openmc.deplete.helpers.DirectReactionRateHelper¶
-
class
openmc.deplete.helpers.
DirectReactionRateHelper
(n_nucs, n_react)[source]¶ Class that generates tallies for one-group rates
Parameters: - n_nucs (int) – Number of burnable nuclides tracked by
openmc.deplete.Operator
- n_react (int) – Number of reactions tracked by
openmc.deplete.Operator
Variables: nuclides (list of str) – All nuclides with desired reaction rates.
-
generate_tallies
(materials, scores)[source]¶ Produce one-group reaction rate tally
Uses the
openmc.lib
to generate a tally of relevant reactions across all burnable materials.Parameters: - materials (iterable of
openmc.Material
) – Burnable materials in the problem. Used to construct aopenmc.MaterialFilter
- scores (iterable of str) – Reaction identifiers, e.g.
"(n, fission)"
,"(n, gamma)"
, needed for the reaction rate tally.
- materials (iterable of
-
get_material_rates
(mat_id, nuc_index, react_index)[source]¶ Return an array of reaction rates for a material
Parameters: - mat_id (int) – Unique ID for the requested material
- nuc_index (iterable of int) – Index for each nuclide in
nuclides
in the desired reaction rate matrix - react_index (iterable of int) – Index for each reaction scored in the tally
Returns: rates – Array with shape
(n_nuclides, n_rxns)
with the reaction rates in this materialReturn type:
- n_nucs (int) – Number of burnable nuclides tracked by