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156 lines
3.9 KiB
Python
156 lines
3.9 KiB
Python
import numpy as np
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import scipy.sparse as sp
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from openmc.deplete.reaction_rates import ReactionRates
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from openmc.deplete.abc import TransportOperator, OperatorResult
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class DummyOperator(TransportOperator):
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"""This is a dummy operator class with no statistical uncertainty.
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y_1' = sin(y_2) y_1 + cos(y_1) y_2
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y_2' = -cos(y_2) y_1 + sin(y_1) y_2
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y_1(0) = 1
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y_2(0) = 1
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y_1(1.5) ~ 2.3197067076743316
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y_2(1.5) ~ 3.1726475740397628
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"""
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def __init__(self, previous_results=None):
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self.prev_res = previous_results
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def __call__(self, vec, power, print_out=False):
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"""Evaluates F(y)
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Parameters
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----------
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vec : list of numpy.array
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Total atoms to be used in function.
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power : float
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Power in [W]
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print_out : bool, optional, ignored
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Whether or not to print out time.
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Returns
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-------
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openmc.deplete.OperatorResult
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Result of transport operator
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"""
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mats = ["1"]
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nuclides = ["1", "2"]
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reactions = ["1"]
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reaction_rates = ReactionRates(mats, nuclides, reactions)
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reaction_rates[0, 0, 0] = vec[0][0]
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reaction_rates[0, 1, 0] = vec[0][1]
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# Create a fake rates object
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return OperatorResult(0.0, reaction_rates)
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@property
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def chain(self):
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return self
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def form_matrix(self, rates):
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"""Forms the f(y) matrix in y' = f(y)y.
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Nominally a depletion matrix, this is abstracted on the off chance
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that the function f has nothing to do with depletion at all.
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Parameters
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----------
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rates : numpy.ndarray
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Slice of reaction rates for a single material
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Returns
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-------
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scipy.sparse.csr_matrix
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Sparse matrix representing f(y).
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"""
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y_1 = rates[0, 0]
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y_2 = rates[1, 0]
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mat = np.zeros((2, 2))
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a11 = np.sin(y_2)
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a12 = np.cos(y_1)
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a21 = -np.cos(y_2)
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a22 = np.sin(y_1)
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return sp.csr_matrix(np.array([[a11, a12], [a21, a22]]))
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@property
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def volume(self):
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"""
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volume : dict of str float
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Volumes of material
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"""
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return {"1": 0.0}
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@property
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def nuc_list(self):
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"""
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nuc_list : list of str
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A list of all nuclide names. Used for sorting the simulation.
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"""
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return ["1", "2"]
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@property
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def local_mats(self):
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"""
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local_mats : list of str
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A list of all material IDs to be burned. Used for sorting the simulation.
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"""
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return ["1"]
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@property
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def burnable_mats(self):
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"""Maps cell name to index in global geometry."""
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return self.local_mats
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@property
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def reaction_rates(self):
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"""
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reaction_rates : ReactionRates
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Reaction rates from the last operator step.
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"""
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mats = ["1"]
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nuclides = ["1", "2"]
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reactions = ["1"]
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return ReactionRates(mats, nuclides, reactions)
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def initial_condition(self):
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"""Returns initial vector.
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Returns
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-------
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list of numpy.array
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Total density for initial conditions.
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"""
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return [np.array((1.0, 1.0))]
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def get_results_info(self):
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"""Returns volume list, cell lists, and nuc lists.
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Returns
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-------
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volume : dict of str float
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Volumes corresponding to materials in full_burn_dict
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nuc_list : list of str
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A list of all nuclide names. Used for sorting the simulation.
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burn_list : list of int
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A list of all cell IDs to be burned. Used for sorting the simulation.
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full_burn_list : OrderedDict of str to int
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Maps cell name to index in global geometry.
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"""
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return self.volume, self.nuc_list, self.local_mats, self.burnable_mats
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