diff --git a/openmc/deplete/openmc_wrapper.py b/openmc/deplete/openmc_wrapper.py
index 5c7a1aeba..bf0a12471 100644
--- a/openmc/deplete/openmc_wrapper.py
+++ b/openmc/deplete/openmc_wrapper.py
@@ -31,7 +31,7 @@ from .function import Settings, Operator
 
 
 
-def chunks(items, n):
+def _chunks(items, n):
     min_size, extra = divmod(len(items), n)
     j = 0
     chunk_list = []
@@ -43,70 +43,61 @@ def chunks(items, n):
 
 
 class OpenMCSettings(Settings):
-    """The OpenMCSettings class.
-
-    Extends Settings to provide information OpenMC needs to run.
+    """Extends Settings to provide information OpenMC needs to run.
 
     Attributes
     ----------
     dt_vec : numpy.array
-        Array of time steps to take. (From Settings)
-    tol : float
-        Tolerance for adaptive time stepping. (From Settings)
+        Array of time steps to in units of [s]
     output_dir : str
-        Path to output directory to save results. (From Settings)
+        Path to output directory to save results.
     chain_file : str
-        Path to the depletion chain xml file.  Defaults to the environment
-        variable "OPENDEPLETE_CHAIN" if it exists.
-    particles : int
-        Number of particles to simulate per batch.
-    batches : int
-        Number of batches.
-    inactive : int
-        Number of inactive batches.
-    lower_left : list of float
-        Coordinate of lower left of bounding box of geometry.
-    upper_right : list of float
-        Coordinate of upper right of bounding box of geometry.
-    entropy_dimension : list of int
-        Grid size of entropy.
-    dilute_initial : float, default 1.0e3
+        Path to the depletion chain xml file.  Defaults to the
+        :envvar:`OPENDEPLETE_CHAIN` environment variable if it exists.
+    dilute_initial : float
         Initial atom density to add for nuclides that are zero in initial
         condition to ensure they exist in the decay chain.  Only done for
-        nuclides with reaction rates.
+        nuclides with reaction rates. Defaults to 1.0e3.
     round_number : bool
         Whether or not to round output to OpenMC to 8 digits.
         Useful in testing, as OpenMC is incredibly sensitive to exact values.
-    constant_seed : int
-        If present, all runs will be performed with this seed.
     power : float
-        Power of the reactor in W. For a 2D problem, the power can be given in
+        Power of the reactor in [W]. For a 2D problem, the power can be given in
         W/cm as long as the "volume" assigned to a depletion material is
         actually an area in cm^2.
+    settings : openmc.Settings
+        Settings for OpenMC simulations
+
     """
 
+    _depletion_attrs = {'dt_vec', 'output_dir', 'chain_file', 'dilute_initial',
+                        'round_number', 'power'}
+
     def __init__(self):
         super().__init__()
-        # OpenMC specific
         try:
             self.chain_file = os.environ["OPENDEPLETE_CHAIN"]
         except KeyError:
             self.chain_file = None
-        self.particles = None
-        self.batches = None
-        self.inactive = None
-        self.lower_left = None
-        self.upper_right = None
-        self.entropy_dimension = None
         self.dilute_initial = 1.0e3
-
-        # OpenMC testing specific
         self.round_number = False
-        self.constant_seed = None
-
-        # Depletion problem specific
         self.power = None
 
+        # Avoid setattr to create OpenMC settings
+        self.__dict__['settings'] = openmc.Settings()
+
+    def __setattr__(self, name, value):
+        if name in self._depletion_attrs:
+            self.__dict__[name] = value
+        else:
+            setattr(self.__dict__['settings'], name, value)
+
+    def __getattr__(self, name):
+        if name in self._depletion_attrs:
+            return self.__dict__[name]
+        else:
+            return getattr(self.__dict__['settings'], name)
+
 
 class Materials(object):
     """The Materials class.
@@ -290,8 +281,8 @@ class OpenMCOperator(Operator):
                 i += 1
 
         # Decompose geometry
-        mat_burn_lists = chunks(mat_burn, comm.size)
-        mat_not_burn_lists = chunks(mat_not_burn, comm.size)
+        mat_burn_lists = _chunks(mat_burn, comm.size)
+        mat_not_burn_lists = _chunks(mat_not_burn, comm.size)
 
         mat_tally_ind = OrderedDict()
 
@@ -456,7 +447,7 @@ class OpenMCOperator(Operator):
         # Create XML files
         if comm.rank == 0:
             self.geometry.export_to_xml()
-            self.generate_settings_xml()
+            self.settings.settings.export_to_xml()
             self.generate_materials_xml()
 
         # Initialize OpenMC library
@@ -526,46 +517,6 @@ class OpenMCOperator(Operator):
 
         materials.export_to_xml()
 
-    def generate_settings_xml(self):
-        """Generates settings.xml.
-
-        This function creates settings.xml using the value of the settings
-        variable.
-
-        Todo
-        ----
-            Rewrite to generalize source box.
-        """
-
-        batches = self.settings.batches
-        inactive = self.settings.inactive
-        particles = self.settings.particles
-
-        # Just a generic settings file to get it running.
-        settings_file = openmc.Settings()
-        settings_file.batches = batches
-        settings_file.inactive = inactive
-        settings_file.particles = particles
-        settings_file.source = openmc.Source(space=openmc.stats.Box(
-            self.settings.lower_left, self.settings.upper_right))
-
-        if self.settings.entropy_dimension is not None:
-            entropy_mesh = openmc.Mesh()
-            entropy_mesh.lower_left = self.settings.lower_left
-            entropy_mesh.upper_right = self.settings.upper_right
-            entropy_mesh.dimension = self.settings.entropy_dimension
-            settings_file.entropy_mesh = entropy_mesh
-
-        # Set seed
-        if self.settings.constant_seed is not None:
-            seed = self.settings.constant_seed
-        else:
-            seed = random.randint(1, sys.maxsize-1)
-
-        settings_file.seed = self.seed = seed
-
-        settings_file.export_to_xml()
-
     def _get_tally_nuclides(self):
         nuc_set = set()
 
@@ -581,7 +532,6 @@ class OpenMCOperator(Operator):
             for i in range(1, comm.size):
                 nuc_newset = comm.recv(source=i, tag=i)
                 nuc_set |= nuc_newset
-
         else:
             comm.send(nuc_set, dest=0, tag=comm.rank)
 
diff --git a/scripts/example_run.py b/scripts/example_run.py
index 78d7dcedd..56d42b21a 100644
--- a/scripts/example_run.py
+++ b/scripts/example_run.py
@@ -1,6 +1,8 @@
 """An example file showing how to run a simulation."""
 
 import numpy as np
+import openmc
+from openmc.data import JOULE_PER_EV
 import openmc.deplete
 
 import example_geometry
@@ -15,20 +17,18 @@ N = np.floor(dt2/dt1)
 
 dt = np.repeat([dt1], N)
 
-# Create settings variable
+# Depletion settings
 settings = openmc.deplete.OpenMCSettings()
+settings.power = 2.337e15*4*JOULE_PER_EV*1e6  # MeV/second cm from CASMO
+settings.dt_vec = dt
+settings.output_dir = 'test'
 
+# OpenMC-delegated settings
 settings.particles = 1000
 settings.batches = 100
 settings.inactive = 40
-settings.lower_left = lower_left
-settings.upper_right = upper_right
-settings.entropy_dimension = [10, 10, 1]
-
-joule_per_mev = 1.6021766208e-13
-settings.power = 2.337e15*4*joule_per_mev  # MeV/second cm from CASMO
-settings.dt_vec = dt
-settings.output_dir = 'test'
+settings.source = openmc.Source(space=openmc.stats.Box(lower_left, upper_right))
+settings.verbosity = 3
 
 op = openmc.deplete.OpenMCOperator(geometry, settings)
 
diff --git a/tests/regression_tests/test_deplete_full.py b/tests/regression_tests/test_deplete_full.py
index 5f4af7a73..fcaa60eee 100644
--- a/tests/regression_tests/test_deplete_full.py
+++ b/tests/regression_tests/test_deplete_full.py
@@ -5,6 +5,8 @@ import shutil
 from pathlib import Path
 
 import numpy as np
+import openmc
+from openmc.data import JOULE_PER_EV
 import openmc.deplete
 from openmc.deplete import results
 from openmc.deplete import utilities
@@ -35,26 +37,23 @@ def test_full(run_in_tmpdir):
     N = floor(dt2/dt1)
     dt = np.full(N, dt1)
 
-    # Create settings variable
+    # Depletion settings
     settings = openmc.deplete.OpenMCSettings()
+    settings.chain_file = str(Path(__file__).parents[2] / 'chains' /
+                              'chain_simple.xml')
+    settings.power = 2.337e15*4*JOULE_PER_EV*1e6  # MeV/second cm from CASMO
+    settings.dt_vec = dt
+    settings.output_dir = "test_full"
+    settings.round_number = True
 
-
-    chain_file = str(Path(__file__).parents[2] / 'chains' / 'chain_simple.xml')
-    settings.chain_file = chain_file
+    # Add OpenMC-specific settings
     settings.particles = 100
     settings.batches = 100
     settings.inactive = 40
-    settings.lower_left = lower_left
-    settings.upper_right = upper_right
-    settings.entropy_dimension = [10, 10, 1]
-
-    settings.round_number = True
-    settings.constant_seed = 1
-
-    joule_per_mev = 1.6021766208e-13
-    settings.power = 2.337e15*4*joule_per_mev  # MeV/second cm from CASMO
-    settings.dt_vec = dt
-    settings.output_dir = "test_full"
+    space = openmc.stats.Box(lower_left, upper_right)
+    settings.source = openmc.Source(space=space)
+    settings.seed = 1
+    settings.verbosity = 3
 
     op = openmc.deplete.OpenMCOperator(geometry, settings)