openmc.deplete.helpers.DirectReactionRateHelper¶
-
class
openmc.deplete.helpers.
DirectReactionRateHelper
(n_nuc, n_react)[source]¶ Class for generating one-group reaction rates with direct tallies
This class generates reaction rate tallies for each nuclide and transmutation reaction relevant for a depletion calculation.
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.
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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: Returns: rates – Array with shape
(n_nuclides, n_rxns)
with the reaction rates in this materialReturn type:
-
nuclides
¶ List of nuclides with requested reaction rates
- n_nucs (int) – Number of burnable nuclides tracked by