openmc.deplete.ResultsList¶
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class
openmc.deplete.
ResultsList
[source]¶ A list of openmc.deplete.Results objects
It is recommended to use
from_hdf5()
over direct creation.-
classmethod
from_hdf5
(filename)[source]¶ Load in depletion results from a previous file
Parameters: filename (str) – Path to depletion result file Returns: new – New instance of depletion results Return type: ResultsList
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get_atoms
(mat, nuc)[source]¶ Get number of nuclides over time from a single material
Note
Initial values for some isotopes that do not appear in initial concentrations may be non-zero, depending on the value of
openmc.deplete.Operator
dilute_initial
. Theopenmc.deplete.Operator
adds isotopes according to this setting, which can be set to zero.Parameters: Returns: - time (numpy.ndarray) – Array of times in [s]
- concentration (numpy.ndarray) – Total number of atoms for specified nuclide
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get_depletion_time
()[source]¶ Return an array of the average time to deplete a material
Note
Will have one fewer row than number of other methods, like
get_eigenvalues()
, because no depletion is performed at the final transport stageReturns: times – Vector of average time to deplete a single material across all processes and materials. Return type: numpy.ndarray
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get_eigenvalue
()[source]¶ Evaluates the eigenvalue from a results list.
Returns: - time (numpy.ndarray) – Array of times in [s]
- eigenvalue (numpy.ndarray) – k-eigenvalue at each time. Column 0 contains the eigenvalue, while column 1 contains the associated uncertainty
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get_reaction_rate
(mat, nuc, rx)[source]¶ Get reaction rate in a single material/nuclide over time
Note
Initial values for some isotopes that do not appear in initial concentrations may be non-zero, depending on the value of
openmc.deplete.Operator
dilute_initial
Theopenmc.deplete.Operator
adds isotopes according to this setting, which can be set to zero.Parameters: Returns: - time (numpy.ndarray) – Array of times in [s]
- rate (numpy.ndarray) – Array of reaction rates
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classmethod