Multi-group capability for kinetics parameter calculations with Iterated Fission Probability (#3425)

Co-authored-by: GuySten <guyste@post.bgu.ac.il>
Co-authored-by: Paul Romano <paul.k.romano@gmail.com>
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Alex Nellis 2025-09-26 12:27:05 -04:00 committed by GitHub
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@ -67,6 +67,23 @@ are needed to compute kinetics parameters in OpenMC:
Obtaining kinetics parameters
-----------------------------
The ``Model`` class can be used to automatically generate all IFP tallies using
the Python API with :attr:`openmc.Settings.ifp_n_generation` greater than 0 and
the :meth:`openmc.Model.add_ifp_kinetics_tallies` method::
model = openmc.Model(geometry, settings=settings)
model.add_kinetics_parameters_tallies(num_groups=6) # Add 6 precursor groups
Alternatively, each of the tallies can be manually defined using group-wise or
total :math:`\beta_{\text{eff}}` specified by providing a 6-group
:class:`openmc.DelayedGroupFilter`::
beta_tally = openmc.Tally(name="group-beta-score")
beta_tally.scores = ["ifp-beta-numerator"]
# Add DelayedGroupFilter to enable group-wise tallies
beta_tally.filters = [openmc.DelayedGroupFilter(list(range(1, 7)))]
Here is an example showing how to declare the three available IFP scores in a
single tally::
@ -95,6 +112,12 @@ for ``ifp-denominator``:
\beta_{\text{eff}} = \frac{S_{\text{ifp-beta-numerator}}}{S_{\text{ifp-denominator}}}
The kinetics parameters can be retrieved directly from a statepoint file using
the :meth:`openmc.StatePoint.ifp_results` method::
with openmc.StatePoint(output_path) as sp:
generation_time, beta_eff = sp.get_kinetics_parameters()
.. only:: html
.. rubric:: References
@ -107,4 +130,4 @@ for ``ifp-denominator``:
of the Iterated Fission Probability Method in OpenMC to Compute Adjoint-Weighted
Kinetics Parameters", International Conference on Mathematics and Computational
Methods Applied to Nuclear Science and Engineering (M&C 2025), Denver, April 27-30,
2025 (to be presented).
2025.