Revising with develop with its latest th5 merge

This commit is contained in:
Adam Nelson 2016-09-08 05:17:30 -04:00
commit 6cf7f7fa48
31 changed files with 29 additions and 66 deletions

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@ -758,12 +758,10 @@ a material default temperature.
The ``<temperature_method>`` element has an accepted value of "nearest" or
"interpolation". A value of "nearest" indicates that for each cell, the nearest
temperature at which cross sections are given is to be applied, within a given
tolerance (see :ref:`temperature_tolerance`). A value of "interpolation"
indicates that cross sections are to be interpolated between temperatures at
which nuclear data are present. A value of "multipole" indicates that the
windowed multipole method should be used to evaluate temperature-dependent cross
sections in the resolved resonance range (a :ref:`windowed multipole library
<multipole_library>` must also be available).
tolerance (see :ref:`temperature_tolerance`). A value of "multipole" indicates
that the windowed multipole method should be used to evaluate
temperature-dependent cross sections in the resolved resonance range (a
:ref:`windowed multipole library <multipole_library>` must also be available).
*Default*: "nearest"

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@ -23,8 +23,7 @@ if sys.version_info[0] >= 3:
def _get_metadata(zaid, metastable_scheme='nndc'):
"""Method to obtain the complete element name, element, Z, mass_number,
and metastable state
"""Return basic identifying data for a nuclide with a given ZAID.
Parameters
----------
@ -283,8 +282,7 @@ class IncidentNeutron(EqualityMixin):
self._urr = urr
def add_temperature_from_ace(self, ace_or_filename, metastable_scheme='nndc'):
"""Add data to the IncidentNeutron object from an ACE file at a
different temperature.
"""Append data from an ACE file at a different temperature.
Parameters
----------

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@ -226,7 +226,7 @@ class ThermalScattering(EqualityMixin):
# Write basic data
g = f.create_group(self.name)
g.attrs['atomic_weight_ratio'] = self.atomic_weight_ratio
g.attrs['nuclides'] = np.string_(self.nuclides)
g.attrs['nuclides'] = np.array(self.nuclides, dtype='S')
g.attrs['secondary_mode'] = np.string_(self.secondary_mode)
ktg = g.create_group('kTs')
for i, temperature in enumerate(self.temperatures):

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@ -724,32 +724,14 @@ class Materials(cv.CheckedList):
materials : Iterable of openmc.Material
Materials to add to the collection
Attributes
----------
default_temperature : str
The default temperature identifier applied to a material when none is
specified. The units are in Kelvin and the temperature rounded to the
nearest integer. For example, a tempreature of 293.6K would be
provided as '294K'
"""
def __init__(self, materials=None):
super(Materials, self).__init__(Material, 'materials collection')
self._default_temperature = None
self._materials_file = ET.Element("materials")
if materials is not None:
self += materials
@property
def default_temperature(self):
return self._default_temperature
@default_temperature.setter
def default_temperature(self, temperature):
cv.check_type('default_temperature', temperature, basestring)
self._default_temperature = temperature
def add_material(self, material):
"""Append material to collection
@ -831,11 +813,6 @@ class Materials(cv.CheckedList):
material.make_isotropic_in_lab()
def _create_material_subelements(self):
if self._default_temperature is not None:
subelement = ET.SubElement(self._materials_file,
"default_temperature")
subelement.text = self._default_temperature
for material in self:
xml_element = material.get_material_xml()
self._materials_file.append(xml_element)

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@ -113,7 +113,7 @@ class Settings(object):
temperatures at which nuclear data doesn't exist. Accepted keys are
'default', 'method', and 'tolerance'. The value for 'default' should be
a float representing the default temperature in Kelvin. The value for
'method' should be 'nearest' or 'interpolation'. If the method is
'method' should be 'nearest' or 'multipole'. If the method is
'nearest', 'tolerance' indicates a range of temperature within which
cross sections may be used.
trigger_active : bool

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@ -2518,7 +2518,6 @@ contains
call h5aget_type_f(attr_id, filetype, hdf5_err)
call h5tget_size_f(filetype, size, hdf5_err)
if (size > len(buffer(1)) + 1) then
print *, size, len(buffer(1))
call fatal_error("Character buffer is not long enough to &
&read HDF5 string array.")
end if

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@ -194,7 +194,6 @@ module nuclide_header
real(8), intent(in) :: tolerance
integer :: i
integer :: n
integer :: storage_type
integer :: max_corder
integer :: n_links
@ -203,7 +202,7 @@ module nuclide_header
integer :: n_temperature
integer(HID_T) :: urr_group, nu_group
integer(HID_T) :: energy_group, energy_dset
integer(HID_T) :: kT_group, kT_dset
integer(HID_T) :: kT_group
integer(HID_T) :: rxs_group
integer(HID_T) :: rx_group
integer(HID_T) :: total_nu

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@ -87,7 +87,6 @@ contains
real(8), intent(in) :: tolerance
integer :: i, j
integer :: n
integer :: t
integer :: n_energy, n_energy_out, n_mu
integer :: i_closest
@ -98,7 +97,7 @@ contains
integer(HID_T) :: elastic_group
integer(HID_T) :: inelastic_group
integer(HID_T) :: dset_id
integer(HID_T) :: kT_group, kT_dset
integer(HID_T) :: kT_group
integer(HSIZE_T) :: dims2(2)
integer(HSIZE_T) :: dims3(3)
real(8), allocatable :: temp(:,:)

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@ -271,7 +271,6 @@ class InputSet(object):
bot_fa.add_s_alpha_beta('c_H_in_H2O')
# Define the materials file.
self.materials.default_temperature = '294K'
self.materials += (fuel, clad, cold_water, hot_water, rpv_steel,
lower_rad_ref, upper_rad_ref, bot_plate,
bot_nozzle, top_nozzle, top_fa, bot_fa)
@ -615,7 +614,6 @@ class PinCellInputSet(object):
hot_water.add_s_alpha_beta('c_H_in_H2O')
# Define the materials file.
self.materials.default_temperature = '294K'
self.materials += (fuel, clad, hot_water)
# Instantiate ZCylinder surfaces
@ -717,7 +715,6 @@ class AssemblyInputSet(object):
hot_water.add_s_alpha_beta('c_H_in_H2O')
# Define the materials file.
self.materials.default_temperature = '294K'
self.materials += (fuel, clad, hot_water)
# Instantiate ZCylinder surfaces
@ -845,7 +842,6 @@ class MGInputSet(InputSet):
water.add_macroscopic(water_data)
# Define the materials file.
self.materials.default_temperature = '294K'
self.materials += (uo2, clad, water)
# Define surfaces.

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@ -29,7 +29,6 @@ class DistribmatTestHarness(PyAPITestHarness):
light_fuel.add_nuclide('U235', 1.0)
mats_file = openmc.Materials([moderator, dense_fuel, light_fuel])
mats_file.default_temperature = '294K'
mats_file.export_to_xml()

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@ -93,7 +93,6 @@ class TRISOTestHarness(PyAPITestHarness):
settings.export_to_xml()
mats = openmc.Materials([fuel, porous_carbon, ipyc, sic, opyc, graphite])
mats.default_temperature = '294K'
mats.export_to_xml()

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@ -1 +1 @@
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@ -24,7 +24,6 @@ class VolumeTest(PyAPITestHarness):
fuel.set_density('g/cc', 4.5)
materials = openmc.Materials((water, fuel))
materials.default_temperature = '294K'
materials.export_to_xml()
cyl = openmc.ZCylinder(1, R=1.0, boundary_type='vacuum')