type="y-plane" />
<surface boundary="reflective" coeffs="1" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="-1" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="1" id="6" type="z-plane" />
<cell id="1" material="1" name="box" region="1 -2 3 -4 5 -6" universe="0" />
<surface boundary="reflective" coeffs="-1" id="1" type="x-plane" />
<surface boundary="reflective" coeffs="1" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="-1" id="3" type="y-plane" />
<surface boundary="reflective" coeffs="1" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="-1" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="1" id="6" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="mat">
<density units="atom/b-cm" value="0.069335" />
<nuclide ao="40.0" name="H1" />
</material>
<material id="1" name="mat">
<density units="atom/b-cm" value="0.069335" />
<nuclide ao="40.0" name="H1" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>fixed source</run_mode>
<particles>100</particles>
<batches>10</batches>
<source strength="1.0">
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
<energy parameters="988000.0 2.249e-06" type="watt" />
</source>
<cutoff>
<energy>4.0</energy>
</cutoff>
<run_mode>fixed source</run_mode>
<particles>100</particles>
<batches>10</batches>
<source strength="1.0">
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
<energy parameters="988000.0 2.249e-06" type="watt" />
</source>
<cutoff>
<energy>4.0</energy>
</cutoff>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="10000" type="energy">
<bins>0.0 4.0</bins>
</filter>
<tally id="1">
<filters>10000</filters>
<scores>flux</scores>
</tally>
<filter id="1" type="energy">
<bins>0.0 4.0</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>

View file

@ -1,38 +1,38 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell fill="200" id="1" region="-6 34 -35" universe="0" />
<cell id="10" material="5" region="7 -8 31 -39" universe="0" />
<cell id="11" material="6" region="5 -6 32 -34" universe="0" />
<cell id="12" material="7" region="5 -6 36 -38" universe="0" />
<cell fill="201" id="2" region="-6 35 -36" universe="0" />
<cell id="21" material="1" region="-1" universe="1" />
<cell id="22" material="2" region="1 -2" universe="1" />
<cell id="23" material="3" region="2" universe="1" />
<cell id="24" material="3" region="-3" universe="2" />
<cell id="25" material="2" region="3 -4" universe="2" />
<cell id="26" material="3" region="4" universe="2" />
<cell id="27" material="1" region="-1" universe="3" />
<cell id="28" material="2" region="1 -2" universe="3" />
<cell id="29" material="4" region="2" universe="3" />
<cell id="3" material="8" region="-7 31 -32" universe="0" />
<cell id="30" material="4" region="-3" universe="4" />
<cell id="31" material="2" region="3 -4" universe="4" />
<cell id="32" material="4" region="4" universe="4" />
<cell id="4" material="9" region="-5 32 -33" universe="0" />
<cell id="5" material="12" region="-5 33 -34" universe="0" />
<cell id="50" material="3" region="34 -35" universe="5" />
<cell id="6" material="11" region="-5 36 -37" universe="0" />
<cell fill="100" id="60" region="34 -35" universe="6" />
<cell id="7" material="10" region="-5 37 -38" universe="0" />
<cell id="70" material="4" region="35 -36" universe="7" />
<cell id="8" material="7" region="-7 38 -39" universe="0" />
<cell fill="101" id="80" region="35 -36" universe="8" />
<cell id="9" material="9" region="6 -7 32 -38" universe="0" />
<lattice id="100" name="Fuel assembly (lower half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
<cell fill="200" id="1" region="-6 34 -35" universe="0" />
<cell fill="201" id="2" region="-6 35 -36" universe="0" />
<cell id="3" material="8" region="-7 31 -32" universe="0" />
<cell id="4" material="9" region="-5 32 -33" universe="0" />
<cell id="5" material="12" region="-5 33 -34" universe="0" />
<cell id="6" material="11" region="-5 36 -37" universe="0" />
<cell id="7" material="10" region="-5 37 -38" universe="0" />
<cell id="8" material="7" region="-7 38 -39" universe="0" />
<cell id="9" material="9" region="6 -7 32 -38" universe="0" />
<cell id="10" material="5" region="7 -8 31 -39" universe="0" />
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<lower_left>-10.71 -10.71</lower_left>
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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 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
@ -50,12 +50,12 @@
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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<lattice id="101" name="Fuel assembly (upper half)">
<pitch>1.26 1.26</pitch>
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<lower_left>-10.71 -10.71</lower_left>
<universes>
</lattice>
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<lower_left>-10.71 -10.71</lower_left>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
@ -73,12 +73,12 @@
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 </universes>
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</lattice>
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5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
@ -100,12 +100,12 @@
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 </universes>
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7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
@ -127,200 +127,200 @@
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
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<?xml version='1.0' encoding='utf-8'?>
<materials>
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<?xml version='1.0' encoding='utf-8'?>
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<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="10000" 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">
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<tally id="10001">
<filters>10000</filters>
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<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="1">
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
<tally id="2">
<filters>1</filters>
<nuclides>Am241</nuclides>
<scores>(n,gamma)</scores>
</tally>
</tallies>

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 9.97e-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

@ -1,38 +1,38 @@
<?xml version='1.0' encoding='utf-8'?>
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<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
@ -50,12 +50,12 @@
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 </universes>
</lattice>
<lattice id="101" name="Fuel assembly (upper half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
</lattice>
<lattice id="101" name="Fuel assembly (upper half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
@ -73,12 +73,12 @@
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 </universes>
</lattice>
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<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
</lattice>
<lattice id="200" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
@ -100,12 +100,12 @@
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 </universes>
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<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
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<lower_left>-224.91 -224.91</lower_left>
<universes>
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
@ -127,234 +127,234 @@
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 </universes>
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<material id="1" name="UOX fuel">
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<material id="3" name="Cold borated water">
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<material id="6" name="Lower radial reflector">
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View file

@ -1,2 +1,2 @@
k-combined:
9.753410E-01 6.608253E-02
9.672875E-01 3.577848E-02

View file

@ -1,97 +1,97 @@
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View file

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View file

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View file

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View file

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View file

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View file

@ -1,229 +1,229 @@
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<filter id="6" type="material">
<bins>1 2 3 4 5 6 7 8 9 10 11 12</bins>
</filter>
<filter id="1" type="energy">
<bins>0.0 20000000.0</bins>
</filter>
<filter id="2" type="energyout">
<bins>0.0 20000000.0</bins>
</filter>
<filter id="3" type="energy">
<bins>1e-05 0.0635 10.0 100.0 1000.0 500000.0 1000000.0 20000000.0</bins>
</filter>
<filter id="4" type="energyout">
<bins>1e-05 0.0635 10.0 100.0 1000.0 500000.0 1000000.0 20000000.0</bins>
</filter>
<tally id="1">
<filters>5</filters>
<scores>total absorption flux fission nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="2">
<filters>5</filters>
<scores>total absorption flux fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="3">
<filters>6 1</filters>
<scores>total absorption flux fission nu-fission scatter nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="4">
<filters>6 1</filters>
<scores>total absorption flux fission nu-fission</scores>
<estimator>collision</estimator>
</tally>
<tally id="5">
<filters>6 1</filters>
<scores>total absorption flux fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="6">
<filters>6 1 2</filters>
<scores>scatter nu-scatter nu-fission</scores>
</tally>
<tally id="7">
<filters>6 3</filters>
<scores>total absorption flux fission nu-fission scatter nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="8">
<filters>6 3</filters>
<scores>total absorption flux fission nu-fission</scores>
<estimator>collision</estimator>
</tally>
<tally id="9">
<filters>6 3</filters>
<scores>total absorption flux fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10">
<filters>6 3 4</filters>
<scores>scatter nu-scatter nu-fission</scores>
</tally>
<tally id="11">
<filters>5</filters>
<nuclides>uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu</nuclides>
<scores>total absorption fission nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="12">
<filters>5</filters>
<nuclides>uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu</nuclides>
<scores>total absorption fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="13">
<filters>6 1</filters>
<nuclides>uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu</nuclides>
<scores>total absorption fission nu-fission scatter nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="14">
<filters>6 1</filters>
<nuclides>uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu</nuclides>
<scores>total absorption fission nu-fission</scores>
<estimator>collision</estimator>
</tally>
<tally id="15">
<filters>6 1</filters>
<nuclides>uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu</nuclides>
<scores>total absorption fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="16">
<filters>6 1 2</filters>
<nuclides>uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu</nuclides>
<scores>scatter nu-scatter nu-fission</scores>
</tally>
<tally id="17">
<filters>6 3</filters>
<nuclides>uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu</nuclides>
<scores>total absorption fission nu-fission scatter nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="18">
<filters>6 3</filters>
<nuclides>uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu</nuclides>
<scores>total absorption fission nu-fission</scores>
<estimator>collision</estimator>
</tally>
<tally id="19">
<filters>6 3</filters>
<nuclides>uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu</nuclides>
<scores>total absorption fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="20">
<filters>6 3 4</filters>
<nuclides>uo2_ang uo2_ang_mu uo2_iso uo2_iso_mu clad_ang clad_ang_mu clad_iso clad_iso_mu lwtr_ang lwtr_ang_mu lwtr_iso lwtr_iso_mu</nuclides>
<scores>scatter nu-scatter nu-fission</scores>
</tally>
</tallies>

View file

@ -1 +1 @@
0a17877c7cf6dbd3e432b1997669a47c588d2a4074a29406deef27332eb7a0f736ea1fdc2037fc02f8ebca39f00332563bbe2172adc26bfaab2d6144d259daee
9183f8b191f2e62334f992acd865d29e3f4e3f871a6df498e280fc4e2d91f2d2d20c732fbd75fa88e2e8c576f86e744f7655af6bb9da66e9b28b1009c8742899

View file

@ -1,248 +1,248 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="10000" material="10000" name="Fuel" region="-10000" universe="0" />
<cell id="10001" material="10001" name="Cladding" region="10000 -10001" universe="0" />
<cell id="10002" material="10002" name="Water" region="10001 10002 -10003 10004 -10005" universe="0" />
<surface coeffs="0 0 0.39218" id="10000" name="Fuel OR" type="z-cylinder" />
<surface coeffs="0 0 0.4572" id="10001" name="Clad OR" type="z-cylinder" />
<surface boundary="reflective" coeffs="-0.63" id="10002" name="left" type="x-plane" />
<surface boundary="reflective" coeffs="0.63" id="10003" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-0.63" id="10004" name="bottom" type="y-plane" />
<surface boundary="reflective" coeffs="0.63" id="10005" name="top" type="y-plane" />
<cell id="1" material="1" name="Fuel" region="-1" universe="0" />
<cell id="2" material="2" name="Cladding" region="1 -2" universe="0" />
<cell id="3" material="3" name="Water" region="2 3 -4 5 -6" universe="0" />
<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="-0.63" id="3" name="left" type="x-plane" />
<surface boundary="reflective" coeffs="0.63" id="4" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-0.63" id="5" name="bottom" type="y-plane" />
<surface boundary="reflective" coeffs="0.63" id="6" name="top" type="y-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="10000" name="UO2 (2.4%)">
<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="Zircaloy">
<density units="g/cm3" value="6.55" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
<nuclide ao="0.0072758" name="Zr92" />
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="10002" name="Hot borated water">
<density units="g/cm3" value="0.740582" />
<nuclide ao="0.049457" name="H1" />
<nuclide ao="0.024672" name="O16" />
<nuclide ao="8.0042e-06" name="B10" />
<nuclide ao="3.2218e-05" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="1" name="UO2 (2.4%)">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />
<nuclide ao="0.022408" name="U238" />
<nuclide ao="0.045829" name="O16" />
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="6.55" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
<nuclide ao="0.0072758" name="Zr92" />
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="3" name="Hot borated water">
<density units="g/cm3" value="0.740582" />
<nuclide ao="0.049457" name="H1" />
<nuclide ao="0.024672" name="O16" />
<nuclide ao="8.0042e-06" name="B10" />
<nuclide ao="3.2218e-05" name="B11" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
</space>
</source>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="10000" type="material">
<bins>10000</bins>
</filter>
<filter id="10001" type="energy">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="10006" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="10013" type="material">
<bins>10001</bins>
</filter>
<filter id="10026" type="material">
<bins>10002</bins>
</filter>
<tally id="10000">
<filters>10000 10001</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10001">
<filters>10000 10001</filters>
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10002">
<filters>10000 10001</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10003">
<filters>10000 10001</filters>
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10004">
<filters>10000 10001</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10005">
<filters>10000 10001 10006</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10006">
<filters>10000 10001</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10007">
<filters>10000 10001 10006</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10008">
<filters>10000 10001 10006</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10009">
<filters>10000 10001 10006</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10010">
<filters>10013 10001</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10011">
<filters>10013 10001</filters>
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10012">
<filters>10013 10001</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10013">
<filters>10013 10001</filters>
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10014">
<filters>10013 10001</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10015">
<filters>10013 10001 10006</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10016">
<filters>10013 10001</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10017">
<filters>10013 10001 10006</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10018">
<filters>10013 10001 10006</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10019">
<filters>10013 10001 10006</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10020">
<filters>10026 10001</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10021">
<filters>10026 10001</filters>
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10022">
<filters>10026 10001</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10023">
<filters>10026 10001</filters>
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10024">
<filters>10026 10001</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10025">
<filters>10026 10001 10006</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10026">
<filters>10026 10001</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="10027">
<filters>10026 10001 10006</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="10028">
<filters>10026 10001 10006</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10029">
<filters>10026 10001 10006</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<filter id="1" type="material">
<bins>1</bins>
</filter>
<filter id="2" type="energy">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="7" type="energyout">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="14" type="material">
<bins>2</bins>
</filter>
<filter id="27" type="material">
<bins>3</bins>
</filter>
<tally id="1">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="2">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="3">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="4">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="5">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="6">
<filters>1 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="7">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="8">
<filters>1 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="9">
<filters>1 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10">
<filters>1 2 7</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="11">
<filters>14 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="12">
<filters>14 2</filters>
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="13">
<filters>14 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="14">
<filters>14 2</filters>
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="15">
<filters>14 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="16">
<filters>14 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="17">
<filters>14 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="18">
<filters>14 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="19">
<filters>14 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="20">
<filters>14 2 7</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="21">
<filters>27 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="22">
<filters>27 2</filters>
<nuclides>total</nuclides>
<scores>total</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="23">
<filters>27 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="24">
<filters>27 2</filters>
<nuclides>total</nuclides>
<scores>absorption</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="25">
<filters>27 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="26">
<filters>27 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="27">
<filters>27 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="28">
<filters>27 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="29">
<filters>27 2 7</filters>
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="30">
<filters>27 2 7</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>analog</estimator>
</tally>
</tallies>

File diff suppressed because it is too large Load diff

View file

@ -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

@ -1,464 +1,464 @@
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<?xml version='1.0' encoding='utf-8'?>
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<nuclide ao="8.0042e-06" name="B10" />
<nuclide ao="3.2218e-05" name="B11" />
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<material id="1" name="Fuel">
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<tally id="37">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="38">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="39">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>scatter</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="40">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>scatter-P3</scores>
<estimator>analog</estimator>
</tally>
<tally id="41">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>nu-scatter-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="42">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>scatter-0</scores>
<estimator>analog</estimator>
</tally>
<tally id="43">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="44">
<filters>1 5</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="45">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="46">
<filters>1 5</filters>
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="47">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="48">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>inverse-velocity</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="49">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="50">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="51">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="52">
<filters>1 2 5</filters>
<nuclides>total</nuclides>
<scores>prompt-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="53">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="54">
<filters>1 59 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="55">
<filters>1 59 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="56">
<filters>1 59 5</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="57">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="58">
<filters>1 59 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="59">
<filters>1 59 2</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="60">
<filters>1 59 2</filters>
<nuclides>total</nuclides>
<scores>decay-rate</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="61">
<filters>1 2</filters>
<nuclides>total</nuclides>
<scores>flux</scores>
<estimator>analog</estimator>
</tally>
<tally id="62">
<filters>1 59 2 5</filters>
<nuclides>total</nuclides>
<scores>delayed-nu-fission</scores>
<estimator>analog</estimator>
</tally>
</tallies>

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]]

File diff suppressed because it is too large Load diff

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@ -1,216 +1,216 @@
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.654966 0.098415
1 1 2 1 1 total 0.639357 0.282107
2 2 1 1 1 total 0.713534 0.079788
3 2 2 1 1 total 0.641095 0.091519
0 1 1 1 1 total 0.762544 0.085298
1 1 2 1 1 total 0.653375 0.153317
2 2 1 1 1 total 0.644837 0.088457
3 2 2 1 1 total 0.676480 0.094215
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.407867 0.104648
1 1 2 1 1 total 0.417805 0.300173
2 2 1 1 1 total 0.451699 0.087229
3 2 2 1 1 total 0.396449 0.095884
0 1 1 1 1 total 0.473988 0.088732
1 1 2 1 1 total 0.379821 0.167092
2 2 1 1 1 total 0.399254 0.091318
3 2 2 1 1 total 0.424265 0.099551
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.407867 0.104648
1 1 2 1 1 total 0.417805 0.300173
2 2 1 1 1 total 0.451699 0.087229
3 2 2 1 1 total 0.396449 0.095884
0 1 1 1 1 total 0.473988 0.088732
1 1 2 1 1 total 0.379821 0.167092
2 2 1 1 1 total 0.399254 0.091318
3 2 2 1 1 total 0.424265 0.099551
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.021476 0.004248
1 1 2 1 1 total 0.020653 0.008355
2 2 1 1 1 total 0.027384 0.003568
3 2 2 1 1 total 0.021826 0.004584
0 1 1 1 1 total 0.027288 0.005813
1 1 2 1 1 total 0.019449 0.004420
2 2 1 1 1 total 0.020262 0.003701
3 2 2 1 1 total 0.021266 0.002869
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.013234 0.004146
1 1 2 1 1 total 0.012342 0.006800
2 2 1 1 1 total 0.016807 0.003428
3 2 2 1 1 total 0.013253 0.004795
0 1 1 1 1 total 0.016037 0.006339
1 1 2 1 1 total 0.012153 0.003804
2 2 1 1 1 total 0.013018 0.003521
3 2 2 1 1 total 0.012965 0.002454
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.008241 0.001798
1 1 2 1 1 total 0.008311 0.003296
2 2 1 1 1 total 0.010577 0.001333
3 2 2 1 1 total 0.008573 0.002017
0 1 1 1 1 total 0.011251 0.003050
1 1 2 1 1 total 0.007296 0.001795
2 2 1 1 1 total 0.007243 0.001219
3 2 2 1 1 total 0.008301 0.001066
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.020322 0.004415
1 1 2 1 1 total 0.020546 0.008145
2 2 1 1 1 total 0.026008 0.003213
3 2 2 1 1 total 0.021015 0.004911
0 1 1 1 1 total 0.027498 0.007445
1 1 2 1 1 total 0.017912 0.004426
2 2 1 1 1 total 0.017954 0.003077
3 2 2 1 1 total 0.020469 0.002617
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 1.596881e+06 348355.002874
1 1 2 1 1 total 1.610266e+06 638514.779022
2 2 1 1 1 total 2.048208e+06 257681.650350
3 2 2 1 1 total 1.660283e+06 390011.381149
0 1 1 1 1 total 2.177345e+06 589804.299388
1 1 2 1 1 total 1.413154e+06 347806.623417
2 2 1 1 1 total 1.404096e+06 236476.851953
3 2 2 1 1 total 1.608259e+06 206502.707865
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.633490 0.094536
1 1 2 1 1 total 0.618705 0.273934
2 2 1 1 1 total 0.686150 0.076703
3 2 2 1 1 total 0.619269 0.087616
0 1 1 1 1 total 0.735256 0.080216
1 1 2 1 1 total 0.633925 0.149098
2 2 1 1 1 total 0.624575 0.084974
3 2 2 1 1 total 0.655214 0.091422
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.638348 0.097266
1 1 2 1 1 total 0.588378 0.266032
2 2 1 1 1 total 0.698373 0.092394
3 2 2 1 1 total 0.625643 0.075089
0 1 1 1 1 total 0.763779 0.070696
1 1 2 1 1 total 0.640809 0.158369
2 2 1 1 1 total 0.628158 0.064356
3 2 2 1 1 total 0.645171 0.080467
mesh 1 group in group out nuclide moment mean std. dev.
x y z
0 1 1 1 1 1 total P0 0.638348 0.097266
1 1 1 1 1 1 total P1 0.247099 0.035574
2 1 1 1 1 1 total P2 0.092195 0.010891
3 1 1 1 1 1 total P3 0.013224 0.004528
4 1 2 1 1 1 total P0 0.588378 0.266032
5 1 2 1 1 1 total P1 0.221552 0.102564
6 1 2 1 1 1 total P2 0.069798 0.034699
7 1 2 1 1 1 total P3 -0.003039 0.009633
8 2 1 1 1 1 total P0 0.698373 0.092394
9 2 1 1 1 1 total P1 0.261835 0.035253
10 2 1 1 1 1 total P2 0.096206 0.013947
11 2 1 1 1 1 total P3 0.016973 0.004808
12 2 2 1 1 1 total P0 0.625643 0.075089
13 2 2 1 1 1 total P1 0.244646 0.028604
14 2 2 1 1 1 total P2 0.088580 0.012369
15 2 2 1 1 1 total P3 0.019989 0.013950
0 1 1 1 1 1 total P0 0.763779 0.070696
1 1 1 1 1 1 total P1 0.288556 0.024446
2 1 1 1 1 1 total P2 0.082441 0.011443
3 1 1 1 1 1 total P3 -0.005627 0.012638
4 1 2 1 1 1 total P0 0.640809 0.158369
5 1 2 1 1 1 total P1 0.273553 0.066437
6 1 2 1 1 1 total P2 0.108446 0.024435
7 1 2 1 1 1 total P3 0.012229 0.003785
8 2 1 1 1 1 total P0 0.628158 0.064356
9 2 1 1 1 1 total P1 0.245583 0.022676
10 2 1 1 1 1 total P2 0.086370 0.007833
11 2 1 1 1 1 total P3 0.019590 0.005345
12 2 2 1 1 1 total P0 0.645171 0.080467
13 2 2 1 1 1 total P1 0.252215 0.032154
14 2 2 1 1 1 total P2 0.089251 0.009734
15 2 2 1 1 1 total P3 0.004748 0.002987
mesh 1 group in group out nuclide moment mean std. dev.
x y z
0 1 1 1 1 1 total P0 0.638348 0.097266
1 1 1 1 1 1 total P1 0.247099 0.035574
2 1 1 1 1 1 total P2 0.092195 0.010891
3 1 1 1 1 1 total P3 0.013224 0.004528
4 1 2 1 1 1 total P0 0.588378 0.266032
5 1 2 1 1 1 total P1 0.221552 0.102564
6 1 2 1 1 1 total P2 0.069798 0.034699
7 1 2 1 1 1 total P3 -0.003039 0.009633
8 2 1 1 1 1 total P0 0.698373 0.092394
9 2 1 1 1 1 total P1 0.261835 0.035253
10 2 1 1 1 1 total P2 0.096206 0.013947
11 2 1 1 1 1 total P3 0.016973 0.004808
12 2 2 1 1 1 total P0 0.625643 0.075089
13 2 2 1 1 1 total P1 0.244646 0.028604
14 2 2 1 1 1 total P2 0.088580 0.012369
15 2 2 1 1 1 total P3 0.019989 0.013950
0 1 1 1 1 1 total P0 0.763779 0.070696
1 1 1 1 1 1 total P1 0.288556 0.024446
2 1 1 1 1 1 total P2 0.082441 0.011443
3 1 1 1 1 1 total P3 -0.005627 0.012638
4 1 2 1 1 1 total P0 0.640809 0.158369
5 1 2 1 1 1 total P1 0.273553 0.066437
6 1 2 1 1 1 total P2 0.108446 0.024435
7 1 2 1 1 1 total P3 0.012229 0.003785
8 2 1 1 1 1 total P0 0.628158 0.064356
9 2 1 1 1 1 total P1 0.245583 0.022676
10 2 1 1 1 1 total P2 0.086370 0.007833
11 2 1 1 1 1 total P3 0.019590 0.005345
12 2 2 1 1 1 total P0 0.645171 0.080467
13 2 2 1 1 1 total P1 0.252215 0.032154
14 2 2 1 1 1 total P2 0.089251 0.009734
15 2 2 1 1 1 total P3 0.004748 0.002987
mesh 1 group in group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 1.0 0.153265
1 1 2 1 1 1 total 1.0 0.454973
2 2 1 1 1 1 total 1.0 0.146747
3 2 2 1 1 1 total 1.0 0.141824
0 1 1 1 1 1 total 1.0 0.108337
1 1 2 1 1 1 total 1.0 0.238517
2 2 1 1 1 1 total 1.0 0.113128
3 2 2 1 1 1 total 1.0 0.132597
mesh 1 group in group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 0.021059 0.003031
1 1 2 1 1 1 total 0.017348 0.008786
2 2 1 1 1 1 total 0.020409 0.003354
3 2 2 1 1 1 total 0.011105 0.003806
0 1 1 1 1 1 total 0.015584 0.003404
1 1 2 1 1 1 total 0.014200 0.003676
2 2 1 1 1 1 total 0.017684 0.002499
3 2 2 1 1 1 total 0.022409 0.002481
mesh 1 group in group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 1.0 0.153265
1 1 2 1 1 1 total 1.0 0.454973
2 2 1 1 1 1 total 1.0 0.146747
3 2 2 1 1 1 total 1.0 0.141824
0 1 1 1 1 1 total 1.0 0.108337
1 1 2 1 1 1 total 1.0 0.238517
2 2 1 1 1 1 total 1.0 0.113128
3 2 2 1 1 1 total 1.0 0.132597
mesh 1 group in group out nuclide moment mean std. dev.
x y z
0 1 1 1 1 1 total P0 0.633490 0.135514
1 1 1 1 1 1 total P1 0.245219 0.051009
2 1 1 1 1 1 total P2 0.091493 0.017479
3 1 1 1 1 1 total P3 0.013124 0.004906
4 1 2 1 1 1 total P0 0.618705 0.392783
5 1 2 1 1 1 total P1 0.232972 0.149703
6 1 2 1 1 1 total P2 0.073396 0.049002
7 1 2 1 1 1 total P3 -0.003195 0.010229
8 2 1 1 1 1 total P0 0.686150 0.126578
9 2 1 1 1 1 total P1 0.257252 0.047890
10 2 1 1 1 1 total P2 0.094522 0.018315
11 2 1 1 1 1 total P3 0.016676 0.005187
12 2 2 1 1 1 total P0 0.619269 0.124057
13 2 2 1 1 1 total P1 0.242153 0.048064
14 2 2 1 1 1 total P2 0.087677 0.018646
15 2 2 1 1 1 total P3 0.019785 0.014168
0 1 1 1 1 1 total P0 0.735256 0.113047
1 1 1 1 1 1 total P1 0.277780 0.041434
2 1 1 1 1 1 total P2 0.079362 0.014706
3 1 1 1 1 1 total P3 -0.005417 0.012184
4 1 2 1 1 1 total P0 0.633925 0.212349
5 1 2 1 1 1 total P1 0.270615 0.089799
6 1 2 1 1 1 total P2 0.107281 0.034246
7 1 2 1 1 1 total P3 0.012098 0.004637
8 2 1 1 1 1 total P0 0.624575 0.110512
9 2 1 1 1 1 total P1 0.244182 0.041824
10 2 1 1 1 1 total P2 0.085877 0.014634
11 2 1 1 1 1 total P3 0.019478 0.006012
12 2 2 1 1 1 total P0 0.655214 0.126119
13 2 2 1 1 1 total P1 0.256141 0.049765
14 2 2 1 1 1 total P2 0.090641 0.016563
15 2 2 1 1 1 total P3 0.004822 0.003115
mesh 1 group in group out nuclide moment mean std. dev.
x y z
0 1 1 1 1 1 total P0 0.633490 0.166706
1 1 1 1 1 1 total P1 0.245219 0.063359
2 1 1 1 1 1 total P2 0.091493 0.022409
3 1 1 1 1 1 total P3 0.013124 0.005303
4 1 2 1 1 1 total P0 0.618705 0.483237
5 1 2 1 1 1 total P1 0.232972 0.183428
6 1 2 1 1 1 total P2 0.073396 0.059298
7 1 2 1 1 1 total P3 -0.003195 0.010332
8 2 1 1 1 1 total P0 0.686150 0.161742
9 2 1 1 1 1 total P1 0.257252 0.060980
10 2 1 1 1 1 total P2 0.094522 0.022975
11 2 1 1 1 1 total P3 0.016676 0.005736
12 2 2 1 1 1 total P0 0.619269 0.152000
13 2 2 1 1 1 total P1 0.242153 0.059073
14 2 2 1 1 1 total P2 0.087677 0.022412
15 2 2 1 1 1 total P3 0.019785 0.014443
0 1 1 1 1 1 total P0 0.735256 0.138292
1 1 1 1 1 1 total P1 0.277780 0.051210
2 1 1 1 1 1 total P2 0.079362 0.017035
3 1 1 1 1 1 total P3 -0.005417 0.012198
4 1 2 1 1 1 total P0 0.633925 0.260681
5 1 2 1 1 1 total P1 0.270615 0.110590
6 1 2 1 1 1 total P2 0.107281 0.042750
7 1 2 1 1 1 total P3 0.012098 0.005462
8 2 1 1 1 1 total P0 0.624575 0.131169
9 2 1 1 1 1 total P1 0.244182 0.050123
10 2 1 1 1 1 total P2 0.085877 0.017565
11 2 1 1 1 1 total P3 0.019478 0.006403
12 2 2 1 1 1 total P0 0.655214 0.153147
13 2 2 1 1 1 total P1 0.256141 0.060250
14 2 2 1 1 1 total P2 0.090641 0.020464
15 2 2 1 1 1 total P3 0.004822 0.003180
mesh 1 group out nuclide mean std. dev.
x y z
0 1 1 1 1 total 1.0 0.135958
1 1 2 1 1 total 1.0 0.557756
2 2 1 1 1 total 1.0 0.201340
3 2 2 1 1 total 1.0 0.475608
0 1 1 1 1 total 1.0 0.300047
1 1 2 1 1 total 1.0 0.262180
2 2 1 1 1 total 1.0 0.178169
3 2 2 1 1 total 1.0 0.104797
mesh 1 group out nuclide mean std. dev.
x y z
0 1 1 1 1 total 1.0 0.133151
1 1 2 1 1 total 1.0 0.557756
2 2 1 1 1 total 1.0 0.201340
3 2 2 1 1 total 1.0 0.475608
0 1 1 1 1 total 1.0 0.300047
1 1 2 1 1 total 1.0 0.262180
2 2 1 1 1 total 1.0 0.178169
3 2 2 1 1 total 1.0 0.108931
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 4.697404e-07 8.304376e-08
1 1 2 1 1 total 4.173069e-07 1.694647e-07
2 2 1 1 1 total 6.581421e-07 1.337227e-07
3 2 2 1 1 total 4.714011e-07 1.140489e-07
0 1 1 1 1 total 7.097008e-07 1.458546e-07
1 1 2 1 1 total 3.984535e-07 1.157576e-07
2 2 1 1 1 total 4.407745e-07 7.903907e-08
3 2 2 1 1 total 4.750476e-07 6.207437e-08
mesh 1 group in nuclide mean std. dev.
x y z
0 1 1 1 1 total 0.020173 0.004383
1 1 2 1 1 total 0.020397 0.008086
2 2 1 1 1 total 0.025824 0.003192
3 2 2 1 1 total 0.020865 0.004879
0 1 1 1 1 total 0.027311 0.007397
1 1 2 1 1 total 0.017783 0.004394
2 2 1 1 1 total 0.017820 0.003054
3 2 2 1 1 total 0.020320 0.002598
mesh 1 group in group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 0.020874 0.002977
1 1 2 1 1 1 total 0.017348 0.008786
2 2 1 1 1 1 total 0.020409 0.003354
3 2 2 1 1 1 total 0.011105 0.003806
0 1 1 1 1 1 total 0.015584 0.003404
1 1 2 1 1 1 total 0.014200 0.003676
2 2 1 1 1 1 total 0.017684 0.002499
3 2 2 1 1 1 total 0.022259 0.002508
mesh 1 delayedgroup group in nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 0.000005 1.004638e-06
1 1 1 1 2 1 total 0.000025 5.397978e-06
2 1 1 1 3 1 total 0.000025 5.275050e-06
3 1 1 1 4 1 total 0.000058 1.230443e-05
4 1 1 1 5 1 total 0.000026 5.548743e-06
5 1 1 1 6 1 total 0.000011 2.307020e-06
6 1 2 1 1 1 total 0.000005 1.838266e-06
7 1 2 1 2 1 total 0.000025 9.941991e-06
8 1 2 1 3 1 total 0.000025 9.753804e-06
9 1 2 1 4 1 total 0.000058 2.290678e-05
10 1 2 1 5 1 total 0.000026 1.050498e-05
11 1 2 1 6 1 total 0.000011 4.361882e-06
12 2 1 1 1 1 total 0.000006 7.462654e-07
13 2 1 1 2 1 total 0.000031 3.842479e-06
14 2 1 1 3 1 total 0.000031 3.666594e-06
15 2 1 1 4 1 total 0.000071 8.228616e-06
16 2 1 1 5 1 total 0.000031 3.416659e-06
17 2 1 1 6 1 total 0.000013 1.428970e-06
18 2 2 1 1 1 total 0.000005 1.117984e-06
19 2 2 1 2 1 total 0.000026 5.744801e-06
20 2 2 1 3 1 total 0.000025 5.480526e-06
21 2 2 1 4 1 total 0.000058 1.231604e-05
22 2 2 1 5 1 total 0.000026 5.181495e-06
23 2 2 1 6 1 total 0.000011 2.163732e-06
0 1 1 1 1 1 total 0.000006 1.689606e-06
1 1 1 1 2 1 total 0.000033 8.718916e-06
2 1 1 1 3 1 total 0.000032 8.323051e-06
3 1 1 1 4 1 total 0.000072 1.866015e-05
4 1 1 1 5 1 total 0.000031 7.654909e-06
5 1 1 1 6 1 total 0.000013 3.206343e-06
6 1 2 1 1 1 total 0.000004 1.003100e-06
7 1 2 1 2 1 total 0.000022 5.425275e-06
8 1 2 1 3 1 total 0.000021 5.324236e-06
9 1 2 1 4 1 total 0.000050 1.251572e-05
10 1 2 1 5 1 total 0.000022 5.762184e-06
11 1 2 1 6 1 total 0.000009 2.391676e-06
12 2 1 1 1 1 total 0.000004 6.723192e-07
13 2 1 1 2 1 total 0.000022 3.706235e-06
14 2 1 1 3 1 total 0.000022 3.674263e-06
15 2 1 1 4 1 total 0.000052 8.774048e-06
16 2 1 1 5 1 total 0.000024 4.168024e-06
17 2 1 1 6 1 total 0.000010 1.726268e-06
18 2 2 1 1 1 total 0.000005 5.962367e-07
19 2 2 1 2 1 total 0.000025 3.200900e-06
20 2 2 1 3 1 total 0.000025 3.127442e-06
21 2 2 1 4 1 total 0.000058 7.296157e-06
22 2 2 1 5 1 total 0.000026 3.298196e-06
23 2 2 1 6 1 total 0.000011 1.370918e-06
mesh 1 delayedgroup group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 0.0 0.000000
1 1 1 1 2 1 total 0.0 0.000000
2 1 1 1 3 1 total 0.0 0.000000
3 1 1 1 4 1 total 0.0 0.000000
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@ -226,85 +226,85 @@
17 2 1 1 6 1 total 0.0 0.000000
18 2 2 1 1 1 total 0.0 0.000000
19 2 2 1 2 1 total 0.0 0.000000
20 2 2 1 3 1 total 0.0 0.000000
20 2 2 1 3 1 total 1.0 1.414214
21 2 2 1 4 1 total 0.0 0.000000
22 2 2 1 5 1 total 0.0 0.000000
23 2 2 1 6 1 total 0.0 0.000000
mesh 1 delayedgroup group in nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 0.000227 0.000061
1 1 1 1 2 1 total 0.001228 0.000327
2 1 1 1 3 1 total 0.001206 0.000320
3 1 1 1 4 1 total 0.002835 0.000748
4 1 1 1 5 1 total 0.001300 0.000340
5 1 1 1 6 1 total 0.000540 0.000141
6 1 2 1 1 1 total 0.000226 0.000076
7 1 2 1 2 1 total 0.001220 0.000412
8 1 2 1 3 1 total 0.001197 0.000404
9 1 2 1 4 1 total 0.002809 0.000949
10 1 2 1 5 1 total 0.001284 0.000436
11 1 2 1 6 1 total 0.000533 0.000181
12 2 1 1 1 1 total 0.000226 0.000033
13 2 1 1 2 1 total 0.001207 0.000174
14 2 1 1 3 1 total 0.001175 0.000167
15 2 1 1 4 1 total 0.002721 0.000378
16 2 1 1 5 1 total 0.001207 0.000160
17 2 1 1 6 1 total 0.000502 0.000067
18 2 2 1 1 1 total 0.000228 0.000071
19 2 2 1 2 1 total 0.001221 0.000373
20 2 2 1 3 1 total 0.001190 0.000360
21 2 2 1 4 1 total 0.002767 0.000822
22 2 2 1 5 1 total 0.001238 0.000357
23 2 2 1 6 1 total 0.000515 0.000149
0 1 1 1 1 1 total 0.000228 0.000084
1 1 1 1 2 1 total 0.001195 0.000438
2 1 1 1 3 1 total 0.001153 0.000420
3 1 1 1 4 1 total 0.002629 0.000950
4 1 1 1 5 1 total 0.001125 0.000398
5 1 1 1 6 1 total 0.000470 0.000166
6 1 2 1 1 1 total 0.000228 0.000057
7 1 2 1 2 1 total 0.001222 0.000309
8 1 2 1 3 1 total 0.001193 0.000304
9 1 2 1 4 1 total 0.002780 0.000713
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11 1 2 1 6 1 total 0.000520 0.000136
12 2 1 1 1 1 total 0.000225 0.000044
13 2 1 1 2 1 total 0.001232 0.000242
14 2 1 1 3 1 total 0.001216 0.000239
15 2 1 1 4 1 total 0.002882 0.000570
16 2 1 1 5 1 total 0.001345 0.000270
17 2 1 1 6 1 total 0.000558 0.000112
18 2 2 1 1 1 total 0.000227 0.000027
19 2 2 1 2 1 total 0.001225 0.000143
20 2 2 1 3 1 total 0.001201 0.000140
21 2 2 1 4 1 total 0.002815 0.000326
22 2 2 1 5 1 total 0.001284 0.000147
23 2 2 1 6 1 total 0.000533 0.000061
mesh 1 delayedgroup group in nuclide mean std. dev.
x y z
0 1 1 1 1 1 total 0.013362 0.003586
1 1 1 1 2 1 total 0.032554 0.008645
2 1 1 1 3 1 total 0.121179 0.031941
3 1 1 1 4 1 total 0.306858 0.079971
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5 1 1 1 6 1 total 2.906554 0.741592
6 1 2 1 1 1 total 0.013361 0.004515
7 1 2 1 2 1 total 0.032560 0.010992
8 1 2 1 3 1 total 0.121165 0.040913
9 1 2 1 4 1 total 0.306728 0.103786
10 1 2 1 5 1 total 0.864851 0.295633
11 1 2 1 6 1 total 2.905009 0.992039
12 2 1 1 1 1 total 0.013353 0.002006
13 2 1 1 2 1 total 0.032614 0.004676
14 2 1 1 3 1 total 0.121052 0.016784
15 2 1 1 4 1 total 0.305600 0.040195
16 2 1 1 5 1 total 0.860792 0.101702
17 2 1 1 6 1 total 2.891182 0.344181
18 2 2 1 1 1 total 0.013355 0.004172
19 2 2 1 2 1 total 0.032599 0.009758
20 2 2 1 3 1 total 0.121084 0.035213
21 2 2 1 4 1 total 0.305920 0.085294
22 2 2 1 5 1 total 0.861968 0.224059
23 2 2 1 6 1 total 2.895182 0.755656
mesh 1 delayedgroup group in group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 1 total 0.000000 0.000000
1 1 1 1 2 1 1 total 0.000000 0.000000
2 1 1 1 3 1 1 total 0.000000 0.000000
3 1 1 1 4 1 1 total 0.000000 0.000000
4 1 1 1 5 1 1 total 0.000185 0.000186
5 1 1 1 6 1 1 total 0.000000 0.000000
6 1 2 1 1 1 1 total 0.000000 0.000000
7 1 2 1 2 1 1 total 0.000000 0.000000
8 1 2 1 3 1 1 total 0.000000 0.000000
9 1 2 1 4 1 1 total 0.000000 0.000000
10 1 2 1 5 1 1 total 0.000000 0.000000
11 1 2 1 6 1 1 total 0.000000 0.000000
12 2 1 1 1 1 1 total 0.000000 0.000000
13 2 1 1 2 1 1 total 0.000000 0.000000
14 2 1 1 3 1 1 total 0.000000 0.000000
15 2 1 1 4 1 1 total 0.000000 0.000000
16 2 1 1 5 1 1 total 0.000000 0.000000
17 2 1 1 6 1 1 total 0.000000 0.000000
18 2 2 1 1 1 1 total 0.000000 0.000000
19 2 2 1 2 1 1 total 0.000000 0.000000
20 2 2 1 3 1 1 total 0.000000 0.000000
21 2 2 1 4 1 1 total 0.000000 0.000000
22 2 2 1 5 1 1 total 0.000000 0.000000
23 2 2 1 6 1 1 total 0.000000 0.000000
0 1 1 1 1 1 total 0.013345 0.004923
1 1 1 1 2 1 total 0.032674 0.011850
2 1 1 1 3 1 total 0.120923 0.043307
3 1 1 1 4 1 total 0.304289 0.106753
4 1 1 1 5 1 total 0.855760 0.286466
5 1 1 1 6 1 total 2.874120 0.965609
6 1 2 1 1 1 total 0.013357 0.003345
7 1 2 1 2 1 total 0.032590 0.008273
8 1 2 1 3 1 total 0.121103 0.031074
9 1 2 1 4 1 total 0.306111 0.080011
10 1 2 1 5 1 total 0.862660 0.235694
11 1 2 1 6 1 total 2.897534 0.788926
12 2 1 1 1 1 total 0.013367 0.002548
13 2 1 1 2 1 total 0.032520 0.006266
14 2 1 1 3 1 total 0.121250 0.023544
15 2 1 1 4 1 total 0.307552 0.060464
16 2 1 1 5 1 total 0.867665 0.175131
17 2 1 1 6 1 total 2.914635 0.587161
18 2 2 1 1 1 total 0.013360 0.001587
19 2 2 1 2 1 total 0.032564 0.003810
20 2 2 1 3 1 total 0.121158 0.014038
21 2 2 1 4 1 total 0.306653 0.035052
22 2 2 1 5 1 total 0.864587 0.096680
23 2 2 1 6 1 total 2.904111 0.325170
mesh 1 delayedgroup group in group out nuclide mean std. dev.
x y z
0 1 1 1 1 1 1 total 0.00000 0.000000
1 1 1 1 2 1 1 total 0.00000 0.000000
2 1 1 1 3 1 1 total 0.00000 0.000000
3 1 1 1 4 1 1 total 0.00000 0.000000
4 1 1 1 5 1 1 total 0.00000 0.000000
5 1 1 1 6 1 1 total 0.00000 0.000000
6 1 2 1 1 1 1 total 0.00000 0.000000
7 1 2 1 2 1 1 total 0.00000 0.000000
8 1 2 1 3 1 1 total 0.00000 0.000000
9 1 2 1 4 1 1 total 0.00000 0.000000
10 1 2 1 5 1 1 total 0.00000 0.000000
11 1 2 1 6 1 1 total 0.00000 0.000000
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13 2 1 1 2 1 1 total 0.00000 0.000000
14 2 1 1 3 1 1 total 0.00000 0.000000
15 2 1 1 4 1 1 total 0.00000 0.000000
16 2 1 1 5 1 1 total 0.00000 0.000000
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18 2 2 1 1 1 1 total 0.00000 0.000000
19 2 2 1 2 1 1 total 0.00000 0.000000
20 2 2 1 3 1 1 total 0.00015 0.000151
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File diff suppressed because it is too large Load diff

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@ -1 +1 @@
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View file

@ -1,55 +1,55 @@
<?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" />
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<cell id="1" material="1" universe="1" />
<cell id="11" material="2" region="-1" temperature="500 0 700 800" universe="11" />
<cell id="12" material="1" region="1" universe="11" />
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<lattice id="101">
<pitch>2.0 2.0</pitch>
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<lower_left>-2.0 -2.0</lower_left>
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11 11
11 11 </universes>
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<surface coeffs="0.0 0.0 0.3" id="10000" type="z-cylinder" />
<surface boundary="reflective" coeffs="-3.0" id="10001" type="x-plane" />
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<surface boundary="reflective" coeffs="-3.0" id="10003" type="y-plane" />
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<surface coeffs="0.0 0.0 0.3" id="1" type="z-cylinder" />
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<surface boundary="reflective" coeffs="3.0" id="5" type="y-plane" />
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<materials>
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</material>
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<material id="1">
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<nuclide ao="1.0" name="O16" />
<sab name="c_H_in_H2O" />
</material>
<material id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>5</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
</source>
<temperature_multipole>true</temperature_multipole>
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<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>5</batches>
<inactive>0</inactive>
<source strength="1.0">
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<temperature_multipole>true</temperature_multipole>
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<tallies>
<tally id="10000">
<nuclides>U235 O16 total</nuclides>
<scores>total fission (n,gamma) elastic (n,p)</scores>
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</tallies>

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

@ -1,37 +1,37 @@
<?xml version='1.0' encoding='utf-8'?>
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View file

@ -1,34 +1,34 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
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View file

@ -1,54 +1,54 @@
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View file

@ -1,38 +1,38 @@
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View file

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View file

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<lattice id="101" name="Fuel assembly (upper half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
</lattice>
<lattice id="101" name="Fuel assembly (upper half)">
<pitch>1.26 1.26</pitch>
<dimension>17 17</dimension>
<lower_left>-10.71 -10.71</lower_left>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
@ -73,12 +73,12 @@
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 </universes>
</lattice>
<lattice id="200" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
</lattice>
<lattice id="200" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
@ -100,12 +100,12 @@
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 </universes>
</lattice>
<lattice id="201" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
</lattice>
<lattice id="201" name="Core lattice (lower half)">
<pitch>21.42 21.42</pitch>
<dimension>21 21</dimension>
<lower_left>-224.91 -224.91</lower_left>
<universes>
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
@ -127,197 +127,197 @@
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 </universes>
</lattice>
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<surface coeffs="0.0 0.0 0.475" id="2" type="z-cylinder" />
<surface coeffs="0.0 0.0 0.56" id="3" type="z-cylinder" />
<surface boundary="vacuum" coeffs="-229.0" id="31" type="z-plane" />
<surface coeffs="-199.0" id="32" type="z-plane" />
<surface coeffs="-193.0" id="33" type="z-plane" />
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<surface boundary="vacuum" coeffs="223.0" id="39" type="z-plane" />
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<surface coeffs="0.0 0.0 187.6" id="5" type="z-cylinder" />
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<surface boundary="vacuum" coeffs="0.0 0.0 249.0" id="8" type="z-cylinder" />
</lattice>
<surface coeffs="0.0 0.0 0.41" id="1" type="z-cylinder" />
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<surface boundary="vacuum" coeffs="-229.0" id="31" type="z-plane" />
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<surface coeffs="183.0" id="36" type="z-plane" />
<surface coeffs="203.0" id="37" type="z-plane" />
<surface coeffs="215.0" id="38" type="z-plane" />
<surface boundary="vacuum" coeffs="223.0" id="39" type="z-plane" />
</geometry>
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
<nuclide ao="0.021504" name="U238" />
<nuclide ao="1.0801e-08" name="Xe135" />
<nuclide ao="0.045737" name="O16" />
</material>
<material id="10" name="Top nozzle region">
<density units="g/cm3" value="1.746" />
<nuclide name="H1" wo="0.035887" />
<nuclide name="O16" wo="0.2847761" />
<nuclide name="B10" wo="0.000115699" />
<nuclide name="B11" wo="0.000527075" />
<nuclide name="Fe54" wo="0.02644016154" />
<nuclide name="Fe56" wo="0.43037146399" />
<nuclide name="Fe57" wo="0.0101152584" />
<nuclide name="Fe58" wo="0.00137211607" />
<nuclide name="Ni58" wo="0.04104621835" />
<nuclide name="Mn55" wo="0.0135739" />
<nuclide name="Cr52" wo="0.107931450781" />
<sab name="c_H_in_H2O" />
</material>
<material id="11" name="Top of fuel assemblies">
<density units="g/cm3" value="3.044" />
<nuclide name="H1" wo="0.0162913" />
<nuclide name="O16" wo="0.1292776" />
<nuclide name="B10" wo="5.25228e-05" />
<nuclide name="B11" wo="0.000239272" />
<nuclide name="Zr90" wo="0.43313403903" />
<nuclide name="Zr91" wo="0.09549277374" />
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" />
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
<nuclide name="H1" wo="0.0292856" />
<nuclide name="O16" wo="0.2323919" />
<nuclide name="B10" wo="9.44159e-05" />
<nuclide name="B11" wo="0.00043012" />
<nuclide name="Zr90" wo="0.3741373658" />
<nuclide name="Zr91" wo="0.0824858164" />
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" />
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="Cold borated water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
<nuclide name="Fe54" wo="0.05437098" />
<nuclide name="Fe56" wo="0.88500663" />
<nuclide name="Fe57" wo="0.0208008" />
<nuclide name="Fe58" wo="0.00282159" />
<nuclide name="Ni58" wo="0.0067198" />
<nuclide name="Ni60" wo="0.0026776" />
<nuclide name="Mn55" wo="0.01" />
<nuclide name="Cr52" wo="0.002092475" />
<nuclide name="C0" wo="0.0025" />
<nuclide name="Cu63" wo="0.0013696" />
</material>
<material id="6" name="Lower radial reflector">
<density units="g/cm3" value="4.32" />
<nuclide name="H1" wo="0.0095661" />
<nuclide name="O16" wo="0.0759107" />
<nuclide name="B10" wo="3.08409e-05" />
<nuclide name="B11" wo="0.000140499" />
<nuclide name="Fe54" wo="0.035620772088" />
<nuclide name="Fe56" wo="0.579805982228" />
<nuclide name="Fe57" wo="0.01362750048" />
<nuclide name="Fe58" wo="0.001848545204" />
<nuclide name="Ni58" wo="0.055298376566" />
<nuclide name="Mn55" wo="0.018287" />
<nuclide name="Cr52" wo="0.145407678031" />
<sab name="c_H_in_H2O" />
</material>
<material id="7" name="Upper radial reflector / Top plate region">
<density units="g/cm3" value="4.28" />
<nuclide name="H1" wo="0.0086117" />
<nuclide name="O16" wo="0.0683369" />
<nuclide name="B10" wo="2.77638e-05" />
<nuclide name="B11" wo="0.000126481" />
<nuclide name="Fe54" wo="0.035953677186" />
<nuclide name="Fe56" wo="0.585224740891" />
<nuclide name="Fe57" wo="0.01375486056" />
<nuclide name="Fe58" wo="0.001865821363" />
<nuclide name="Ni58" wo="0.055815129186" />
<nuclide name="Mn55" wo="0.0184579" />
<nuclide name="Cr52" wo="0.146766614995" />
<sab name="c_H_in_H2O" />
</material>
<material id="8" name="Bottom plate region">
<density units="g/cm3" value="7.184" />
<nuclide name="H1" wo="0.0011505" />
<nuclide name="O16" wo="0.0091296" />
<nuclide name="B10" wo="3.70915e-06" />
<nuclide name="B11" wo="1.68974e-05" />
<nuclide name="Fe54" wo="0.03855611055" />
<nuclide name="Fe56" wo="0.627585036425" />
<nuclide name="Fe57" wo="0.014750478" />
<nuclide name="Fe58" wo="0.002000875025" />
<nuclide name="Ni58" wo="0.059855207342" />
<nuclide name="Mn55" wo="0.019794" />
<nuclide name="Cr52" wo="0.157390026871" />
<sab name="c_H_in_H2O" />
</material>
<material id="9" name="Bottom nozzle region">
<density units="g/cm3" value="2.53" />
<nuclide name="H1" wo="0.0245014" />
<nuclide name="O16" wo="0.1944274" />
<nuclide name="B10" wo="7.89917e-05" />
<nuclide name="B11" wo="0.000359854" />
<nuclide name="Fe54" wo="0.030411411144" />
<nuclide name="Fe56" wo="0.495012237964" />
<nuclide name="Fe57" wo="0.01163454624" />
<nuclide name="Fe58" wo="0.001578204652" />
<nuclide name="Ni58" wo="0.047211231662" />
<nuclide name="Mn55" wo="0.0156126" />
<nuclide name="Cr52" wo="0.124142524198" />
<sab name="c_H_in_H2O" />
</material>
<material id="1" name="UOX fuel">
<density units="g/cm3" value="10.062" />
<nuclide ao="4.9476e-06" name="U234" />
<nuclide ao="0.00048218" name="U235" />
<nuclide ao="0.021504" name="U238" />
<nuclide ao="1.0801e-08" name="Xe135" />
<nuclide ao="0.045737" name="O16" />
</material>
<material id="2" name="Zircaloy">
<density units="g/cm3" value="5.77" />
<nuclide ao="0.5145" name="Zr90" />
<nuclide ao="0.1122" name="Zr91" />
<nuclide ao="0.1715" name="Zr92" />
<nuclide ao="0.1738" name="Zr94" />
<nuclide ao="0.028" name="Zr96" />
</material>
<material id="3" name="Cold borated water">
<density units="atom/b-cm" value="0.07416" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="4" name="Hot borated water">
<density units="atom/b-cm" value="0.06614" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
<nuclide name="Fe54" wo="0.05437098" />
<nuclide name="Fe56" wo="0.88500663" />
<nuclide name="Fe57" wo="0.0208008" />
<nuclide name="Fe58" wo="0.00282159" />
<nuclide name="Ni58" wo="0.0067198" />
<nuclide name="Ni60" wo="0.0026776" />
<nuclide name="Mn55" wo="0.01" />
<nuclide name="Cr52" wo="0.002092475" />
<nuclide name="C0" wo="0.0025" />
<nuclide name="Cu63" wo="0.0013696" />
</material>
<material id="6" name="Lower radial reflector">
<density units="g/cm3" value="4.32" />
<nuclide name="H1" wo="0.0095661" />
<nuclide name="O16" wo="0.0759107" />
<nuclide name="B10" wo="3.08409e-05" />
<nuclide name="B11" wo="0.000140499" />
<nuclide name="Fe54" wo="0.035620772088" />
<nuclide name="Fe56" wo="0.579805982228" />
<nuclide name="Fe57" wo="0.01362750048" />
<nuclide name="Fe58" wo="0.001848545204" />
<nuclide name="Ni58" wo="0.055298376566" />
<nuclide name="Mn55" wo="0.018287" />
<nuclide name="Cr52" wo="0.145407678031" />
<sab name="c_H_in_H2O" />
</material>
<material id="7" name="Upper radial reflector / Top plate region">
<density units="g/cm3" value="4.28" />
<nuclide name="H1" wo="0.0086117" />
<nuclide name="O16" wo="0.0683369" />
<nuclide name="B10" wo="2.77638e-05" />
<nuclide name="B11" wo="0.000126481" />
<nuclide name="Fe54" wo="0.035953677186" />
<nuclide name="Fe56" wo="0.585224740891" />
<nuclide name="Fe57" wo="0.01375486056" />
<nuclide name="Fe58" wo="0.001865821363" />
<nuclide name="Ni58" wo="0.055815129186" />
<nuclide name="Mn55" wo="0.0184579" />
<nuclide name="Cr52" wo="0.146766614995" />
<sab name="c_H_in_H2O" />
</material>
<material id="8" name="Bottom plate region">
<density units="g/cm3" value="7.184" />
<nuclide name="H1" wo="0.0011505" />
<nuclide name="O16" wo="0.0091296" />
<nuclide name="B10" wo="3.70915e-06" />
<nuclide name="B11" wo="1.68974e-05" />
<nuclide name="Fe54" wo="0.03855611055" />
<nuclide name="Fe56" wo="0.627585036425" />
<nuclide name="Fe57" wo="0.014750478" />
<nuclide name="Fe58" wo="0.002000875025" />
<nuclide name="Ni58" wo="0.059855207342" />
<nuclide name="Mn55" wo="0.019794" />
<nuclide name="Cr52" wo="0.157390026871" />
<sab name="c_H_in_H2O" />
</material>
<material id="9" name="Bottom nozzle region">
<density units="g/cm3" value="2.53" />
<nuclide name="H1" wo="0.0245014" />
<nuclide name="O16" wo="0.1944274" />
<nuclide name="B10" wo="7.89917e-05" />
<nuclide name="B11" wo="0.000359854" />
<nuclide name="Fe54" wo="0.030411411144" />
<nuclide name="Fe56" wo="0.495012237964" />
<nuclide name="Fe57" wo="0.01163454624" />
<nuclide name="Fe58" wo="0.001578204652" />
<nuclide name="Ni58" wo="0.047211231662" />
<nuclide name="Mn55" wo="0.0156126" />
<nuclide name="Cr52" wo="0.124142524198" />
<sab name="c_H_in_H2O" />
</material>
<material id="10" name="Top nozzle region">
<density units="g/cm3" value="1.746" />
<nuclide name="H1" wo="0.035887" />
<nuclide name="O16" wo="0.2847761" />
<nuclide name="B10" wo="0.000115699" />
<nuclide name="B11" wo="0.000527075" />
<nuclide name="Fe54" wo="0.02644016154" />
<nuclide name="Fe56" wo="0.43037146399" />
<nuclide name="Fe57" wo="0.0101152584" />
<nuclide name="Fe58" wo="0.00137211607" />
<nuclide name="Ni58" wo="0.04104621835" />
<nuclide name="Mn55" wo="0.0135739" />
<nuclide name="Cr52" wo="0.107931450781" />
<sab name="c_H_in_H2O" />
</material>
<material id="11" name="Top of fuel assemblies">
<density units="g/cm3" value="3.044" />
<nuclide name="H1" wo="0.0162913" />
<nuclide name="O16" wo="0.1292776" />
<nuclide name="B10" wo="5.25228e-05" />
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<sab name="c_H_in_H2O" />
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
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<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="10000" type="energy">
<bins>0.0 0.253 1000.0 1000000.0 20000000.0</bins>
</filter>
<filter id="10001" type="distribcell">
<bins>60</bins>
</filter>
<tally id="10000" name="distribcell tally">
<filters>10000 10001</filters>
<nuclides>U234 U235 U238</nuclides>
<scores>nu-fission total</scores>
</tally>
<filter id="1" type="energy">
<bins>0.0 0.253 1000.0 1000000.0 20000000.0</bins>
</filter>
<filter id="2" type="distribcell">
<bins>60</bins>
</filter>
<tally id="1" name="distribcell tally">
<filters>1 2</filters>
<nuclides>U234 U235 U238</nuclides>
<scores>nu-fission total</scores>
</tally>
</tallies>

View file

@ -1 +1 @@
a5a6f035b6106bd6d0312f0f339193f8745f9e3260c704d60d230fc1675a8e779b58a73a2c1f84e8f312d8a0e335d2d84341fe7df25e24024cc09a31058ebfe7
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View file

@ -1,38 +1,38 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell fill="200" id="1" region="-6 34 -35" universe="0" />
<cell id="10" material="5" region="7 -8 31 -39" universe="0" />
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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 1 1 1 2 1 1 2 1 1 2 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 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
@ -73,12 +73,12 @@
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 </universes>
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5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
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5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
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<?xml version='1.0' encoding='utf-8'?>
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<sab name="c_H_in_H2O" />
</material>
<material id="11" name="Top of fuel assemblies">
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<sab name="c_H_in_H2O" />
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<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
<run_mode>eigenvalue</run_mode>
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<source strength="1.0">
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<parameters>-160 -160 -183 160 160 183</parameters>
</space>
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</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1" type="regular">
<dimension>2 2 2</dimension>
<lower_left>-160.0 -160.0 -183.0</lower_left>
<upper_right>160.0 160.0 183.0</upper_right>
</mesh>
<filter id="10001" type="material">
<bins>1 3</bins>
</filter>
<filter id="10000" type="energy">
<bins>0.0 2.53e-07 0.001 1.0 20.0</bins>
</filter>
<filter id="10002" type="distribcell">
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</filter>
<filter id="10003" type="mesh">
<bins>1</bins>
</filter>
<tally id="10000" name="tally 1">
<filters>10001 10000 10002</filters>
<nuclides>U234 U235</nuclides>
<scores>nu-fission total</scores>
</tally>
<tally id="10001" name="tally 2">
<filters>10000 10003</filters>
<nuclides>U238 U235</nuclides>
<scores>total fission</scores>
</tally>
<mesh id="1" type="regular">
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</filter>
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</filter>
<tally id="1" name="tally 1">
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<nuclides>U234 U235</nuclides>
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</tally>
<tally id="2" name="tally 2">
<filters>1 4</filters>
<nuclides>U238 U235</nuclides>
<scores>total fission</scores>
</tally>
</tallies>

View file

@ -1,38 +1,38 @@
<?xml version='1.0' encoding='utf-8'?>
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@ -73,12 +73,12 @@
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<nuclide ao="1.0" name="O16" />
<nuclide ao="0.000649" name="B10" />
<nuclide ao="0.002689" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material id="5" name="Reactor pressure vessel steel">
<density units="g/cm3" value="7.9" />
<nuclide name="Fe54" wo="0.05437098" />
<nuclide name="Fe56" wo="0.88500663" />
<nuclide name="Fe57" wo="0.0208008" />
<nuclide name="Fe58" wo="0.00282159" />
<nuclide name="Ni58" wo="0.0067198" />
<nuclide name="Ni60" wo="0.0026776" />
<nuclide name="Mn55" wo="0.01" />
<nuclide name="Cr52" wo="0.002092475" />
<nuclide name="C0" wo="0.0025" />
<nuclide name="Cu63" wo="0.0013696" />
</material>
<material id="6" name="Lower radial reflector">
<density units="g/cm3" value="4.32" />
<nuclide name="H1" wo="0.0095661" />
<nuclide name="O16" wo="0.0759107" />
<nuclide name="B10" wo="3.08409e-05" />
<nuclide name="B11" wo="0.000140499" />
<nuclide name="Fe54" wo="0.035620772088" />
<nuclide name="Fe56" wo="0.579805982228" />
<nuclide name="Fe57" wo="0.01362750048" />
<nuclide name="Fe58" wo="0.001848545204" />
<nuclide name="Ni58" wo="0.055298376566" />
<nuclide name="Mn55" wo="0.018287" />
<nuclide name="Cr52" wo="0.145407678031" />
<sab name="c_H_in_H2O" />
</material>
<material id="7" name="Upper radial reflector / Top plate region">
<density units="g/cm3" value="4.28" />
<nuclide name="H1" wo="0.0086117" />
<nuclide name="O16" wo="0.0683369" />
<nuclide name="B10" wo="2.77638e-05" />
<nuclide name="B11" wo="0.000126481" />
<nuclide name="Fe54" wo="0.035953677186" />
<nuclide name="Fe56" wo="0.585224740891" />
<nuclide name="Fe57" wo="0.01375486056" />
<nuclide name="Fe58" wo="0.001865821363" />
<nuclide name="Ni58" wo="0.055815129186" />
<nuclide name="Mn55" wo="0.0184579" />
<nuclide name="Cr52" wo="0.146766614995" />
<sab name="c_H_in_H2O" />
</material>
<material id="8" name="Bottom plate region">
<density units="g/cm3" value="7.184" />
<nuclide name="H1" wo="0.0011505" />
<nuclide name="O16" wo="0.0091296" />
<nuclide name="B10" wo="3.70915e-06" />
<nuclide name="B11" wo="1.68974e-05" />
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<nuclide name="Fe56" wo="0.627585036425" />
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<nuclide name="Fe58" wo="0.002000875025" />
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<nuclide name="Cr52" wo="0.157390026871" />
<sab name="c_H_in_H2O" />
</material>
<material id="9" name="Bottom nozzle region">
<density units="g/cm3" value="2.53" />
<nuclide name="H1" wo="0.0245014" />
<nuclide name="O16" wo="0.1944274" />
<nuclide name="B10" wo="7.89917e-05" />
<nuclide name="B11" wo="0.000359854" />
<nuclide name="Fe54" wo="0.030411411144" />
<nuclide name="Fe56" wo="0.495012237964" />
<nuclide name="Fe57" wo="0.01163454624" />
<nuclide name="Fe58" wo="0.001578204652" />
<nuclide name="Ni58" wo="0.047211231662" />
<nuclide name="Mn55" wo="0.0156126" />
<nuclide name="Cr52" wo="0.124142524198" />
<sab name="c_H_in_H2O" />
</material>
<material id="10" name="Top nozzle region">
<density units="g/cm3" value="1.746" />
<nuclide name="H1" wo="0.035887" />
<nuclide name="O16" wo="0.2847761" />
<nuclide name="B10" wo="0.000115699" />
<nuclide name="B11" wo="0.000527075" />
<nuclide name="Fe54" wo="0.02644016154" />
<nuclide name="Fe56" wo="0.43037146399" />
<nuclide name="Fe57" wo="0.0101152584" />
<nuclide name="Fe58" wo="0.00137211607" />
<nuclide name="Ni58" wo="0.04104621835" />
<nuclide name="Mn55" wo="0.0135739" />
<nuclide name="Cr52" wo="0.107931450781" />
<sab name="c_H_in_H2O" />
</material>
<material id="11" name="Top of fuel assemblies">
<density units="g/cm3" value="3.044" />
<nuclide name="H1" wo="0.0162913" />
<nuclide name="O16" wo="0.1292776" />
<nuclide name="B10" wo="5.25228e-05" />
<nuclide name="B11" wo="0.000239272" />
<nuclide name="Zr90" wo="0.43313403903" />
<nuclide name="Zr91" wo="0.09549277374" />
<nuclide name="Zr92" wo="0.14759527104" />
<nuclide name="Zr94" wo="0.15280552077" />
<nuclide name="Zr96" wo="0.02511169542" />
<sab name="c_H_in_H2O" />
</material>
<material id="12" name="Bottom of fuel assemblies">
<density units="g/cm3" value="1.762" />
<nuclide name="H1" wo="0.0292856" />
<nuclide name="O16" wo="0.2323919" />
<nuclide name="B10" wo="9.44159e-05" />
<nuclide name="B11" wo="0.00043012" />
<nuclide name="Zr90" wo="0.3741373658" />
<nuclide name="Zr91" wo="0.0824858164" />
<nuclide name="Zr92" wo="0.1274914944" />
<nuclide name="Zr94" wo="0.1319920622" />
<nuclide name="Zr96" wo="0.0216912612" />
<sab name="c_H_in_H2O" />
</material>
</materials>
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
<run_mode>eigenvalue</run_mode>
<particles>100</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>-160 -160 -183 160 160 183</parameters>
</space>
</source>
</settings>
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<!--mesh-->
<mesh id="10000" type="regular">
<dimension>2 2</dimension>
<lower_left>-50.0 -50.0</lower_left>
<upper_right>50.0 50.0</upper_right>
</mesh>
<filter id="10015" type="cell">
<bins>21 27</bins>
</filter>
<filter id="10007" type="energy">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="10005" type="distribcell">
<bins>21</bins>
</filter>
<filter id="10006" type="mesh">
<bins>10000</bins>
</filter>
<tally id="10030" name="cell tally">
<filters>10015 10007</filters>
<nuclides>U235 U238</nuclides>
<scores>fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10031" name="distribcell tally">
<filters>10005 10007</filters>
<nuclides>U235 U238</nuclides>
<scores>fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10032" name="mesh tally">
<filters>10006 10007</filters>
<nuclides>U235 U238</nuclides>
<scores>fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<!--mesh-->
<mesh id="1" type="regular">
<dimension>2 2</dimension>
<lower_left>-50.0 -50.0</lower_left>
<upper_right>50.0 50.0</upper_right>
</mesh>
<filter id="16" type="cell">
<bins>21 27</bins>
</filter>
<filter id="8" type="energy">
<bins>0.0 0.625 20000000.0</bins>
</filter>
<filter id="6" type="distribcell">
<bins>21</bins>
</filter>
<filter id="7" type="mesh">
<bins>1</bins>
</filter>
<tally id="31" name="cell tally">
<filters>16 8</filters>
<nuclides>U235 U238</nuclides>
<scores>fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="32" name="distribcell tally">
<filters>6 8</filters>
<nuclides>U235 U238</nuclides>
<scores>fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="33" name="mesh tally">
<filters>7 8</filters>
<nuclides>U235 U238</nuclides>
<scores>fission nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
</tallies>

View file

@ -1,36 +1,36 @@
cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 21 0.00e+00 6.25e-01 U235 fission 2.36e-01 2.26e-02 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 21 0.00e+00 6.25e-01 U235 nu-fission 5.74e-01 5.51e-02 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 21 0.00e+00 6.25e-01 U238 fission 3.19e-07 3.06e-08 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 21 0.00e+00 6.25e-01 U238 nu-fission 7.96e-07 7.63e-08 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 21 6.25e-01 2.00e+07 U235 fission 2.82e-02 1.82e-03 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 21 6.25e-01 2.00e+07 U235 nu-fission 6.92e-02 4.42e-03 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 21 6.25e-01 2.00e+07 U238 fission 1.98e-02 1.74e-03 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 21 6.25e-01 2.00e+07 U238 nu-fission 5.54e-02 4.65e-03 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 27 0.00e+00 6.25e-01 U235 fission 1.11e-01 1.16e-02 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 27 0.00e+00 6.25e-01 U235 nu-fission 2.71e-01 2.83e-02 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 27 0.00e+00 6.25e-01 U238 fission 1.53e-07 1.67e-08 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 27 0.00e+00 6.25e-01 U238 nu-fission 3.81e-07 4.15e-08 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 27 6.25e-01 2.00e+07 U235 fission 2.00e-02 2.72e-03 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 27 6.25e-01 2.00e+07 U235 nu-fission 4.89e-02 6.62e-03 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 27 6.25e-01 2.00e+07 U238 fission 1.06e-02 6.18e-04 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 27 6.25e-01 2.00e+07 U238 nu-fission 2.91e-02 1.85e-03 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 21 0.00e+00 6.25e-01 U235 fission 2.36e-01 2.26e-02
1 21 0.00e+00 6.25e-01 U235 nu-fission 5.74e-01 5.51e-02
2 21 0.00e+00 6.25e-01 U238 fission 3.19e-07 3.06e-08
3 21 0.00e+00 6.25e-01 U238 nu-fission 7.96e-07 7.63e-08
4 21 6.25e-01 2.00e+07 U235 fission 2.82e-02 1.82e-03
5 21 6.25e-01 2.00e+07 U235 nu-fission 6.92e-02 4.42e-03
6 21 6.25e-01 2.00e+07 U238 fission 1.98e-02 1.74e-03
7 21 6.25e-01 2.00e+07 U238 nu-fission 5.54e-02 4.65e-03
8 27 0.00e+00 6.25e-01 U235 fission 1.11e-01 1.16e-02
9 27 0.00e+00 6.25e-01 U235 nu-fission 2.71e-01 2.83e-02
10 27 0.00e+00 6.25e-01 U238 fission 1.53e-07 1.67e-08
11 27 0.00e+00 6.25e-01 U238 nu-fission 3.81e-07 4.15e-08
12 27 6.25e-01 2.00e+07 U235 fission 2.00e-02 2.72e-03
13 27 6.25e-01 2.00e+07 U235 nu-fission 4.89e-02 6.62e-03
14 27 6.25e-01 2.00e+07 U238 fission 1.06e-02 6.18e-04
15 27 6.25e-01 2.00e+07 U238 nu-fission 2.91e-02 1.85e-03
0 21 0.00e+00 6.25e-01 U235 fission 2.21e-01 9.47e-03 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 21 0.00e+00 6.25e-01 U235 nu-fission 5.38e-01 2.31e-02 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 21 0.00e+00 6.25e-01 U238 fission 3.05e-07 1.36e-08 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 21 0.00e+00 6.25e-01 U238 nu-fission 7.60e-07 3.39e-08 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 21 6.25e-01 2.00e+07 U235 fission 3.97e-02 4.54e-03 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 21 6.25e-01 2.00e+07 U235 nu-fission 9.72e-02 1.10e-02 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 21 6.25e-01 2.00e+07 U238 fission 1.89e-02 1.11e-03 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 21 6.25e-01 2.00e+07 U238 nu-fission 5.31e-02 3.32e-03 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 27 0.00e+00 6.25e-01 U235 fission 6.24e-02 1.10e-02 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 27 0.00e+00 6.25e-01 U235 nu-fission 1.52e-01 2.67e-02 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 27 0.00e+00 6.25e-01 U238 fission 8.80e-08 1.49e-08 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 27 0.00e+00 6.25e-01 U238 nu-fission 2.19e-07 3.72e-08 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 27 6.25e-01 2.00e+07 U235 fission 1.08e-02 1.46e-03 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 27 6.25e-01 2.00e+07 U235 nu-fission 2.65e-02 3.55e-03 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 27 6.25e-01 2.00e+07 U238 fission 5.88e-03 9.74e-04 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 27 6.25e-01 2.00e+07 U238 nu-fission 1.61e-02 2.59e-03 cell energy low [eV] energy high [eV] nuclide score mean std. dev.
0 21 0.00e+00 6.25e-01 U235 fission 2.21e-01 9.47e-03
1 21 0.00e+00 6.25e-01 U235 nu-fission 5.38e-01 2.31e-02
2 21 0.00e+00 6.25e-01 U238 fission 3.05e-07 1.36e-08
3 21 0.00e+00 6.25e-01 U238 nu-fission 7.60e-07 3.39e-08
4 21 6.25e-01 2.00e+07 U235 fission 3.97e-02 4.54e-03
5 21 6.25e-01 2.00e+07 U235 nu-fission 9.72e-02 1.10e-02
6 21 6.25e-01 2.00e+07 U238 fission 1.89e-02 1.11e-03
7 21 6.25e-01 2.00e+07 U238 nu-fission 5.31e-02 3.32e-03
8 27 0.00e+00 6.25e-01 U235 fission 6.24e-02 1.10e-02
9 27 0.00e+00 6.25e-01 U235 nu-fission 1.52e-01 2.67e-02
10 27 0.00e+00 6.25e-01 U238 fission 8.80e-08 1.49e-08
11 27 0.00e+00 6.25e-01 U238 nu-fission 2.19e-07 3.72e-08
12 27 6.25e-01 2.00e+07 U235 fission 1.08e-02 1.46e-03
13 27 6.25e-01 2.00e+07 U235 nu-fission 2.65e-02 3.55e-03
14 27 6.25e-01 2.00e+07 U238 fission 5.88e-03 9.74e-04
15 27 6.25e-01 2.00e+07 U238 nu-fission 1.61e-02 2.59e-03
sum(distribcell) energy low [eV] energy high [eV] nuclide score mean std. dev.
0 (0, 100, 2000, 30000) 0.00e+00 6.25e-01 U235 fission 0.00e+00 0.00e+00
1 (0, 100, 2000, 30000) 0.00e+00 6.25e-01 U235 nu-fission 0.00e+00 0.00e+00
@ -49,19 +49,19 @@
14 (500, 5000, 50000) 6.25e-01 2.00e+07 U238 fission 0.00e+00 0.00e+00
15 (500, 5000, 50000) 6.25e-01 2.00e+07 U238 nu-fission 0.00e+00 0.00e+00
sum(mesh) energy low [eV] energy high [eV] nuclide score mean std. dev.
0 ((1, 1, 1), (1, 2, 1)) 0.00e+00 6.25e-01 U235 fission 1.12e-02 2.45e-03
1 ((1, 1, 1), (1, 2, 1)) 0.00e+00 6.25e-01 U235 nu-fission 2.74e-02 5.96e-03
2 ((1, 1, 1), (1, 2, 1)) 0.00e+00 6.25e-01 U238 fission 1.56e-08 3.04e-09
3 ((1, 1, 1), (1, 2, 1)) 0.00e+00 6.25e-01 U238 nu-fission 3.89e-08 7.57e-09
4 ((1, 1, 1), (1, 2, 1)) 6.25e-01 2.00e+07 U235 fission 1.15e-03 4.71e-04
5 ((1, 1, 1), (1, 2, 1)) 6.25e-01 2.00e+07 U235 nu-fission 2.81e-03 1.15e-03
6 ((1, 1, 1), (1, 2, 1)) 6.25e-01 2.00e+07 U238 fission 3.25e-04 9.99e-05
7 ((1, 1, 1), (1, 2, 1)) 6.25e-01 2.00e+07 U238 nu-fission 8.81e-04 2.68e-04
8 ((2, 1, 1), (2, 2, 1)) 0.00e+00 6.25e-01 U235 fission 1.44e-02 5.57e-03
9 ((2, 1, 1), (2, 2, 1)) 0.00e+00 6.25e-01 U235 nu-fission 3.51e-02 1.36e-02
10 ((2, 1, 1), (2, 2, 1)) 0.00e+00 6.25e-01 U238 fission 1.95e-08 7.37e-09
11 ((2, 1, 1), (2, 2, 1)) 0.00e+00 6.25e-01 U238 nu-fission 4.86e-08 1.84e-08
12 ((2, 1, 1), (2, 2, 1)) 6.25e-01 2.00e+07 U235 fission 2.55e-03 1.30e-03
13 ((2, 1, 1), (2, 2, 1)) 6.25e-01 2.00e+07 U235 nu-fission 6.23e-03 3.16e-03
14 ((2, 1, 1), (2, 2, 1)) 6.25e-01 2.00e+07 U238 fission 8.62e-04 4.53e-04
15 ((2, 1, 1), (2, 2, 1)) 6.25e-01 2.00e+07 U238 nu-fission 2.30e-03 1.21e-03
0 ((1, 1, 1), (1, 2, 1)) 0.00e+00 6.25e-01 U235 fission 1.48e-02 3.65e-03
1 ((1, 1, 1), (1, 2, 1)) 0.00e+00 6.25e-01 U235 nu-fission 3.60e-02 8.90e-03
2 ((1, 1, 1), (1, 2, 1)) 0.00e+00 6.25e-01 U238 fission 2.06e-08 4.98e-09
3 ((1, 1, 1), (1, 2, 1)) 0.00e+00 6.25e-01 U238 nu-fission 5.14e-08 1.24e-08
4 ((1, 1, 1), (1, 2, 1)) 6.25e-01 2.00e+07 U235 fission 2.23e-03 3.92e-04
5 ((1, 1, 1), (1, 2, 1)) 6.25e-01 2.00e+07 U235 nu-fission 5.45e-03 9.56e-04
6 ((1, 1, 1), (1, 2, 1)) 6.25e-01 2.00e+07 U238 fission 5.58e-04 2.08e-04
7 ((1, 1, 1), (1, 2, 1)) 6.25e-01 2.00e+07 U238 nu-fission 1.50e-03 5.43e-04
8 ((2, 1, 1), (2, 2, 1)) 0.00e+00 6.25e-01 U235 fission 2.56e-02 5.50e-03
9 ((2, 1, 1), (2, 2, 1)) 0.00e+00 6.25e-01 U235 nu-fission 6.24e-02 1.34e-02
10 ((2, 1, 1), (2, 2, 1)) 0.00e+00 6.25e-01 U238 fission 3.55e-08 7.70e-09
11 ((2, 1, 1), (2, 2, 1)) 0.00e+00 6.25e-01 U238 nu-fission 8.85e-08 1.92e-08
12 ((2, 1, 1), (2, 2, 1)) 6.25e-01 2.00e+07 U235 fission 5.01e-03 1.38e-03
13 ((2, 1, 1), (2, 2, 1)) 6.25e-01 2.00e+07 U235 nu-fission 1.22e-02 3.37e-03
14 ((2, 1, 1), (2, 2, 1)) 6.25e-01 2.00e+07 U238 fission 2.40e-03 2.69e-04
15 ((2, 1, 1), (2, 2, 1)) 6.25e-01 2.00e+07 U238 nu-fission 6.60e-03 7.63e-04

View file

@ -1,442 +1,442 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="10000" material="10000" region="-10000" universe="10000" />
<cell id="10001" material="10001" region="10000 -10001" universe="10000" />
<cell id="10002" material="10002" region="10001 -10002" universe="10000" />
<cell id="10003" material="10003" region="10002 -10003" universe="10000" />
<cell id="10004" material="10004" region="10003" universe="10000" />
<cell fill="10001" id="10105" region="10104 -10105 10106 -10107 10108 -10109" universe="0" />
<cell fill="10000" id="10106" region="-10110" translation="-0.00140620118176 -0.0152577471673 -0.0918476696602" universe="10026" />
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View file

@ -1,51 +1,51 @@
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