diff --git a/docs/source/pythonapi/deplete.rst b/docs/source/pythonapi/deplete.rst
index e9cd6d305..d4a0f128f 100644
--- a/docs/source/pythonapi/deplete.rst
+++ b/docs/source/pythonapi/deplete.rst
@@ -181,7 +181,7 @@ total system energy.
    helpers.DirectReactionRateHelper
    helpers.EnergyScoreHelper
    helpers.FissionYieldCutoffHelper
-
+   helpers.FluxCollapseHelper
 
 Abstract Base Classes
 ---------------------
diff --git a/openmc/deplete/helpers.py b/openmc/deplete/helpers.py
index 11692e1a7..ec51c211c 100644
--- a/openmc/deplete/helpers.py
+++ b/openmc/deplete/helpers.py
@@ -109,107 +109,6 @@ class FluxCollapseHelper(ReactionRateHelper):
 
     .. versionadded:: 0.12.1
 
-    Parameters
-    ----------
-    n_nucs : int
-        Number of burnable nuclides tracked by :class:`openmc.deplete.Operator`
-    n_react : int
-        Number of reactions tracked by :class:`openmc.deplete.Operator`
-    energies : iterable of float
-        Energy group boundaries for flux spectrum in [eV]
-
-    Attributes
-    ----------
-    nuclides : list of str
-        All nuclides with desired reaction rates.
-    """
-    def __init__(self, n_nucs, n_reacts, energies):
-        super().__init__(n_nucs, n_reacts)
-        self._energies = asarray(energies)
-
-    def generate_tallies(self, materials, scores):
-        """Produce multigroup flux spectrum tally
-
-        Uses the :mod:`openmc.lib` module to generate a multigroup flux tally
-        for each burnable material.
-
-        Parameters
-        ----------
-        materials : iterable of :class:`openmc.Material`
-            Burnable materials in the problem. Used to construct a
-            :class:`openmc.MaterialFilter`
-        scores : iterable of str
-            Reaction identifiers, e.g. ``"(n, fission)"``, ``"(n, gamma)"``,
-            needed for the reaction rate tally.
-        """
-        self._materials = materials
-
-        # Convert reactions to MT values (needed when collapsing)
-        mt_values = {v: k for k, v in REACTION_NAME.items()}
-        mt_values['fission'] = 18
-        self._mts = [mt_values[x] for x in scores]
-
-        # Create flux tally with material and energy filters
-        self._flux_tally = Tally()
-        self._flux_tally.writable = False
-        self._flux_tally.filters = [
-            MaterialFilter(materials),
-            EnergyFilter(self._energies)
-        ]
-        self._flux_tally.scores = ['flux']
-
-    def get_material_rates(self, mat_index, nuc_index, react_index):
-        """Return an array of reaction rates for a material
-
-        Parameters
-        ----------
-        mat_index : int
-            Index for material
-        nuc_index : iterable of int
-            Index for each nuclide in :attr:`nuclides` in the
-            desired reaction rate matrix
-        react_index : iterable of int
-            Index for each reaction scored in the tally
-
-        Returns
-        -------
-        rates : numpy.ndarray
-            Array with shape ``(n_nuclides, n_rxns)`` with the reaction rates in
-            this material
-
-        """
-        self._results_cache.fill(0.0)
-
-        # Get flux for specified material
-        shape = (len(self._materials), len(self._energies) - 1)
-        mean_value = self._flux_tally.mean.reshape(shape)
-        flux = mean_value[mat_index]
-
-        mat = self._materials[mat_index]
-
-        # Build nucname: density mapping to enable O(1) lookup in loop below
-        densities = dict(zip(mat.nuclides, mat.densities))
-
-        for name, i_nuc in zip(self.nuclides, nuc_index):
-            # Determine density of nuclide
-            density = densities[name]
-
-            for mt, i_react in zip(self._mts, react_index):
-                # Use flux to collapse reaction rate (per N)
-                nuc = openmc.lib.nuclides[name]
-                rate_per_nuc = nuc.collapse_rate(mt, mat.temperature, self._energies, flux)
-
-                # Multiply by density to get absolute reaction rate
-                self._results_cache[i_nuc, i_react] = rate_per_nuc * density
-
-        return self._results_cache
-
-
-class HybridReactionHelper(ReactionRateHelper):
-    """Class that generates tallies for one-group rates
-
-    .. versionadded:: 0.12.1
-
     Parameters
     ----------
     n_nucs : int
diff --git a/openmc/deplete/operator.py b/openmc/deplete/operator.py
index bc106278b..1f99abe95 100644
--- a/openmc/deplete/operator.py
+++ b/openmc/deplete/operator.py
@@ -27,7 +27,7 @@ from .results_list import ResultsList
 from .helpers import (
     DirectReactionRateHelper, ChainFissionHelper, ConstantFissionYieldHelper,
     FissionYieldCutoffHelper, AveragedFissionYieldHelper, EnergyScoreHelper,
-    SourceRateHelper, FluxCollapseHelper, HybridReactionHelper)
+    SourceRateHelper, FluxCollapseHelper)
 
 
 __all__ = ["Operator", "OperatorResult"]
@@ -113,16 +113,20 @@ class Operator(TransportOperator):
         ``fission_yield_mode``. Will be passed directly on to the
         helper. Passing a value of None will use the defaults for
         the associated helper.
-    reaction_rate_mode : {"direct", "flux"}
+    reaction_rate_mode : {"direct", "flux"}, optional
         Indicate how one-group reaction rates should be calculated. The "direct"
         method tallies transmutation reaction rates directly. The "flux" method
         tallies a multigroup flux spectrum and then collapses one-group reaction
-        rates after a transport solve.
+        rates after a transport solve (with an option to tally some reaction
+        rates directly).
 
         .. versionadded:: 0.12.1
-    reaction_rate_opts : iterable of float
-        Energy group boundaries that are to be used for calculating a multigroup
-        flux spectrum when the "flux" based ``reaction_rate_mode`` is being used.
+    reaction_rate_opts : dict, optional
+        Keyword arguments that are passed to the reaction rate helper class.
+        When ``reaction_rate_mode`` is set to "flux", energy group boundaries
+        can be set using the "energies" key. See the
+        :class:`~openmc.deplete.helpers.FluxCollapseHelper` class for all
+        options.
 
         .. versionadded:: 0.12.1
     reduce_chain : bool, optional
@@ -255,7 +259,7 @@ class Operator(TransportOperator):
         if reaction_rate_mode == "direct":
             self._rate_helper = DirectReactionRateHelper(
                 self.reaction_rates.n_nuc, self.reaction_rates.n_react)
-        elif reaction_rate_mode in ("flux", "hybrid"):
+        elif reaction_rate_mode == "flux":
             if reaction_rate_opts is None:
                 reaction_rate_opts = {}
 
@@ -264,15 +268,9 @@ class Operator(TransportOperator):
                 raise ValueError(
                     "Energy group boundaries must be specified in the "
                     "reaction_rate_opts argument when reaction_rate_mode is"
-                    "set to 'flux' or 'hybrid'.")
+                    "set to 'flux'.")
 
-            if reaction_rate_mode == "flux":
-                cls = FluxCollapseHelper
-            else:
-                cls = HybridReactionHelper
-
-
-            self._rate_helper = cls(
+            self._rate_helper = FluxCollapseHelper(
                 self.reaction_rates.n_nuc,
                 self.reaction_rates.n_react,
                 **reaction_rate_opts