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Refactored openmc.mgxs.ScatterProbabilityMatrix to only calculate for scattering moment probabilities
This commit is contained in:
Will Boyd
parent
99db48bc8e
commit
2ab390c75b
12 changed files with 1071 additions and 1877 deletions
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@ -33,7 +33,6 @@ MGXS_TYPES = ['total',
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'multiplicity matrix',
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'nu-fission matrix',
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'scatter probability matrix',
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'nu-scatter probability matrix',
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'consistent scatter matrix',
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'consistent nu-scatter matrix',
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'chi',
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@ -737,9 +736,6 @@ class MGXS(object):
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mgxs = MultiplicityMatrixXS(domain, domain_type, energy_groups)
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elif mgxs_type == 'scatter probability matrix':
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mgxs = ScatterProbabilityMatrix(domain, domain_type, energy_groups)
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elif mgxs_type == 'nu-scatter probability matrix':
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mgxs = ScatterProbabilityMatrix(
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domain, domain_type, energy_groups, nu=True)
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elif mgxs_type == 'consistent scatter matrix':
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mgxs = ScatterMatrixXS(domain, domain_type, energy_groups)
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mgxs.formulation = 'consistent'
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@ -3559,7 +3555,7 @@ class ScatterMatrixXS(MatrixMGXS):
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group-to-group scattering probabilities.
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Unlike the default 'simple' formulation, the 'consistent' formulation
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is computed from the groupwise cattering cross section which uses a
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is computed from the groupwise scattering cross section which uses a
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tracklength estimator. This ensures that reaction rate balance is exactly
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preserved with a :class:`TotalXS` computed using a tracklength estimator.
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@ -4800,21 +4796,17 @@ class ScatterProbabilityMatrix(MatrixMGXS):
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.. math::
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\langle \sigma_{s,\ell,g'\rightarrow g} \phi \rangle &= \int_{r \in V} dr
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\langle \sigma_{s,g'\rightarrow g} \phi \rangle &= \int_{r \in V} dr
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\int_{4\pi} d\Omega' \int_{E_{g'}}^{E_{g'-1}} dE' \int_{4\pi} d\Omega
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\int_{E_g}^{E_{g-1}} dE \; P_\ell (\Omega \cdot \Omega')
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\sigma_{s} (r, E' \rightarrow E, \Omega' \cdot \Omega) \psi(r, E',
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\Omega')\\
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\int_{E_g}^{E_{g-1}} dE \; \sigma_{s} (r, E' \rightarrow E, \Omega'
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\cdot \Omega) \psi(r, E', \Omega')\\
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\langle \sigma_{s,0,g'} \phi \rangle &= \int_{r \in V} dr
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\int_{4\pi} d\Omega' \int_{E_{g'}}^{E_{g'-1}} dE' \int_{4\pi} d\Omega
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\int_{0}^{\infty} dE \; \sigma_s (r, E'
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\rightarrow E, \Omega' \cdot \Omega) \psi(r, E', \Omega')\\
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P_{s,\ell,g'\rightarrow g} &= \frac{\langle
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\sigma_{s,\ell,g'\rightarrow g} \phi \rangle}{\langle
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\sigma_{s,0,g'} \phi \rangle}
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To incorporate the effect of neutron multiplication from (n,xn) reactions
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in the above probability matrix, the `nu` parameter can be set to `True`.
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P_{s,g'\rightarrow g} &= \frac{\langle
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\sigma_{s,g'\rightarrow g} \phi \rangle}{\langle
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\sigma_{s,g'} \phi \rangle}
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Parameters
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----------
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@ -4835,30 +4827,13 @@ class ScatterProbabilityMatrix(MatrixMGXS):
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num_azimuthal : Integral, optional
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Number of equi-width azimuthal angle bins for angle discretization;
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defaults to one bin
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nu : bool
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If True, the cross section data will include neutron multiplication;
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defaults to False
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Attributes
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----------
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scatter_format : {'legendre', or 'histogram'}
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Representation of the angular scattering distribution (default is
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'legendre')
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legendre_order : int
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The highest Legendre moment in the scattering matrix; this is used if
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:attr:`ScatterProbabilityMatrix.scatter_format` is 'legendre'.
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(default is 0)
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histogram_bins : int
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The number of equally-spaced bins for the histogram representation of
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the angular scattering distribution; this is used if
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:attr:`ScatterProbabilityMatrix.scatter_format` is 'histogram'.
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(default is 16)
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name : str, optional
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Name of the multi-group cross section
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rxn_type : str
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Reaction type (e.g., 'total', 'nu-fission', etc.)
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nu : bool
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If True, the cross section data will include neutron multiplication
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by_nuclide : bool
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If true, computes cross sections for each nuclide in domain
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domain : Material or Cell or Universe or Mesh
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@ -4920,65 +4895,18 @@ class ScatterProbabilityMatrix(MatrixMGXS):
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"""
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def __init__(self, domain=None, domain_type=None, groups=None,
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by_nuclide=False, name='', num_polar=1,
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num_azimuthal=1, nu=False):
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by_nuclide=False, name='', num_polar=1, num_azimuthal=1):
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super(ScatterProbabilityMatrix, self).__init__(
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domain, domain_type, groups, by_nuclide,
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name, num_polar, num_azimuthal)
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self._scatter_format = 'legendre'
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self._legendre_order = 0
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self._histogram_bins = 16
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self._rxn_type = 'scatter'
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self._estimator = 'analog'
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self._valid_estimators = ['analog']
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self.nu = nu
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def __deepcopy__(self, memo):
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clone = super(ScatterProbabilityMatrix, self).__deepcopy__(memo)
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clone._scatter_format = self.scatter_format
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clone._legendre_order = self.legendre_order
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clone._histogram_bins = self.histogram_bins
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clone._nu = self.nu
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return clone
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@property
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def _dont_squeeze(self):
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"""Create a tuple of axes which should not be removed during the get_xs
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process
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"""
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if self.num_polar > 1 or self.num_azimuthal > 1:
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if self.scatter_format == 'histogram':
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return (0, 1, 3, 4, 5)
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else:
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return (0, 1, 3, 4)
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else:
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if self.scatter_format == 'histogram':
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return (1, 2, 3)
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else:
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return (1, 2)
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@property
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def scatter_format(self):
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return self._scatter_format
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@property
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def legendre_order(self):
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return self._legendre_order
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@property
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def histogram_bins(self):
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return self._histogram_bins
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@property
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def nu(self):
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return self._nu
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@property
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def scores(self):
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if self.scatter_format == 'legendre':
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return ['{}-P{}'.format(self.rxn_type, self.legendre_order)]
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elif self.scatter_format == 'histogram':
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return [self.rxn_type]
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return [self.rxn_type]
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@property
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def filters(self):
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@ -4991,17 +4919,9 @@ class ScatterProbabilityMatrix(MatrixMGXS):
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@property
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def rxn_rate_tally(self):
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if self._rxn_rate_tally is None:
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if self.scatter_format == 'legendre':
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tally_key = '{}-P{}'.format(self.rxn_type,
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self.legendre_order)
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self._rxn_rate_tally = self.tallies[tally_key]
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elif self.scatter_format == 'histogram':
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self._rxn_rate_tally = self.tallies[self.rxn_type]
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self._rxn_rate_tally = self.tallies[self.rxn_type]
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self._rxn_rate_tally.sparse = self.sparse
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return self._rxn_rate_tally
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@property
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@ -5010,8 +4930,7 @@ class ScatterProbabilityMatrix(MatrixMGXS):
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if self._xs_tally is None:
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energyout_bins = [self.energy_groups.get_group_bounds(i)
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for i in range(self.num_groups, 0, -1)]
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norm = self.rxn_rate_tally.get_slice(
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scores=['{}-0'.format(self.rxn_type)])
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norm = self.rxn_rate_tally.get_slice(scores=[self.rxn_type])
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norm = norm.summation(
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filter_type=openmc.EnergyoutFilter, filter_bins=energyout_bins)
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@ -5019,595 +4938,11 @@ class ScatterProbabilityMatrix(MatrixMGXS):
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norm._filters = norm._filters[:2]
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# Compute the group-to-group probabilities
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tally_key = '{}-P{}'.format(self.rxn_type, self.legendre_order)
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self._xs_tally = self.tallies[tally_key] / norm
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self._xs_tally = self.tallies[self.rxn_type] / norm
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super(ScatterProbabilityMatrix, self)._compute_xs()
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return self._xs_tally
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@scatter_format.setter
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def scatter_format(self, scatter_format):
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cv.check_value('scatter_format', scatter_format, MU_TREATMENTS)
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self._scatter_format = scatter_format
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@legendre_order.setter
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def legendre_order(self, legendre_order):
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cv.check_type('legendre_order', legendre_order, Integral)
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cv.check_greater_than('legendre_order', legendre_order, 0,
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equality=True)
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cv.check_less_than('legendre_order', legendre_order, _MAX_LEGENDRE,
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equality=True)
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if self.scatter_format == 'histogram':
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msg = 'The legendre order will be ignored since the ' \
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'scatter format is set to histogram'
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warnings.warn(msg)
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self._legendre_order = legendre_order
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@histogram_bins.setter
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def histogram_bins(self, histogram_bins):
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cv.check_type('histogram_bins', histogram_bins, Integral)
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cv.check_greater_than('histogram_bins', histogram_bins, 0)
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self._histogram_bins = histogram_bins
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@nu.setter
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def nu(self, nu):
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cv.check_type('nu', nu, bool)
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self._nu = nu
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if not nu:
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self._rxn_type = 'scatter'
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self._hdf5_key = 'scatter probability matrix'
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else:
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self._rxn_type = 'nu-scatter'
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self._hdf5_key = 'nu-scatter probability matrix'
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def load_from_statepoint(self, statepoint):
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"""Extracts tallies in an OpenMC StatePoint with the data needed to
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compute multi-group cross sections.
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This method is needed to compute cross section data from tallies
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in an OpenMC StatePoint object.
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.. note:: The statepoint must be linked with an OpenMC Summary object.
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Parameters
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----------
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statepoint : openmc.StatePoint
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An OpenMC StatePoint object with tally data
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Raises
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------
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ValueError
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When this method is called with a statepoint that has not been
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linked with a summary object.
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"""
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# Clear any tallies previously loaded from a statepoint
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if self.loaded_sp:
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self._tallies = None
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self._xs_tally = None
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self._rxn_rate_tally = None
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self._loaded_sp = False
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if self.scatter_format == 'legendre':
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# Expand scores to match the format in the statepoint
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# e.g., "scatter-P2" -> "scatter-0", "scatter-1", "scatter-2"
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tally_key = '{}-P{}'.format(self.rxn_type, self.legendre_order)
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self.tallies[tally_key].scores = \
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[self.rxn_type + '-{}'.format(i)
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for i in range(self.legendre_order + 1)]
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elif self.scatter_format == 'histogram':
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self.tallies[self.rxn_type].scores = [self.rxn_type]
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super(ScatterProbabilityMatrix, self).load_from_statepoint(statepoint)
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def get_slice(self, nuclides=[], in_groups=[], out_groups=[],
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legendre_order='same'):
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"""Build a sliced ScatterProbabilityMatrix for the specified nuclides
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and energy groups.
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This method constructs a new MGXS to encapsulate a subset of the data
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represented by this MGXS. The subset of data to include in the tally
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slice is determined by the nuclides and energy groups specified in
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the input parameters.
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Parameters
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----------
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nuclides : list of str
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A list of nuclide name strings
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(e.g., ['U235', 'U238']; default is [])
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in_groups : list of int
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A list of incoming energy group indices starting at 1 for the high
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energies (e.g., [1, 2, 3]; default is [])
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out_groups : list of int
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A list of outgoing energy group indices starting at 1 for the high
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energies (e.g., [1, 2, 3]; default is [])
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legendre_order : int or 'same'
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The highest Legendre moment in the sliced MGXS. If order is 'same'
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then the sliced MGXS will have the same Legendre moments as the
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original MGXS (default). If order is an integer less than the
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original MGXS' order, then only those Legendre moments up to that
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order will be included in the sliced MGXS.
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Returns
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-------
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openmc.mgxs.MatrixMGXS
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A new MatrixMGXS which encapsulates the subset of data requested
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for the nuclide(s) and/or energy group(s) requested in the
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parameters.
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"""
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# Call super class method and null out derived tallies
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slice_xs = \
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super(ScatterProbabilityMatrix, self).get_slice(nuclides, in_groups)
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slice_xs._rxn_rate_tally = None
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slice_xs._xs_tally = None
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# Slice the Legendre order if needed
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if legendre_order != 'same' and self.scatter_format == 'legendre':
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cv.check_type('legendre_order', legendre_order, Integral)
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cv.check_less_than('legendre_order', legendre_order,
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self.legendre_order, equality=True)
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slice_xs.legendre_order = legendre_order
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# Slice the scattering tally
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tally_key = '{}-P{}'.format(self.rxn_type, self.legendre_order)
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expand_scores = \
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[self.rxn_type + '-{}'.format(i)
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for i in range(self.legendre_order + 1)]
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slice_xs.tallies[tally_key] = \
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slice_xs.tallies[tally_key].get_slice(scores=expand_scores)
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# Slice outgoing energy groups if needed
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if len(out_groups) != 0:
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filter_bins = []
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for group in out_groups:
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group_bounds = self.energy_groups.get_group_bounds(group)
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filter_bins.append(group_bounds)
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filter_bins = [tuple(filter_bins)]
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# Slice each of the tallies across energyout groups
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for tally_type, tally in slice_xs.tallies.items():
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if tally.contains_filter(openmc.EnergyoutFilter):
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tally_slice = tally.get_slice(
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filters=[openmc.EnergyoutFilter], filter_bins=filter_bins)
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slice_xs.tallies[tally_type] = tally_slice
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slice_xs.sparse = self.sparse
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return slice_xs
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def get_xs(self, in_groups='all', out_groups='all',
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subdomains='all', nuclides='all', moment='all',
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xs_type='macro', order_groups='increasing',
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row_column='inout', value='mean', squeeze=True):
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r"""Returns an array of multi-group cross sections.
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This method constructs a 5D NumPy array for the requested
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multi-group cross section data for one or more subdomains
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(1st dimension), energy groups in (2nd dimension), energy groups out
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(3rd dimension), nuclides (4th dimension), and moments/histograms
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(5th dimension).
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Parameters
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----------
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in_groups : Iterable of Integral or 'all'
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Incoming energy groups of interest. Defaults to 'all'.
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out_groups : Iterable of Integral or 'all'
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Outgoing energy groups of interest. Defaults to 'all'.
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subdomains : Iterable of Integral or 'all'
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Subdomain IDs of interest. Defaults to 'all'.
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nuclides : Iterable of str or 'all' or 'sum'
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A list of nuclide name strings (e.g., ['U235', 'U238']). The
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special string 'all' will return the cross sections for all nuclides
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in the spatial domain. The special string 'sum' will return the
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cross section summed over all nuclides. Defaults to 'all'.
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moment : int or 'all'
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The scattering matrix moment to return. All moments will be
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returned if the moment is 'all' (default); otherwise, a specific
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moment will be returned.
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xs_type: {'macro', 'micro'}
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Return the macro or micro cross section in units of cm^-1 or barns.
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Defaults to 'macro'.
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order_groups: {'increasing', 'decreasing'}
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Return the cross section indexed according to increasing or
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decreasing energy groups (decreasing or increasing energies).
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Defaults to 'increasing'.
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row_column: {'inout', 'outin'}
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Return the cross section indexed first by incoming group and
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second by outgoing group ('inout'), or vice versa ('outin').
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Defaults to 'inout'.
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value : {'mean', 'std_dev', 'rel_err'}
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A string for the type of value to return. Defaults to 'mean'.
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squeeze : bool
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A boolean representing whether to eliminate the extra dimensions
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of the multi-dimensional array to be returned. Defaults to True.
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Returns
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-------
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numpy.ndarray
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A NumPy array of the multi-group cross section indexed in the order
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each group and subdomain is listed in the parameters.
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Raises
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------
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ValueError
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When this method is called before the multi-group cross section is
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computed from tally data.
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"""
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cv.check_value('value', value, ['mean', 'std_dev', 'rel_err'])
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cv.check_value('xs_type', xs_type, ['macro', 'micro'])
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# FIXME: Unable to get microscopic xs for mesh domain because the mesh
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# cells do not know the nuclide densities in each mesh cell.
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if self.domain_type == 'mesh' and xs_type == 'micro':
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msg = 'Unable to get micro xs for mesh domain since the mesh ' \
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'cells do not know the nuclide densities in each mesh cell.'
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raise ValueError(msg)
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filters = []
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filter_bins = []
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# Construct a collection of the domain filter bins
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if not isinstance(subdomains, string_types):
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cv.check_iterable_type('subdomains', subdomains, Integral, max_depth=3)
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filters.append(_DOMAIN_TO_FILTER[self.domain_type])
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subdomain_bins = []
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for subdomain in subdomains:
|
||||
subdomain_bins.append(subdomain)
|
||||
filter_bins.append(tuple(subdomain_bins))
|
||||
|
||||
# Construct list of energy group bounds tuples for all requested groups
|
||||
if not isinstance(in_groups, string_types):
|
||||
cv.check_iterable_type('groups', in_groups, Integral)
|
||||
filters.append(openmc.EnergyFilter)
|
||||
energy_bins = []
|
||||
for group in in_groups:
|
||||
energy_bins.append(
|
||||
(self.energy_groups.get_group_bounds(group),))
|
||||
filter_bins.append(tuple(energy_bins))
|
||||
|
||||
# Construct list of energy group bounds tuples for all requested groups
|
||||
if not isinstance(out_groups, string_types):
|
||||
cv.check_iterable_type('groups', out_groups, Integral)
|
||||
for group in out_groups:
|
||||
filters.append(openmc.EnergyoutFilter)
|
||||
filter_bins.append((self.energy_groups.get_group_bounds(group),))
|
||||
|
||||
# Construct CrossScore for requested scattering moment
|
||||
if moment != 'all' and self.scatter_format == 'legendre':
|
||||
cv.check_type('moment', moment, Integral)
|
||||
cv.check_greater_than('moment', moment, 0, equality=True)
|
||||
cv.check_less_than(
|
||||
'moment', moment, self.legendre_order, equality=True)
|
||||
scores = [self.xs_tally.scores[moment]]
|
||||
else:
|
||||
scores = []
|
||||
|
||||
# Construct a collection of the nuclides to retrieve from the xs tally
|
||||
if self.by_nuclide:
|
||||
if nuclides == 'all' or nuclides == 'sum' or nuclides == ['sum']:
|
||||
query_nuclides = self.get_nuclides()
|
||||
else:
|
||||
query_nuclides = nuclides
|
||||
else:
|
||||
query_nuclides = ['total']
|
||||
|
||||
# Use tally summation if user requested the sum for all nuclides
|
||||
if nuclides == 'sum' or nuclides == ['sum']:
|
||||
xs_tally = self.xs_tally.summation(nuclides=query_nuclides)
|
||||
xs = xs_tally.get_values(scores=scores, filters=filters,
|
||||
filter_bins=filter_bins, value=value)
|
||||
else:
|
||||
xs = self.xs_tally.get_values(scores=scores, filters=filters,
|
||||
filter_bins=filter_bins,
|
||||
nuclides=query_nuclides, value=value)
|
||||
|
||||
# Divide by atom number densities for microscopic cross sections
|
||||
if xs_type == 'micro':
|
||||
if self.by_nuclide:
|
||||
densities = self.get_nuclide_densities(nuclides)
|
||||
else:
|
||||
densities = self.get_nuclide_densities('sum')
|
||||
if value == 'mean' or value == 'std_dev':
|
||||
xs /= densities[np.newaxis, :, np.newaxis]
|
||||
|
||||
# Convert and nans to zero
|
||||
xs = np.nan_to_num(xs)
|
||||
|
||||
if in_groups == 'all':
|
||||
num_in_groups = self.num_groups
|
||||
else:
|
||||
num_in_groups = len(in_groups)
|
||||
|
||||
if out_groups == 'all':
|
||||
num_out_groups = self.num_groups
|
||||
else:
|
||||
num_out_groups = len(out_groups)
|
||||
|
||||
if self.scatter_format == 'histogram':
|
||||
num_mu_bins = self.histogram_bins
|
||||
else:
|
||||
num_mu_bins = 1
|
||||
|
||||
# Reshape tally data array with separate axes for domain and energy
|
||||
# Accomodate the polar and azimuthal bins if needed
|
||||
num_subdomains = int(xs.shape[0] / (num_mu_bins * num_in_groups *
|
||||
num_out_groups * self.num_polar *
|
||||
self.num_azimuthal))
|
||||
if self.num_polar > 1 or self.num_azimuthal > 1:
|
||||
if self.scatter_format == 'histogram':
|
||||
new_shape = (self.num_polar, self.num_azimuthal,
|
||||
num_subdomains, num_in_groups, num_out_groups,
|
||||
num_mu_bins)
|
||||
else:
|
||||
new_shape = (self.num_polar, self.num_azimuthal,
|
||||
num_subdomains, num_in_groups, num_out_groups)
|
||||
new_shape += xs.shape[1:]
|
||||
xs = np.reshape(xs, new_shape)
|
||||
|
||||
# Transpose the scattering matrix if requested by user
|
||||
if row_column == 'outin':
|
||||
xs = np.swapaxes(xs, 3, 4)
|
||||
|
||||
# Reverse data if user requested increasing energy groups since
|
||||
# tally data is stored in order of increasing energies
|
||||
if order_groups == 'increasing':
|
||||
xs = xs[:, :, :, ::-1, ::-1, ...]
|
||||
else:
|
||||
if self.scatter_format == 'histogram':
|
||||
new_shape = (num_subdomains, num_in_groups, num_out_groups,
|
||||
num_mu_bins)
|
||||
else:
|
||||
new_shape = (num_subdomains, num_in_groups, num_out_groups)
|
||||
new_shape += xs.shape[1:]
|
||||
xs = np.reshape(xs, new_shape)
|
||||
|
||||
# Transpose the scattering matrix if requested by user
|
||||
if row_column == 'outin':
|
||||
xs = np.swapaxes(xs, 1, 2)
|
||||
|
||||
# Reverse data if user requested increasing energy groups since
|
||||
# tally data is stored in order of increasing energies
|
||||
if order_groups == 'increasing':
|
||||
xs = xs[:, ::-1, ::-1, ...]
|
||||
|
||||
if squeeze:
|
||||
# We want to squeeze out everything but the angles, in_groups,
|
||||
# out_groups, and, if needed, num_mu_bins dimension. These must
|
||||
# not be squeezed so 1-group, 1-angle problems have the correct
|
||||
# shape.
|
||||
xs = self._squeeze_xs(xs)
|
||||
return xs
|
||||
|
||||
def get_pandas_dataframe(self, groups='all', nuclides='all', moment='all',
|
||||
xs_type='macro', distribcell_paths=True):
|
||||
"""Build a Pandas DataFrame for the MGXS data.
|
||||
|
||||
This method leverages :meth:`openmc.Tally.get_pandas_dataframe`, but
|
||||
renames the columns with terminology appropriate for cross section data.
|
||||
|
||||
Parameters
|
||||
----------
|
||||
groups : Iterable of Integral or 'all'
|
||||
Energy groups of interest. Defaults to 'all'.
|
||||
nuclides : Iterable of str or 'all' or 'sum'
|
||||
The nuclides of the cross-sections to include in the dataframe. This
|
||||
may be a list of nuclide name strings (e.g., ['U235', 'U238']).
|
||||
The special string 'all' will include the cross sections for all
|
||||
nuclides in the spatial domain. The special string 'sum' will
|
||||
include the cross sections summed over all nuclides. Defaults
|
||||
to 'all'.
|
||||
moment : int or 'all'
|
||||
The scattering matrix moment to return. All moments will be
|
||||
returned if the moment is 'all' (default); otherwise, a specific
|
||||
moment will be returned.
|
||||
xs_type: {'macro', 'micro'}
|
||||
Return macro or micro cross section in units of cm^-1 or barns.
|
||||
Defaults to 'macro'.
|
||||
distribcell_paths : bool, optional
|
||||
Construct columns for distribcell tally filters (default is True).
|
||||
The geometric information in the Summary object is embedded into a
|
||||
Multi-index column with a geometric "path" to each distribcell
|
||||
instance.
|
||||
|
||||
Returns
|
||||
-------
|
||||
pandas.DataFrame
|
||||
A Pandas DataFrame for the cross section data.
|
||||
|
||||
Raises
|
||||
------
|
||||
ValueError
|
||||
When this method is called before the multi-group cross section is
|
||||
computed from tally data.
|
||||
|
||||
"""
|
||||
|
||||
df = super(ScatterProbabilityMatrix, self).get_pandas_dataframe(
|
||||
groups, nuclides, xs_type, distribcell_paths)
|
||||
|
||||
if self.scatter_format == 'legendre':
|
||||
# Add a moment column to dataframe
|
||||
if self.legendre_order > 0:
|
||||
# Insert a column corresponding to the Legendre moments
|
||||
moments = ['P{}'.format(i)
|
||||
for i in range(self.legendre_order + 1)]
|
||||
moments = np.tile(moments, int(df.shape[0] / len(moments)))
|
||||
df['moment'] = moments
|
||||
|
||||
# Place the moment column before the mean column
|
||||
columns = df.columns.tolist()
|
||||
mean_index \
|
||||
= [i for i, s in enumerate(columns) if 'mean' in s][0]
|
||||
if self.domain_type == 'mesh':
|
||||
df = df[columns[:mean_index] + [('moment', '')] +
|
||||
columns[mean_index:-1]]
|
||||
else:
|
||||
df = df[columns[:mean_index] + ['moment'] +
|
||||
columns[mean_index:-1]]
|
||||
|
||||
# Select rows corresponding to requested scattering moment
|
||||
if moment != 'all':
|
||||
cv.check_type('moment', moment, Integral)
|
||||
cv.check_greater_than('moment', moment, 0, equality=True)
|
||||
cv.check_less_than(
|
||||
'moment', moment, self.legendre_order, equality=True)
|
||||
df = df[df['moment'] == 'P{}'.format(moment)]
|
||||
|
||||
return df
|
||||
|
||||
def print_xs(self, subdomains='all', nuclides='all',
|
||||
xs_type='macro', moment=0):
|
||||
"""Prints a string representation for the multi-group cross section.
|
||||
|
||||
Parameters
|
||||
----------
|
||||
subdomains : Iterable of Integral or 'all'
|
||||
The subdomain IDs of the cross sections to include in the report.
|
||||
Defaults to 'all'.
|
||||
nuclides : Iterable of str or 'all' or 'sum'
|
||||
The nuclides of the cross-sections to include in the report. This
|
||||
may be a list of nuclide name strings (e.g., ['U235', 'U238']).
|
||||
The special string 'all' will report the cross sections for all
|
||||
nuclides in the spatial domain. The special string 'sum' will report
|
||||
the cross sections summed over all nuclides. Defaults to 'all'.
|
||||
xs_type: {'macro', 'micro'}
|
||||
Return the macro or micro cross section in units of cm^-1 or barns.
|
||||
Defaults to 'macro'.
|
||||
moment : int
|
||||
The scattering moment to print (default is 0)
|
||||
|
||||
"""
|
||||
|
||||
# Construct a collection of the subdomains to report
|
||||
if not isinstance(subdomains, string_types):
|
||||
cv.check_iterable_type('subdomains', subdomains, Integral)
|
||||
elif self.domain_type == 'distribcell':
|
||||
subdomains = np.arange(self.num_subdomains, dtype=np.int)
|
||||
elif self.domain_type == 'mesh':
|
||||
xyz = [range(1, x + 1) for x in self.domain.dimension]
|
||||
subdomains = list(itertools.product(*xyz))
|
||||
else:
|
||||
subdomains = [self.domain.id]
|
||||
|
||||
# Construct a collection of the nuclides to report
|
||||
if self.by_nuclide:
|
||||
if nuclides == 'all':
|
||||
nuclides = self.get_nuclides()
|
||||
if nuclides == 'sum':
|
||||
nuclides = ['sum']
|
||||
else:
|
||||
cv.check_iterable_type('nuclides', nuclides, string_types)
|
||||
else:
|
||||
nuclides = ['sum']
|
||||
|
||||
cv.check_value('xs_type', xs_type, ['macro', 'micro'])
|
||||
|
||||
if self.scatter_format == 'legendre':
|
||||
rxn_type = '{0} (P{1})'.format(self.rxn_type, moment)
|
||||
else:
|
||||
rxn_type = self.rxn_type
|
||||
|
||||
# Build header for string with type and domain info
|
||||
string = 'Multi-Group XS\n'
|
||||
string += '{0: <16}=\t{1}\n'.format('\tReaction Type', rxn_type)
|
||||
string += '{0: <16}=\t{1}\n'.format('\tDomain Type', self.domain_type)
|
||||
string += '{0: <16}=\t{1}\n'.format('\tDomain ID', self.domain.id)
|
||||
|
||||
# Generate the header for an individual XS
|
||||
xs_header = '\tCross Sections [{0}]:'.format(self.get_units(xs_type))
|
||||
|
||||
# If cross section data has not been computed, only print string header
|
||||
if self.tallies is None:
|
||||
print(string)
|
||||
return
|
||||
|
||||
string += '{0: <16}\n'.format('\tEnergy Groups:')
|
||||
template = '{0: <12}Group {1} [{2: <10} - {3: <10}eV]\n'
|
||||
|
||||
# Loop over energy groups ranges
|
||||
for group in range(1, self.num_groups + 1):
|
||||
bounds = self.energy_groups.get_group_bounds(group)
|
||||
string += template.format('', group, bounds[0], bounds[1])
|
||||
|
||||
# Set polar and azimuthal bins if necessary
|
||||
if self.num_polar > 1 or self.num_azimuthal > 1:
|
||||
pol_bins = np.linspace(0., np.pi, num=self.num_polar + 1,
|
||||
endpoint=True)
|
||||
azi_bins = np.linspace(-np.pi, np.pi, num=self.num_azimuthal + 1,
|
||||
endpoint=True)
|
||||
|
||||
# Loop over all subdomains
|
||||
for subdomain in subdomains:
|
||||
|
||||
if self.domain_type == 'distribcell' or self.domain_type == 'mesh':
|
||||
string += '{0: <16}=\t{1}\n'.format('\tSubdomain', subdomain)
|
||||
|
||||
# Loop over all Nuclides
|
||||
for nuclide in nuclides:
|
||||
|
||||
# Build header for nuclide type
|
||||
if xs_type != 'sum':
|
||||
string += '{0: <16}=\t{1}\n'.format('\tNuclide', nuclide)
|
||||
|
||||
# Build header for cross section type
|
||||
string += '{0: <16}\n'.format(xs_header)
|
||||
template = '{0: <12}Group {1} -> Group {2}:\t\t'
|
||||
|
||||
average_xs = self.get_xs(nuclides=[nuclide],
|
||||
subdomains=[subdomain],
|
||||
xs_type=xs_type, value='mean',
|
||||
moment=moment)
|
||||
rel_err_xs = self.get_xs(nuclides=[nuclide],
|
||||
subdomains=[subdomain],
|
||||
xs_type=xs_type, value='rel_err',
|
||||
moment=moment)
|
||||
rel_err_xs = rel_err_xs * 100.
|
||||
|
||||
if self.num_polar > 1 or self.num_azimuthal > 1:
|
||||
# Loop over polar, azi, and in/out energy group ranges
|
||||
for pol in range(len(pol_bins) - 1):
|
||||
pol_low, pol_high = pol_bins[pol: pol + 2]
|
||||
for azi in range(len(azi_bins) - 1):
|
||||
azi_low, azi_high = azi_bins[azi: azi + 2]
|
||||
string += '\t\tPolar Angle: [{0:5f} - {1:5f}]'.format(
|
||||
pol_low, pol_high) + \
|
||||
'\tAzimuthal Angle: [{0:5f} - {1:5f}]'.format(
|
||||
azi_low, azi_high) + '\n'
|
||||
for in_group in range(1, self.num_groups + 1):
|
||||
for out_group in range(1, self.num_groups + 1):
|
||||
string += '\t' + template.format('',
|
||||
in_group,
|
||||
out_group)
|
||||
string += '{0:.2e} +/- {1:.2e}%'.format(
|
||||
average_xs[pol, azi, in_group - 1,
|
||||
out_group - 1],
|
||||
rel_err_xs[pol, azi, in_group - 1,
|
||||
out_group - 1])
|
||||
string += '\n'
|
||||
string += '\n'
|
||||
string += '\n'
|
||||
else:
|
||||
# Loop over incoming/outgoing energy groups ranges
|
||||
for in_group in range(1, self.num_groups + 1):
|
||||
for out_group in range(1, self.num_groups + 1):
|
||||
string += template.format('', in_group, out_group)
|
||||
string += '{0:.2e} +/- {1:.2e}%'.format(
|
||||
average_xs[in_group - 1, out_group - 1],
|
||||
rel_err_xs[in_group - 1, out_group - 1])
|
||||
string += '\n'
|
||||
string += '\n'
|
||||
string += '\n'
|
||||
string += '\n'
|
||||
string += '\n'
|
||||
|
||||
print(string)
|
||||
|
||||
|
||||
class NuFissionMatrixXS(MatrixMGXS):
|
||||
r"""A fission production matrix multi-group cross section.
|
||||
|
|
|
|||
File diff suppressed because it is too large
Load diff
|
|
@ -33,8 +33,6 @@
|
|||
material group in group out nuclide mean std. dev.
|
||||
0 10000 1 1 total 0.085835 0.005592
|
||||
material group in group out nuclide mean std. dev.
|
||||
0 10000 1 1 total 1.0 0.066111
|
||||
material group in group out nuclide mean std. dev.
|
||||
0 10000 1 1 total 1.0 0.066111
|
||||
material group in group out nuclide moment mean std. dev.
|
||||
0 10000 1 1 total P0 0.388721 0.031279
|
||||
|
|
@ -126,8 +124,6 @@
|
|||
material group in group out nuclide mean std. dev.
|
||||
0 10001 1 1 total 0.0 0.0
|
||||
material group in group out nuclide mean std. dev.
|
||||
0 10001 1 1 total 1.0 0.095039
|
||||
material group in group out nuclide mean std. dev.
|
||||
0 10001 1 1 total 1.0 0.095039
|
||||
material group in group out nuclide moment mean std. dev.
|
||||
0 10001 1 1 total P0 0.309384 0.032376
|
||||
|
|
@ -219,8 +215,6 @@
|
|||
material group in group out nuclide mean std. dev.
|
||||
0 10002 1 1 total 0.0 0.0
|
||||
material group in group out nuclide mean std. dev.
|
||||
0 10002 1 1 total 1.0 0.056867
|
||||
material group in group out nuclide mean std. dev.
|
||||
0 10002 1 1 total 1.0 0.056867
|
||||
material group in group out nuclide moment mean std. dev.
|
||||
0 10002 1 1 total P0 0.898938 0.067118
|
||||
|
|
|
|||
|
|
@ -304,32 +304,24 @@
|
|||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>scatter-P0</scores>
|
||||
<scores>scatter</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10032">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>nu-scatter-P0</scores>
|
||||
<estimator>analog</estimator>
|
||||
<scores>flux</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10033">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>flux</scores>
|
||||
<scores>scatter</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10034">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>scatter</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10035">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
|
|
@ -337,21 +329,21 @@
|
|||
<scores>scatter-P3</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10036">
|
||||
<tally id="10035">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>flux</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10037">
|
||||
<tally id="10036">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>scatter</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10038">
|
||||
<tally id="10037">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
|
|
@ -359,7 +351,7 @@
|
|||
<scores>scatter-P3</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10039">
|
||||
<tally id="10038">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
|
|
@ -367,7 +359,7 @@
|
|||
<scores>nu-scatter-0</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10040">
|
||||
<tally id="10039">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
|
|
@ -375,70 +367,70 @@
|
|||
<scores>scatter-0</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10041">
|
||||
<tally id="10040">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>nu-fission</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10041">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>nu-fission</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10042">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>nu-fission</scores>
|
||||
<scores>prompt-nu-fission</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10043">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>prompt-nu-fission</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10044">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>prompt-nu-fission</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10045">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>flux</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10046">
|
||||
<tally id="10045">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>inverse-velocity</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10047">
|
||||
<tally id="10046">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>flux</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10048">
|
||||
<tally id="10047">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>prompt-nu-fission</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10049">
|
||||
<tally id="10048">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>flux</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10050">
|
||||
<tally id="10049">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
|
|
@ -446,22 +438,22 @@
|
|||
<scores>prompt-nu-fission</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10051">
|
||||
<tally id="10050">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>flux</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10051">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>delayed-nu-fission</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10052">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>delayed-nu-fission</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10053">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
|
|
@ -469,7 +461,7 @@
|
|||
<scores>delayed-nu-fission</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10054">
|
||||
<tally id="10053">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
|
|
@ -477,13 +469,21 @@
|
|||
<scores>delayed-nu-fission</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10055">
|
||||
<tally id="10054">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>nu-fission</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10055">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>delayed-nu-fission</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10056">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
|
||||
|
|
@ -493,14 +493,6 @@
|
|||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10057">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>delayed-nu-fission</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10058">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
|
|
@ -508,14 +500,14 @@
|
|||
<scores>decay-rate</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10059">
|
||||
<tally id="10058">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>flux</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10060">
|
||||
<tally id="10059">
|
||||
<filter bins="10000" type="distribcell" />
|
||||
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
|
|
|
|||
|
|
@ -34,8 +34,6 @@
|
|||
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total 0.094516 0.0059
|
||||
sum(distribcell) group in group out nuclide mean std. dev.
|
||||
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total 1.0 0.037213
|
||||
sum(distribcell) group in group out nuclide mean std. dev.
|
||||
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total 1.0 0.037208
|
||||
sum(distribcell) group in group out nuclide moment mean std. dev.
|
||||
0 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P0 0.390797 0.016955
|
||||
1 ((0, 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13... 1 1 total P1 0.047641 0.005091
|
||||
|
|
|
|||
File diff suppressed because it is too large
Load diff
|
|
@ -541,32 +541,24 @@
|
|||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>scatter-P0</scores>
|
||||
<scores>scatter</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10032">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>nu-scatter-P0</scores>
|
||||
<estimator>analog</estimator>
|
||||
<scores>flux</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10033">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>flux</scores>
|
||||
<scores>scatter</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10034">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>scatter</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10035">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
|
|
@ -574,21 +566,21 @@
|
|||
<scores>scatter-P3</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10036">
|
||||
<tally id="10035">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>flux</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10037">
|
||||
<tally id="10036">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>scatter</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10038">
|
||||
<tally id="10037">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
|
|
@ -596,7 +588,7 @@
|
|||
<scores>scatter-P3</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10039">
|
||||
<tally id="10038">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
|
|
@ -604,7 +596,7 @@
|
|||
<scores>nu-scatter-0</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10040">
|
||||
<tally id="10039">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
|
|
@ -612,70 +604,70 @@
|
|||
<scores>scatter-0</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10041">
|
||||
<tally id="10040">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>nu-fission</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10041">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>nu-fission</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10042">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>nu-fission</scores>
|
||||
<scores>prompt-nu-fission</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10043">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>prompt-nu-fission</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10044">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>prompt-nu-fission</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10045">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>flux</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10046">
|
||||
<tally id="10045">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>inverse-velocity</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10047">
|
||||
<tally id="10046">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>flux</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10048">
|
||||
<tally id="10047">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>prompt-nu-fission</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10049">
|
||||
<tally id="10048">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>flux</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10050">
|
||||
<tally id="10049">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
|
|
@ -683,22 +675,22 @@
|
|||
<scores>prompt-nu-fission</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10051">
|
||||
<tally id="10050">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>flux</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10051">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>delayed-nu-fission</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10052">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>delayed-nu-fission</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10053">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
|
|
@ -706,7 +698,7 @@
|
|||
<scores>delayed-nu-fission</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10054">
|
||||
<tally id="10053">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
|
||||
<filter bins="0.0 20000000.0" type="energyout" />
|
||||
|
|
@ -714,13 +706,21 @@
|
|||
<scores>delayed-nu-fission</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10055">
|
||||
<tally id="10054">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>nu-fission</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10055">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>delayed-nu-fission</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10056">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
|
||||
|
|
@ -730,14 +730,6 @@
|
|||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10057">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>delayed-nu-fission</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10058">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
|
|
@ -745,14 +737,14 @@
|
|||
<scores>decay-rate</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="10059">
|
||||
<tally id="10058">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
<nuclides>total</nuclides>
|
||||
<scores>flux</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
<tally id="10060">
|
||||
<tally id="10059">
|
||||
<filter bins="1" type="mesh" />
|
||||
<filter bins="1 2 3 4 5 6" type="delayedgroup" />
|
||||
<filter bins="0.0 20000000.0" type="energy" />
|
||||
|
|
|
|||
|
|
@ -111,12 +111,6 @@
|
|||
0 1 1 1 1 1 total 1.0 0.153265
|
||||
1 1 2 1 1 1 total 1.0 0.454973
|
||||
2 2 1 1 1 1 total 1.0 0.146747
|
||||
3 2 2 1 1 1 total 1.0 0.141824
|
||||
mesh 1 group in group out nuclide mean std. dev.
|
||||
x y z
|
||||
0 1 1 1 1 1 total 1.0 0.153265
|
||||
1 1 2 1 1 1 total 1.0 0.454973
|
||||
2 2 1 1 1 1 total 1.0 0.146747
|
||||
3 2 2 1 1 1 total 1.0 0.141824
|
||||
mesh 1 group in group out nuclide moment mean std. dev.
|
||||
x y z
|
||||
|
|
|
|||
File diff suppressed because it is too large
Load diff
|
|
@ -76,11 +76,6 @@
|
|||
3 10000 1 1 total 0.997433 0.078224
|
||||
2 10000 1 2 total 0.002567 0.001256
|
||||
1 10000 2 1 total 0.002242 0.002243
|
||||
0 10000 2 2 total 0.997758 0.041053
|
||||
material group in group out nuclide mean std. dev.
|
||||
3 10000 1 1 total 0.997433 0.078224
|
||||
2 10000 1 2 total 0.002567 0.001256
|
||||
1 10000 2 1 total 0.002242 0.002243
|
||||
0 10000 2 2 total 0.997758 0.041053
|
||||
material group in group out nuclide moment mean std. dev.
|
||||
12 10000 1 1 total P0 0.386423 0.036629
|
||||
|
|
@ -288,11 +283,6 @@
|
|||
3 10001 1 1 total 1.0 0.108779
|
||||
2 10001 1 2 total 0.0 0.000000
|
||||
1 10001 2 1 total 0.0 0.000000
|
||||
0 10001 2 2 total 1.0 0.142427
|
||||
material group in group out nuclide mean std. dev.
|
||||
3 10001 1 1 total 1.0 0.108779
|
||||
2 10001 1 2 total 0.0 0.000000
|
||||
1 10001 2 1 total 0.0 0.000000
|
||||
0 10001 2 2 total 1.0 0.142427
|
||||
material group in group out nuclide moment mean std. dev.
|
||||
12 10001 1 1 total P0 0.312163 0.037253
|
||||
|
|
@ -500,11 +490,6 @@
|
|||
3 10002 1 1 total 0.953271 0.036018
|
||||
2 10002 1 2 total 0.046729 0.002547
|
||||
1 10002 2 1 total 0.000218 0.000219
|
||||
0 10002 2 2 total 0.999782 0.135885
|
||||
material group in group out nuclide mean std. dev.
|
||||
3 10002 1 1 total 0.953271 0.036018
|
||||
2 10002 1 2 total 0.046729 0.002547
|
||||
1 10002 2 1 total 0.000218 0.000219
|
||||
0 10002 2 2 total 0.999782 0.135885
|
||||
material group in group out nuclide moment mean std. dev.
|
||||
12 10002 1 1 total P0 0.632859 0.038142
|
||||
|
|
|
|||
File diff suppressed because it is too large
Load diff
|
|
@ -1 +1 @@
|
|||
bd5c4c64a77f8df58fc6753bc5d43de9d7b80c47097cfbafa37f52f10f661997caec72acdfa31dd1af246314447bd5781e950181814cbc77435ebbf029e9f6d7
|
||||
5df54054ab37cd69b7096b9f785be57a83a8c3872d3e065ff605aa6de5688640a5551f99313a3e60a9ab8f902c1d4927630e1838db26a2a09d41e29338634b43
|
||||
Loading…
Add table
Add a link
Reference in a new issue