openmc.arithmetic.CrossNuclide¶

class openmc.arithmetic.CrossNuclide(left_nuclide=None, right_nuclide=None, binary_op=None)[source]¶

A special-purpose nuclide used to encapsulate all combinations of two tally’s nuclides as an outer product for tally arithmetic.

Parameters:	left_nuclide (Nuclide or CrossNuclide) – The left nuclide in the outer product right_nuclide (Nuclide or CrossNuclide) – The right nuclide in the outer product binary_op (str) – The tally arithmetic binary operator (e.g., ‘+’, ‘-‘, etc.) used to combine two tally’s nuclides with this CrossNuclide
Variables:	left_nuclide (Nuclide or CrossNuclide) – The left nuclide in the outer product right_nuclide (Nuclide or CrossNuclide) – The right nuclide in the outer product binary_op (str) – The tally arithmetic binary operator (e.g., ‘+’, ‘-‘, etc.) used to combine two tally’s nuclides with this CrossNuclide