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Co-authored-by: Patrick Shriwise <pshriwise@gmail.com>
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Paul Romano 2020-09-17 22:18:20 -05:00 • committed by GitHub
parent 18c132ab67
commit ce6bfa47b2
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3 changed files with 3 additions and 3 deletions
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2
openmc/deplete/abc.py
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@ -228,7 +228,7 @@ class ReactionRateHelper(ABC):
Responsible for generating reaction rate tallies for burnable materials,
given nuclides and scores from the operator.
Reaction rates are passed back to the operator for be used in an
Reaction rates are passed back to the operator to be used by an
:class:`openmc.deplete.OperatorResult` instance.
Parameters

2
openmc/deplete/helpers.py
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@ -108,7 +108,7 @@ class DirectReactionRateHelper(ReactionRateHelper):
class FluxCollapseHelper(ReactionRateHelper):
"""Class that generating one-group reaction rates using multigroup flux
"""Class that generates one-group reaction rates using multigroup flux
This class generates a multigroup flux tally that is used afterward to
calculate a one-group reaction rate by collapsing it with continuous-energy

2
src/nuclide.cpp
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@ -1111,7 +1111,7 @@ openmc_nuclide_collapse_rate(int index, int MT, double temperature,
*xs = data::nuclides[index]->collapse_rate(MT, temperature,
{energy, energy + n + 1}, {flux, flux + n});
} catch (const std::out_of_range& e) {
fmt::print("Cuaght error\n");
fmt::print("Caught error\n");
set_errmsg(e.what());
return OPENMC_E_OUT_OF_BOUNDS;
}