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Fixing comments per the review by @paulromano

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This commit is contained in:
agnelson 2020-11-09 15:59:23 -06:00
parent a83e7fa0b7
commit a9ebadaecc
2 changed files with 14 additions and 15 deletions
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18
openmc/mgxs/library.py
View file

@ -946,10 +946,10 @@ class Library:
apply_domain_chi : bool
This parameter sets whether (True) or not (False) the
domain-averaged values of chi, chi-prompt, and chi-delayed are to
be applied to each of the nuclidic fission energy spectra of a
domain. In effect, if this is True, then every nuclide in the
be applied to each of the nuclide-dependent fission energy spectra
of a domain. In effect, if this is True, then every nuclide in the
domain receives the same flux-weighted Chi. This is useful for
downstream multigroup solvers that pre-compute a material-specific
downstream multigroup solvers that precompute a material-specific
chi before the transport solve provides group-wise fluxes. Defaults
to False.
@ -1242,10 +1242,10 @@ class Library:
apply_domain_chi : bool
This parameter sets whether (True) or not (False) the
domain-averaged values of chi, chi-prompt, and chi-delayed are to
be applied to each of the nuclidic fission energy spectra of a
domain. In effect, if this is True, then every nuclide in the
be applied to each of the nuclide-dependent fission energy spectra
of a domain. In effect, if this is True, then every nuclide in the
domain receives the same flux-weighted Chi. This is useful for
downstream multigroup solvers that pre-compute a material-specific
downstream multigroup solvers that precompute a material-specific
chi before the transport solve provides group-wise fluxes. Defaults
to False.
@ -1354,10 +1354,10 @@ class Library:
apply_domain_chi : bool
This parameter sets whether (True) or not (False) the
domain-averaged values of chi, chi-prompt, and chi-delayed are to
be applied to each of the nuclidic fission energy spectra of a
domain. In effect, if this is True, then every nuclide in the
be applied to each of the nuclide-dependent fission energy spectra
of a domain. In effect, if this is True, then every nuclide in the
domain receives the same flux-weighted Chi. This is useful for
downstream multigroup solvers that pre-compute a material-specific
downstream multigroup solvers that precompute a material-specific
chi before the transport solve provides group-wise fluxes. Defaults
to False.

11
openmc/mgxs/mgxs.py
View file

@ -47,8 +47,8 @@ MGXS_TYPES = (
# support and test (like inelastic levels), remoev those from consideration
_BAD_SCORES = ["(n,misc)", "(n,absorption)", "(n,total)", "fission"]
_BAD_SCORES += [REACTION_NAME[mt] for mt in FISSION_MTS]
ARBITRARY_VECTOR_TYPES = [k for k in REACTION_MT.keys() if k not in _BAD_SCORES]
ARBITRARY_VECTOR_TYPES = tuple(ARBITRARY_VECTOR_TYPES)
ARBITRARY_VECTOR_TYPES = tuple(k for k in REACTION_MT.keys()
if k not in _BAD_SCORES)
ARBITRARY_MATRIX_TYPES = []
for rxn in ARBITRARY_VECTOR_TYPES:
# Preclude the fission channels from being treated as a matrix
@ -1237,12 +1237,11 @@ class MGXS:
# Determine which flux to obtain
# Step through in order of usefulness
tally = None
for key in ['flux', 'flux (tracklength)', 'flux (analog)']:
if key in self.tally_keys:
tally = self.tallies[key]
break
if tally is None:
else:
msg = "MGXS of Type {} do not have an explicit weighting flux!"
raise ValueError(msg.format(self.__name__))
@ -4021,7 +4020,7 @@ class ArbitraryXS(MGXS):
\sigma_X (r, E) \psi (r, E, \Omega)}{\int_{r \in V} dr \int_{4\pi}
d\Omega \int_{E_g}^{E_{g-1}} dE \; \psi (r, E, \Omega)}
where :math:`_\sigma_X` is the requested reaction type of interest.
where :math:`\sigma_X` is the requested reaction type of interest.
Parameters
----------
@ -4152,7 +4151,7 @@ class ArbitraryMatrixXS(MatrixMGXS):
g} \phi \rangle}{\langle \phi \rangle}
\end{aligned}
where :math:`_\sigma_X` is the requested reaction type of interest.
where :math:`\sigma_X` is the requested reaction type of interest.
Parameters
----------