openmc.deplete.MicroXS

class openmc.deplete.MicroXS(data: ndarray, nuclides: List[str], reactions: List[str])[source]

Microscopic cross section data for use in transport-independent depletion.

New in version 0.13.1.

Changed in version 0.14.0: Class was heavily refactored and no longer subclasses pandas.DataFrame.

Parameters

  • data (numpy.ndarray of floats) – 3D array containing microscopic cross section values for each nuclide, reaction, and energy group. Cross section values are assumed to be in [b], and indexed by [nuclide, reaction, energy group]

  • nuclides (list of str) – List of nuclide symbols for that have data for at least one reaction.

  • reactions (list of str) – List of reactions. All reactions must match those in openmc.deplete.chain.REACTIONS

classmethod from_csv(csv_file, **kwargs)[source]

Load data from a comma-separated values (csv) file.

Parameters

  • csv_file (str) – Relative path to csv-file containing microscopic cross section data. Cross section values are assumed to be in [b]

  • **kwargs (dict) – Keyword arguments to pass to pandas.read_csv().

Return type

MicroXS

to_csv(*args, **kwargs)[source]

Write data to a comma-separated values (csv) file

Parameters