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https://github.com/openmc-dev/openmc.git
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Remove unused table types in openmc.data.ace
This commit is contained in:
Paul Romano
parent
68e5a093aa
commit
9230203efb
1 changed files with 1 additions and 366 deletions
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@ -1856,371 +1856,6 @@ class Reaction(object):
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return rxn
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class DosimetryTable(Table):
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def __init__(self, name, atomic_weight_ratio, temperature):
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super(DosimetryTable, self).__init__(
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name, atomic_weight_ratio, temperature)
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def __repr__(self):
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if hasattr(self, 'name'):
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return "<ACE Dosimetry Table: {0}>".format(self.name)
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else:
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return "<ACE Dosimetry Table>"
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class NeutronDiscreteTable(Table):
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def __init__(self, name, atomic_weight_ratio, temperature):
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super(NeutronDiscreteTable, self).__init__(
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name, atomic_weight_ratio, temperature)
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def __repr__(self):
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if hasattr(self, 'name'):
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return "<ACE Discrete-E Neutron Table: {0}>".format(self.name)
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else:
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return "<ACE Discrete-E Neutron Table>"
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class NeutronMGTable(Table):
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def __init__(self, name, atomic_weight_ratio, temperature):
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super(NeutronMGTable, self).__init__(
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name, atomic_weight_ratio, temperature)
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def __repr__(self):
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if hasattr(self, 'name'):
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return "<ACE Multigroup Neutron Table: {0}>".format(self.name)
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else:
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return "<ACE Multigroup Neutron Table>"
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class PhotoatomicTable(Table):
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def __init__(self, name, atomic_weight_ratio, temperature):
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super(PhotoatomicTable, self).__init__(
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name, atomic_weight_ratio, temperature)
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def __repr__(self):
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if hasattr(self, 'name'):
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return "<ACE Continuous-E Photoatomic Table: {0}>".format(self.name)
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else:
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return "<ACE Continuous-E Photoatomic Table>"
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def _read_all(self):
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self._read_eszg()
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self._read_jinc()
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self._read_jcoh()
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self._read_heating()
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self._read_compton_data()
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def _read_eszg(self):
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# Determine number of energies on common energy grid
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n_energies = self._nxs[3]
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# Read cross sections
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idx = self._jxs[1]
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data = np.asarray(self._xss[idx:idx + 5*n_energies])
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data.shape = (5, n_energies)
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self.energy = data[0]
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self.incoherent = data[1]
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self.coherent = data[2]
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self.photoelectric = data[3]
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self.pairproduction = data[4]
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def _read_jinc(self):
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# Read incoherent scattering function
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idx = self._jxs[2]
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self.incoherent_scattering = self._xss[idx:idx + 21]
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def _read_jcoh(self):
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# Read coherent form factors and integrated coherent form factors
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idx = self._jxs[3]
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self.int_coherent_form_factors = self._xss[idx:idx + 55]
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self.coherent_form_factors = self._xss[idx + 55:idx + 2*55]
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def _read_jflo(self):
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raise NotImplementedError
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def _read_heating(self):
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idx = self._jxs[5]
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self.avg_heating = self._xss[idx:idx + self._nxs[3]]
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def _read_compton_data(self):
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# Determine number of Compton profiles
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n_shells = self._nxs[5]
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if n_shells > 0:
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# Number of electrons per shell
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idx = self._jxs[6]
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self.electrons_per_shell = np.asarray(
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self._xss[idx:idx + n_shells], dtype=int)
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# Binding energy per shell
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idx = self._jxs[7]
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self.binding_energy_per_shell = self._xss[idx:idx + n_shells]
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# Probability of interaction per shell
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idx = self._jxs[8]
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self.probability_per_shell = self._xss[idx:idx + n_shells]
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# Initialize arrays for Compton profile data
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self.compton_profile_interp = np.zeros(n_shells)
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self.compton_profile_momentum = []
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self.compton_profile_pdf = []
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self.compton_profile_cdf = []
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for i in range(n_shells):
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# Get locator for SWD block
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loca = int(self._xss[self._jxs[9] + i])
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idx = self._jxs[10] + loca - 1
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# Get interpolation parameter and number of momentum entries
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self.compton_profile_interp[i] = int(self._xss[idx])
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n_momentum = int(self._xss[idx + 1])
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idx += 2
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# Get momentum entries, PDF, and CDF
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data = self._xss[idx:idx + 3*n_momentum]
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data.shape = (3, n_momentum)
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self.compton_profile_momentum.append(data[0])
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self.compton_profile_pdf.append(data[1])
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self.compton_profile_cdf.append(data[2])
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class PhotoatomicMGTable(Table):
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def __init__(self, name, atomic_weight_ratio, temperature):
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super(PhotoatomicMGTable, self).__init__(
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name, atomic_weight_ratio, temperature)
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def __repr__(self):
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if hasattr(self, 'name'):
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return "<ACE Multigroup Photoatomic Table: {0}>".format(self.name)
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else:
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return "<ACE Multigroup Photoatomic Table>"
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class ElectronTable(Table):
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def __init__(self, name, atomic_weight_ratio, temperature):
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super(ElectronTable, self).__init__(
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name, atomic_weight_ratio, temperature)
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def __repr__(self):
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if hasattr(self, 'name'):
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return "<ACE Electron Table: {0}>".format(self.name)
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else:
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return "<ACE Electron Table>"
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class PhotonuclearTable(Table):
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def __init__(self, name, atomic_weight_ratio, temperature):
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super(PhotonuclearTable, self).__init__(
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name, atomic_weight_ratio, temperature)
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self.reactions = OrderedDict()
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def __repr__(self):
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if hasattr(self, 'name'):
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return "<ACE Photonuclear Table: {0}>".format(self.name)
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else:
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return "<ACE Photonuclear Table>"
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def _read_all(self):
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self._read_basic()
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self._read_cross_sections()
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self._read_secondaries()
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self._read_angular_distributions()
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self._read_energy_distributions()
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def _read_basic(self):
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n_energies = self._nxs[3]
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# Read energy mesh
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idx = self._jxs[1]
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self.energy = self._xss[idx:idx + n_energies]
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# Read total cross section
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idx = self._jxs[2]
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self.total_xs = self._xss[idx:idx + n_energies]
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# Read non-elastic and elastic cross section
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if self._jxs[4] > 0:
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idx = self._jxs[3]
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self.non_elastic_xs = self._xss[idx:idx + n_energies]
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idx = self._jxs[4]
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self.elastic_xs = self._xss[idx:idx + n_energies]
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else:
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self.non_elastic_xs = self.total_xs.copy()
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self.elastic_xs = np.zeros(n_energies)
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# Read heating numbers
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idx = self._jxs[5]
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if idx > 0:
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self.heating_number = self._xss[idx:idx + n_energies]
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else:
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self.heating_number = np.zeros(n_energies)
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def _read_cross_sections(self):
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# Determine number of reactions
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n_reactions = self._nxs[4]
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# Read list of MT numbers and Q values
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mts = np.asarray(self._xss[self._jxs[6]:self._jxs[6] +
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n_reactions], dtype=int)
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qvalues = np.asarray(self._xss[self._jxs[7]:self._jxs[7] +
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n_reactions])
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# Create reactions in dictionary
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reactions = [(mt, Reaction(mt, self)) for mt in mts]
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self.reactions.update(reactions)
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for i, rx in enumerate(self.reactions.values()):
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# Copy Q values
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rx.Q_value = qvalues[i]
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# Determine starting index on energy grid and number of energies
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idx = self._jxs[9] + int(self._xss[self._jxs[8] + i]) - 1
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rx.threshold_idx = int(self._xss[idx])
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n_energies = int(self._xss[idx + 1])
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energy = self.energy[rx.threshold_idx:rx.threshold_idx + n_energies]
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idx += 2
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# Read reaction cross setion
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xs = self._xss[idx:idx + n_energies]
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rx.xs = Tabulated1D(energy, xs, [], [])
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def _read_secondaries(self):
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names = {1: 'neutron', 2: 'photon', 3: 'electron',
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9: 'proton', 31: 'deuteron', 32: 'triton',
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33: 'helium3', 34: 'alpha'}
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n_particles = self._nxs[5]
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n_entries = self._nxs[7]
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idx = self._jxs[10]
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ixs = np.asarray(self._xss[idx:idx + n_particles*n_entries], dtype=int)
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ixs.shape = (n_particles, n_entries)
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self.ixs = ixs.transpose()
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self.particles = []
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for j in range(n_particles):
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# Create dictionary for particle
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particle = {}
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self.particles.append(particle)
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# Get secondary particle type/name
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particle['ipt'] = self.ixs[0, j]
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particle['name'] = names[particle['ipt']]
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# Number of reactions that produce secondary particle
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n_producing = self.ixs[1, j]
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# Particle-production cross section
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idx = self.ixs[2, j]
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particle['ie_production'] = int(self._xss[idx])
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ne = int(self._xss[idx + 1])
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idx += 2
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particle['production'] = self._xss[idx:idx + ne]
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# Average heating numbers
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idx = self.ixs[3, j]
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particle['ie_heating'] = int(self._xss[idx])
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ne = int(self._xss[idx + 1])
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idx += 2
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particle['heating_number'] = self._xss[idx:idx + ne]
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# MTs of particle production reactions
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idx = self.ixs[4, j]
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particle['mt_producing'] = np.asarray(
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self._xss[idx:idx + n_producing], dtype=int)
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# Coordinate system of reaction producing secondary particle
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idx = self.ixs[5, j]
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particle['center_of_mass'] = [i < 0 for i in
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self._xss[idx:idx + n_producing]]
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# Reaction yields
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particle['yield'] = {}
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for k in range(n_producing):
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# Create dictionary for yield data
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yieldData = {}
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# Read reaction yield data for a single MT
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idx = self.ixs[7, j] + int(self._xss[self.ixs[6, j] + k]) - 1
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yieldData['mftype'] = int(self._xss[idx])
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idx += 1
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if yieldData['mftype'] in (6, 12, 16):
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# Yield data from ENDF File 6 or 12
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mtmult = int(self._xss[idx])
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assert mtmult == particle['mt_producing'][k]
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# Read yield as function of energy
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yieldData['multiplicity'] = _get_tabulated_1d(
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self._xss, idx + 1)
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elif yieldData['mftype'] == 13:
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# Production cross section for corresponding MT
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yieldData['ie'] = int(self._xss[idx])
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ne = int(self._xss[idx + 1])
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idx += 2
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yieldData['cross_section'] = self._xss[idx:idx + ne]
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# Add reaction yield data to dictionary
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mt = particle['mt_producing'][k]
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particle['yield'][mt] = yieldData
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def _read_angular_distributions(self):
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for j, particle in enumerate(self.particles):
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# Create dictionary for angular distributions
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angular_dists = {}
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particle['angular_distribution'] = angular_dists
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for k, mt in enumerate(particle['mt_producing']):
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landp = int(self._xss[self.ixs[8, j] + k])
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# check if angular distribution data exists
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if landp == -1:
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# Angular distribution data are specified through the
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# DLWP block
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continue
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elif landp == 0:
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# No angular distribution data are given for this
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# reaction, isotropic scattering is assumed
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ie = self.reactions[mt].threshold_idx
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ne = len(self.reactions[mt].sigma)
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angular_dists[mt] = AngularDistribution.isotropic(
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np.array([self.energy[ie], self.energy[ie + ne - 1]]))
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continue
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idx = self.ixs[9, j] + landp - 1
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angular_dists[mt] = AngularDistribution()
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angular_dists[mt].read(self._xss, idx, self.ixs[9, j])
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def _read_energy_distributions(self):
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for j, particle in enumerate(self.particles):
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# Create dictionary for energy distributions
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energy_dists = {}
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particle['energy_distribution'] = energy_dists
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for k, mt in enumerate(particle['mt_producing']):
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# Determine locator for kth energy distribution
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ldlwp = int(self._xss[self.ixs[10, j] + k])
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# Read energy distribution data
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energy_dists[mt] = self._get_energy_distribution(
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self.ixs[11, j], ldlwp)
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table_types = {
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"c": NeutronTable,
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"t": SabTable,
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"y": DosimetryTable,
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"d": NeutronDiscreteTable,
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"p": PhotoatomicTable,
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"m": NeutronMGTable,
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"g": PhotoatomicMGTable,
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"e": ElectronTable,
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"u": PhotonuclearTable}
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"t": SabTable}
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