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.CoupledOperator
n_react (int) – Number of reactions tracked by an instance of
openmc.deplete.CoupledOperator
- 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.lib.Material
) – Burnable materials in the problem. Used to construct aopenmc.lib.MaterialFilter
scores (iterable of str) – Reaction identifiers, e.g.
"(n, fission)"
,"(n, gamma)"
, needed for the reaction rate tally.
- get_material_rates(mat_index, nuc_index, rx_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 material- Return type
- property nuclides¶
List of nuclides with requested reaction rates
- property rate_tally_means¶
The mean results of the tally of every material’s reaction rates for this cycle