- class openmc.deplete.helpers.DirectReactionRateHelper(n_nuc, n_react)¶
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.
nuclides (list of str) – All nuclides with desired reaction rates.
- generate_tallies(materials, scores)¶
Produce one-group reaction rate tally
openmc.libto generate a tally of relevant reactions across all burnable materials.
- get_material_rates(mat_index, nuc_index, rx_index)¶
Return an array of reaction rates for a material
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
Reset the cached mean rate tallies. .. note:
This step must be performed after each transport cycle