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