diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 6f8abefd1..ce7511193 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -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': diff --git a/openmc/mgxs_library.py b/openmc/mgxs_library.py index 70ff7a91b..3c2bffcef 100644 --- a/openmc/mgxs_library.py +++ b/openmc/mgxs_library.py @@ -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