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merge from_hdf5_misc changes

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Adam Nelson 2016-11-30 19:51:21 -05:00
commit c87ca6f989
2 changed files with 17 additions and 17 deletions
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4
openmc/mgxs/mgxs.py
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@ -63,7 +63,7 @@ _DOMAINS = (openmc.Cell,
MU_TREATMENTS = ('legendre', 'histogram')
# Maximum Legendre order supported by OpenMC
MAX_LEGENDRE = 10
_MAX_LEGENDRE = 10
@add_metaclass(ABCMeta)
@ -3478,7 +3478,7 @@ class ScatterMatrixXS(MatrixMGXS):
cv.check_type('legendre_order', legendre_order, Integral)
cv.check_greater_than('legendre_order', legendre_order, 0,
equality=True)
cv.check_less_than('legendre_order', legendre_order, MAX_LEGENDRE,
cv.check_less_than('legendre_order', legendre_order, _MAX_LEGENDRE,
equality=True)
if self.scatter_format == 'legendre':

30
openmc/mgxs_library.py
View file

@ -71,50 +71,50 @@ class XSdata(object):
Number of equal width angular bins that the polar angular domain is
subdivided into. This only applies when :attr:`XSdata.representation`
is "angle".
total : dict of numpy.ndarray
total : list of numpy.ndarray
Group-wise total cross section.
absorption : dict of numpy.ndarray
absorption : list of numpy.ndarray
Group-wise absorption cross section.
scatter_matrix : dict of numpy.ndarray
scatter_matrix : list of numpy.ndarray
Scattering moment matrices presented with the columns representing
incoming group and rows representing the outgoing group. That is,
down-scatter will be above the diagonal of the resultant matrix.
multiplicity_matrix : dict of numpy.ndarray
multiplicity_matrix : list of numpy.ndarray
Ratio of neutrons produced in scattering collisions to the neutrons
which undergo scattering collisions; that is, the multiplicity provides
the code with a scaling factor to account for neutrons produced in
(n,xn) reactions.
fission : dict of numpy.ndarray
fission : list of numpy.ndarray
Group-wise fission cross section.
kappa_fission : dict of numpy.ndarray
kappa_fission : list of numpy.ndarray
Group-wise kappa_fission cross section.
chi : dict of numpy.ndarray
chi : list of numpy.ndarray
Group-wise fission spectra ordered by increasing group index (i.e.,
fast to thermal). This attribute should be used if making the common
approximation that the fission spectra does not depend on incoming
energy. If the user does not wish to make this approximation, then
this should not be provided and this information included in the
:attr:`XSdata.nu_fission` attribute instead.
chi_prompt : dict of numpy.ndarray
chi_prompt : list of numpy.ndarray
Group-wise prompt fission spectra ordered by increasing group index
(i.e., fast to thermal). This attribute should be used if chi from
prompt and delayed neutrons is being set separately.
chi_delayed : dict of numpy.ndarray
chi_delayed : list of numpy.ndarray
Group-wise delayed fission spectra ordered by increasing group index
(i.e., fast to thermal). This attribute should be used if chi from
prompt and delayed neutrons is being set separately.
nu_fission : dict of numpy.ndarray
nu_fission : list of numpy.ndarray
Group-wise fission production cross section vector (i.e., if ``chi`` is
provided), or is the group-wise fission production matrix.
prompt_nu_fission : dict of numpy.ndarray
prompt_nu_fission : list of numpy.ndarray
Group-wise prompt fission production cross section vector.
delayed_nu_fission : dict of numpy.ndarray
delayed_nu_fission : list of numpy.ndarray
Group-wise delayed fission production cross section vector.
beta : dict of numpy.ndarray
beta : list of numpy.ndarray
Delayed-group-wise delayed neutron fraction cross section vector.
decay_rate : dict of numpy.ndarray
decay_rate : list of numpy.ndarray
Delayed-group-wise decay rate vector.
inverse_velocity : dict of numpy.ndarray
inverse_velocity : list of numpy.ndarray
Inverse of velocity, in units of sec/cm.
xs_shapes : dict of iterable of int
Dictionary with keys of _XS_SHAPES and iterable of int values with the