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Now using a "data" descriptor rather than "ace" for the nuclide/element scattering XML tag

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This commit is contained in:
Will Boyd 2015-11-09 09:26:48 -05:00
parent 4db72c90af
commit baa0b4c10c
5 changed files with 19 additions and 19 deletions
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12
docs/source/usersguide/input.rst
View file

@ -1137,9 +1137,9 @@ Each ``material`` element can have the following attributes or sub-elements:
be given in atom percent. The same applies for weight percentages.
An optional attribute/sub-element for each nuclide is ``scattering``. This
attribute may be set to "ace" to use the scattering laws specified in the
ACE files (default). Alternatively, when set to "iso-in-lab", the ACE
scattering laws are used to sample the outgoing energy but an
attribute may be set to "data" to use the scattering laws specified by the
cross section library (default). Alternatively, when set to "iso-in-lab",
the scattering laws are used to sample the outgoing energy but an
isotropic-in-lab distribution is used to sample the outgoing angle at each
scattering interaction. The ``scattering`` attribute may be most useful
when using OpenMC to compute multi-group cross-sections for deterministic
@ -1172,9 +1172,9 @@ Each ``material`` element can have the following attributes or sub-elements:
*Default*: None
An optional attribute/sub-element for each element is ``scattering``. This
attribute may be set to "ace" to use the scattering laws specified in the
ACE files (default). Alternatively, when set to "iso-in-lab", the ACE
scattering laws are used to sample the outgoing energy but an
attribute may be set to "data" to use the scattering laws specified by the
cross section library (default). Alternatively, when set to "iso-in-lab",
the scattering laws are used to sample the outgoing energy but an
isotropic-in-lab distribution is used to sample the outgoing angle at each
scattering interaction. The ``scattering`` attribute may be most useful
when using OpenMC to compute multi-group cross-sections for deterministic

6
openmc/element.py
View file

@ -24,7 +24,7 @@ class Element(object):
Chemical symbol of the element, e.g. Pu
xs : str
Cross section identifier, e.g. 71c
scattering : 'ace' or 'iso-in-lab' or None
scattering : 'data' or 'iso-in-lab' or None
The type of angular scattering distribution to use
"""
@ -94,9 +94,9 @@ class Element(object):
@scattering.setter
def scattering(self, scattering):
if not scattering in ['ace', 'iso-in-lab']:
if not scattering in ['data', 'iso-in-lab']:
msg = 'Unable to set scattering for Element to {0} ' \
'which is not "ace" or "iso-in-lab"'.format(scattering)
'which is not "data" or "iso-in-lab"'.format(scattering)
raise ValueError(msg)
self._scattering = scattering

4
openmc/material.py
View file

@ -33,8 +33,8 @@ NO_DENSITY = 99999.
class Material(object):
"""A material composed of a collection of nuclides/elements that can be assigned
to a region of space.
"""A material composed of a collection of nuclides/elements that can be
assigned to a region of space.
Parameters
----------

6
openmc/nuclide.py
View file

@ -26,7 +26,7 @@ class Nuclide(object):
zaid : int
1000*(atomic number) + mass number. As an example, the zaid of U-235
would be 92235.
scattering : 'ace' or 'iso-in-lab' or None
scattering : 'data' or 'iso-in-lab' or None
The type of angular scattering distribution to use
"""
@ -104,9 +104,9 @@ class Nuclide(object):
@scattering.setter
def scattering(self, scattering):
if not scattering in ['ace', 'iso-in-lab']:
if not scattering in ['data', 'iso-in-lab']:
msg = 'Unable to set scattering for Nuclide to {0} ' \
'which is not "ace" or "iso-in-lab"'.format(scattering)
'which is not "data" or "iso-in-lab"'.format(scattering)
raise ValueError(msg)
self._scattering = scattering

10
src/input_xml.F90
View file

@ -1940,9 +1940,9 @@ contains
! Check enforced isotropic lab scattering
if (check_for_node(node_nuc, "scattering")) then
call get_node_value(node_nuc, "scattering", temp_str)
if (trim(adjustl(to_lower(temp_str))) == "iso-in-lab") then
if (adjustl(to_lower(temp_str)) == "iso-in-lab") then
call list_iso_lab % append(1)
else if (trim(adjustl(to_lower(temp_str))) == "ace") then
else if (adjustl(to_lower(temp_str)) == "data") then
call list_iso_lab % append(0)
else
call fatal_error("Scattering must be isotropic in lab or follow&
@ -2043,14 +2043,14 @@ contains
if (check_for_node(node_ele, "scattering")) then
call get_node_value(node_ele, "scattering", temp_str)
else
temp_str = "ace"
temp_str = "data"
end if
! Set ace or iso-in-lab scattering for each nuclide in element
do k = 1, n_nuc_ele
if (trim(adjustl(to_lower(temp_str))) == "iso-in-lab") then
if (adjustl(to_lower(temp_str)) == "iso-in-lab") then
call list_iso_lab % append(1)
else if (trim(adjustl(to_lower(temp_str))) == "ace") then
else if (adjustl(to_lower(temp_str)) == "data") then
call list_iso_lab % append(0)
else
call fatal_error("Scattering must be isotropic in lab or follow&