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pep8 fixes
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yardasol
parent
ecc38a1ae4
commit
5fec7a2355
1 changed files with 31 additions and 22 deletions
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@ -155,7 +155,6 @@ class FluxSpectraDepletionOperator(TransportOperator):
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self._yield_helper = fission_helper.from_operator(
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self, **fission_yield_opts)
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def __call__(self, vec, source_rate):
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"""Obtain the reaction rates
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@ -207,7 +206,12 @@ class FluxSpectraDepletionOperator(TransportOperator):
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for nuc in nuclides:
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density = number.get_atom_density('0', nuc)
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for rxn in self.chain.reactions:
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rates.set('0', nuc, rxn, self._micro_xs[rxn].loc[nuc] * density)
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rates.set(
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'0',
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nuc,
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rxn,
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self._micro_xs[rxn].loc[nuc] *
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density)
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# Get reaction rate in reactions/sec
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rates *= self.flux_spectra
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@ -219,7 +223,8 @@ class FluxSpectraDepletionOperator(TransportOperator):
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# the reason we do this is based on the mathematical equation;
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# in the equation, we multiply the depletion matrix by the nuclide
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# vector. Since what we want is the depletion matrix, we need to
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# divide the reaction rates by the number of atoms to get the right units.
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# divide the reaction rates by the number of atoms to get the right
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# units.
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mask = nonzero(number)
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results = rates[0]
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for col in range(results.shape[1]):
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@ -231,7 +236,6 @@ class FluxSpectraDepletionOperator(TransportOperator):
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return OperatorResult(self._keff, rates)
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def initial_condition(self):
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"""Performs final setup and returns initial condition.
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@ -244,8 +248,6 @@ class FluxSpectraDepletionOperator(TransportOperator):
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# Return number density vector
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return list(self.number.get_mat_slice(np.s_[:]))
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def write_bos_data(self, step):
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"""Document beginning of step data for a given step
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@ -260,7 +262,6 @@ class FluxSpectraDepletionOperator(TransportOperator):
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# Since we aren't running a transport simulation, we simply pass
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pass
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def get_results_info(self):
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"""Returns volume list, cell lists, and nuc lists.
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@ -287,9 +288,9 @@ class FluxSpectraDepletionOperator(TransportOperator):
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return volume, nuc_list, burn_list, burn_list
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@staticmethod
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def create_micro_xs_from_data_array(nuclides, reactions, data, units='barn'):
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def create_micro_xs_from_data_array(
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nuclides, reactions, data, units='barn'):
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"""
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Creates a ``micro_xs`` parameter from a dictionary.
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@ -316,9 +317,10 @@ class FluxSpectraDepletionOperator(TransportOperator):
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try:
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assert data.shape == (len(nuclides), len(reactions))
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except AssertionError:
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raise SyntaxError('Nuclides list of length {len(nuclides)} and'
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'reactions array of length {len(reactions)} do not'
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'match dimensions of data array of shape {data.shape}')
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raise SyntaxError(
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'Nuclides list of length {len(nuclides)} and'
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'reactions array of length {len(reactions)} do not'
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'match dimensions of data array of shape {data.shape}')
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check_iterable_type('nuclides', nuclides, str)
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check_iterable_type('reactions', reactions, str)
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@ -330,7 +332,6 @@ class FluxSpectraDepletionOperator(TransportOperator):
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return pd.DataFrame(index=nuclides, columns=reactions, data=data)
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@staticmethod
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def create_micro_xs_from_csv(csv_file, units='barn'):
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"""
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@ -356,7 +357,6 @@ class FluxSpectraDepletionOperator(TransportOperator):
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return micro_xs
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def _update_materials(self):
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"""Updates material compositions in OpenMC on all processes."""
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@ -383,14 +383,20 @@ class FluxSpectraDepletionOperator(TransportOperator):
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densities.append(val)
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else:
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# Only output warnings if values are significantly
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# negative. CRAM does not guarantee positive values.
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# negative. CRAM does not guarantee positive
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# values.
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if val < -1.0e-21:
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print("WARNING: nuclide ", nuc, " in material ", mat,
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" is negative (density = ", val, " at/barn-cm)")
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print(
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"WARNING: nuclide ",
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nuc,
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" in material ",
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mat,
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" is negative (density = ",
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val,
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" at/barn-cm)")
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number_i[mat, nuc] = 0.0
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#TODO Update densities on the Python side, otherwise the
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# TODO Update densities on the Python side, otherwise the
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# summary.h5 file contains densities at the first time step
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def _get_reaction_nuclides(self):
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@ -481,17 +487,20 @@ class FluxSpectraDepletionOperator(TransportOperator):
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if self.dilute_initial != 0.0:
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for nuc in self._burnable_nucs:
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self.number.set_atom_density(np.s_[:], nuc, self.dilute_initial)
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self.number.set_atom_density(
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np.s_[:], nuc, self.dilute_initial)
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# Now extract and store the number densities
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# From the geometry if no previous depletion results
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if prev_res is None:
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for nuclide in nuclides:
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if nuclide in self._init_nuclides:
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self.number.set_atom_density('0', nuclide, self._init_nuclides[nuclide])
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self.number.set_atom_density(
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'0', nuclide, self._init_nuclides[nuclide])
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elif nuclide not in self._burnable_nucs:
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self.number.set_atom_density('0', nuclide, 0)
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# Else from previous depletion results
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else:
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raise RuntimeError("Loading from previous results not yet supported")
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raise RuntimeError(
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"Loading from previous results not yet supported")
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