From 5fec7a2355819039007e509d4cc365dfcf6ac928 Mon Sep 17 00:00:00 2001 From: yardasol Date: Wed, 29 Jun 2022 15:05:22 -0500 Subject: [PATCH] pep8 fixes --- openmc/deplete/flux_operator.py | 53 +++++++++++++++++++-------------- 1 file changed, 31 insertions(+), 22 deletions(-) diff --git a/openmc/deplete/flux_operator.py b/openmc/deplete/flux_operator.py index ab6fbe565d..3ca046cf2d 100644 --- a/openmc/deplete/flux_operator.py +++ b/openmc/deplete/flux_operator.py @@ -155,7 +155,6 @@ class FluxSpectraDepletionOperator(TransportOperator): self._yield_helper = fission_helper.from_operator( self, **fission_yield_opts) - def __call__(self, vec, source_rate): """Obtain the reaction rates @@ -207,7 +206,12 @@ class FluxSpectraDepletionOperator(TransportOperator): for nuc in nuclides: density = number.get_atom_density('0', nuc) for rxn in self.chain.reactions: - rates.set('0', nuc, rxn, self._micro_xs[rxn].loc[nuc] * density) + rates.set( + '0', + nuc, + rxn, + self._micro_xs[rxn].loc[nuc] * + density) # Get reaction rate in reactions/sec rates *= self.flux_spectra @@ -219,7 +223,8 @@ class FluxSpectraDepletionOperator(TransportOperator): # the reason we do this is based on the mathematical equation; # in the equation, we multiply the depletion matrix by the nuclide # vector. Since what we want is the depletion matrix, we need to - # divide the reaction rates by the number of atoms to get the right units. + # divide the reaction rates by the number of atoms to get the right + # units. mask = nonzero(number) results = rates[0] for col in range(results.shape[1]): @@ -231,7 +236,6 @@ class FluxSpectraDepletionOperator(TransportOperator): return OperatorResult(self._keff, rates) - def initial_condition(self): """Performs final setup and returns initial condition. @@ -244,8 +248,6 @@ class FluxSpectraDepletionOperator(TransportOperator): # Return number density vector return list(self.number.get_mat_slice(np.s_[:])) - - def write_bos_data(self, step): """Document beginning of step data for a given step @@ -260,7 +262,6 @@ class FluxSpectraDepletionOperator(TransportOperator): # Since we aren't running a transport simulation, we simply pass pass - def get_results_info(self): """Returns volume list, cell lists, and nuc lists. @@ -287,9 +288,9 @@ class FluxSpectraDepletionOperator(TransportOperator): return volume, nuc_list, burn_list, burn_list - @staticmethod - def create_micro_xs_from_data_array(nuclides, reactions, data, units='barn'): + def create_micro_xs_from_data_array( + nuclides, reactions, data, units='barn'): """ Creates a ``micro_xs`` parameter from a dictionary. @@ -316,9 +317,10 @@ class FluxSpectraDepletionOperator(TransportOperator): try: assert data.shape == (len(nuclides), len(reactions)) except AssertionError: - raise SyntaxError('Nuclides list of length {len(nuclides)} and' - 'reactions array of length {len(reactions)} do not' - 'match dimensions of data array of shape {data.shape}') + raise SyntaxError( + 'Nuclides list of length {len(nuclides)} and' + 'reactions array of length {len(reactions)} do not' + 'match dimensions of data array of shape {data.shape}') check_iterable_type('nuclides', nuclides, str) check_iterable_type('reactions', reactions, str) @@ -330,7 +332,6 @@ class FluxSpectraDepletionOperator(TransportOperator): return pd.DataFrame(index=nuclides, columns=reactions, data=data) - @staticmethod def create_micro_xs_from_csv(csv_file, units='barn'): """ @@ -356,7 +357,6 @@ class FluxSpectraDepletionOperator(TransportOperator): return micro_xs - def _update_materials(self): """Updates material compositions in OpenMC on all processes.""" @@ -383,14 +383,20 @@ class FluxSpectraDepletionOperator(TransportOperator): densities.append(val) else: # Only output warnings if values are significantly - # negative. CRAM does not guarantee positive values. + # negative. CRAM does not guarantee positive + # values. if val < -1.0e-21: - print("WARNING: nuclide ", nuc, " in material ", mat, - " is negative (density = ", val, " at/barn-cm)") + print( + "WARNING: nuclide ", + nuc, + " in material ", + mat, + " is negative (density = ", + val, + " at/barn-cm)") number_i[mat, nuc] = 0.0 - - #TODO Update densities on the Python side, otherwise the + # TODO Update densities on the Python side, otherwise the # summary.h5 file contains densities at the first time step def _get_reaction_nuclides(self): @@ -481,17 +487,20 @@ class FluxSpectraDepletionOperator(TransportOperator): if self.dilute_initial != 0.0: for nuc in self._burnable_nucs: - self.number.set_atom_density(np.s_[:], nuc, self.dilute_initial) + self.number.set_atom_density( + np.s_[:], nuc, self.dilute_initial) # Now extract and store the number densities # From the geometry if no previous depletion results if prev_res is None: for nuclide in nuclides: if nuclide in self._init_nuclides: - self.number.set_atom_density('0', nuclide, self._init_nuclides[nuclide]) + self.number.set_atom_density( + '0', nuclide, self._init_nuclides[nuclide]) elif nuclide not in self._burnable_nucs: self.number.set_atom_density('0', nuclide, 0) # Else from previous depletion results else: - raise RuntimeError("Loading from previous results not yet supported") + raise RuntimeError( + "Loading from previous results not yet supported")