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
- to_csv(*args, **kwargs)[source]¶
Write data to a comma-separated values (csv) file
- Parameters
*args – Positional arguments passed to
pandas.DataFrame.to_csv()
**kwargs – Keyword arguments passed to
pandas.DataFrame.to_csv()