# openmc.deplete.ResultsList¶

class openmc.deplete.ResultsList[source]

A list of openmc.deplete.Results objects

It is recommended to use from_hdf5() over direct creation.

export_to_materials(burnup_index, nuc_with_data=None) → openmc.material.Materials[source]

Return openmc.Materials object based on results at a given step

New in version 0.12.1.

Parameters: burn_index (int) – Index of burnup step to evaluate. See also: get_step_where for obtaining burnup step indices from other data such as the time. nuc_with_data (Iterable of str, optional) – Nuclides to include in resulting materials. This can be specified if not all nuclides appearing in depletion results have associated neutron cross sections, and as such cannot be used in subsequent transport calculations. If not provided, nuclides from the cross_sections element of materials.xml will be used. If that element is not present, nuclides from OPENMC_CROSS_SECTIONS will be used. mat_file – A modified Materials instance containing depleted material data and original isotopic compositions of non-depletable materials Materials
classmethod from_hdf5(filename)[source]

Load in depletion results from a previous file

Parameters: filename (str) – Path to depletion result file new – New instance of depletion results ResultsList
get_atoms(mat, nuc, nuc_units='atoms', time_units='s')[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. The openmc.deplete.Operator adds isotopes according to this setting, which can be set to zero.

Parameters: mat (str) – Material name to evaluate nuc (str) – Nuclide name to evaluate nuc_units ({"atoms", "atom/b-cm", "atom/cm3"}, optional) – Units for the returned concentration. Default is "atoms" New in version 0.12. time_units ({"s", "min", "h", "d"}, optional) – Units for the returned time array. Default is "s" to return the value in seconds. New in version 0.12. times (numpy.ndarray) – Array of times in units of time_units concentrations (numpy.ndarray) – Concentration of specified nuclide in units of nuc_units
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 stage

Returns: times – Vector of average time to deplete a single material across all processes and materials. numpy.ndarray
get_eigenvalue()[source]

Evaluates the eigenvalue from a results list.

Returns: times (numpy.ndarray) – Array of times in [s] eigenvalues (numpy.ndarray) – k-eigenvalue at each time. Column 0 contains the eigenvalue, while column 1 contains the associated uncertainty
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 The openmc.deplete.Operator adds isotopes according to this setting, which can be set to zero.

Parameters: mat (str) – Material name to evaluate nuc (str) – Nuclide name to evaluate rx (str) – Reaction rate to evaluate times (numpy.ndarray) – Array of times in [s] rates (numpy.ndarray) – Array of reaction rates
get_step_where(time, time_units='d', atol=1e-06, rtol=0.001) → int[source]

Return the index closest to a given point in time

In the event time lies exactly between two points, the lower index will be returned. It is possible that the index will be at most one past the point in time requested, but only according to tolerances requested.

Passing atol=math.inf and rtol=math.inf will return the closest index to the requested point.

New in version 0.12.1.

Parameters: time (float) – Desired point in time time_units ({"s", "d", "min", "h"}, optional) – Units on time. Default: days atol (float, optional) – Absolute tolerance (in time_units) if time is not found. rtol (float, optional) – Relative tolerance if time is not found. int
get_times(time_units='d') → numpy.ndarray[source]

Return the points in time that define the depletion schedule

New in version 0.12.1.

Parameters: time_units ({"s", "d", "h", "min"}, optional) – Return the vector in these units. Default is to convert to days 1-D vector of time points numpy.ndarray