diff --git a/examples/python/lattice/nested/build-xml.py b/examples/python/lattice/nested/build-xml.py
new file mode 100644
index 000000000..b7d314f3f
--- /dev/null
+++ b/examples/python/lattice/nested/build-xml.py
@@ -0,0 +1,189 @@
+import openmc
+
+
+###############################################################################
+#                      Simulation Input File Parameters
+###############################################################################
+
+# OpenMC simulation parameters
+batches = 20
+inactive = 10
+particles = 10000
+
+
+###############################################################################
+#                 Exporting to OpenMC materials.xml File
+###############################################################################
+
+# Instantiate some Nuclides
+h1 = openmc.Nuclide('H-1')
+o16 = openmc.Nuclide('O-16')
+u235 = openmc.Nuclide('U-235')
+
+# Instantiate some Materials and register the appropriate Nuclides
+fuel = openmc.Material(material_id=1, name='fuel')
+fuel.setDensity('g/cc', 4.5)
+fuel.addNuclide(u235, 1.)
+
+moderator = openmc.Material(material_id=2, name='moderator')
+moderator.setDensity('g/cc', 1.0)
+moderator.addNuclide(h1, 2.)
+moderator.addNuclide(o16, 1.)
+moderator.addSAlphaBeta('HH2O', '71t')
+
+# Instantiate a MaterialsFile, register all Materials, and export to XML
+materials_file = openmc.MaterialsFile()
+materials_file.setDefaultXS('71c')
+materials_file.addMaterials([moderator, fuel])
+materials_file.exportToXML()
+
+
+###############################################################################
+#                 Exporting to OpenMC geometry.xml File
+###############################################################################
+
+# Instantiate Surfaces
+left = openmc.XPlane(surface_id=1, x0=-2, name='left')
+right = openmc.XPlane(surface_id=2, x0=2, name='right')
+bottom = openmc.YPlane(surface_id=3, y0=-2, name='bottom')
+top = openmc.YPlane(surface_id=4, y0=2, name='top')
+fuel1 = openmc.ZCylinder(surface_id=5, x0=0, y0=0, R=0.4)
+fuel2 = openmc.ZCylinder(surface_id=6, x0=0, y0=0, R=0.3)
+fuel3 = openmc.ZCylinder(surface_id=7, x0=0, y0=0, R=0.2)
+
+left.setBoundaryType('vacuum')
+right.setBoundaryType('vacuum')
+top.setBoundaryType('vacuum')
+bottom.setBoundaryType('vacuum')
+
+# Instantiate Cells
+cell1 = openmc.Cell(cell_id=1, name='Cell 1')
+cell2 = openmc.Cell(cell_id=2, name='Cell 2')
+cell3 = openmc.Cell(cell_id=101, name='cell 3')
+cell4 = openmc.Cell(cell_id=102, name='cell 4')
+cell5 = openmc.Cell(cell_id=201, name='cell 5')
+cell6 = openmc.Cell(cell_id=202, name='cell 6')
+cell7 = openmc.Cell(cell_id=301, name='cell 7')
+cell8 = openmc.Cell(cell_id=302, name='cell 8')
+
+# Register Surfaces with Cells
+cell1.addSurface(left, halfspace=+1)
+cell1.addSurface(right, halfspace=-1)
+cell1.addSurface(bottom, halfspace=+1)
+cell1.addSurface(top, halfspace=-1)
+cell2.addSurface(left, halfspace=+1)
+cell2.addSurface(right, halfspace=-1)
+cell2.addSurface(bottom, halfspace=+1)
+cell2.addSurface(top, halfspace=-1)
+cell3.addSurface(fuel1, halfspace=-1)
+cell4.addSurface(fuel1, halfspace=+1)
+cell5.addSurface(fuel2, halfspace=-1)
+cell6.addSurface(fuel2, halfspace=+1)
+cell7.addSurface(fuel3, halfspace=-1)
+cell8.addSurface(fuel3, halfspace=+1)
+
+# Register Materials with Cells
+cell3.setFill(fuel)
+cell4.setFill(moderator)
+cell5.setFill(fuel)
+cell6.setFill(moderator)
+cell7.setFill(fuel)
+cell8.setFill(moderator)
+
+# Instantiate Universe
+univ1 = openmc.Universe(universe_id=1)
+univ2 = openmc.Universe(universe_id=2)
+univ3 = openmc.Universe(universe_id=3)
+univ4 = openmc.Universe(universe_id=5)
+root = openmc.Universe(universe_id=0, name='root universe')
+
+# Register Cells with Universe
+univ1.addCells([cell3, cell4])
+univ2.addCells([cell5, cell6])
+univ3.addCells([cell7, cell8])
+root.addCell(cell1)
+univ4.addCell(cell2)
+
+# Instantiate nested Lattices
+lattice1 = openmc.Lattice(lattice_id=4, name='4x4 assembly')
+lattice1.setDimension([2, 2])
+lattice1.setLowerLeft([-1., -1.])
+lattice1.setWidth([1., 1.])
+lattice1.setUniverses([[univ1, univ2],
+                       [univ2, univ3]])
+
+lattice2 = openmc.Lattice(lattice_id=6, name='4x4 core')
+lattice2.setDimension([2, 2])
+lattice2.setLowerLeft([-2., -2.])
+lattice2.setWidth([2., 2.])
+lattice2.setUniverses([[univ4, univ4],
+                       [univ4, univ4]])
+
+# Fill Cell with the Lattice
+cell1.setFill(lattice2)
+cell2.setFill(lattice1)
+
+# Instantiate a Geometry and register the root Universe
+geometry = openmc.Geometry()
+geometry.setRootUniverse(root)
+
+# Instantiate a GeometryFile, register Geometry, and export to XML
+geometry_file = openmc.GeometryFile()
+geometry_file.setGeometry(geometry)
+geometry_file.exportToXML()
+
+
+###############################################################################
+#                   Exporting to OpenMC settings.xml File
+###############################################################################
+
+# Instantiate a SettingsFile, set all runtime parameters, and export to XML
+settings_file = openmc.SettingsFile()
+settings_file.setBatches(batches)
+settings_file.setInactive(inactive)
+settings_file.setParticles(particles)
+settings_file.setSourceSpace('box', [-1, -1, -1, 1, 1, 1])
+settings_file.exportToXML()
+
+
+###############################################################################
+#                   Exporting to OpenMC plots.xml File
+###############################################################################
+
+plot = openmc.Plot(plot_id=1)
+plot.setOrigin([0, 0, 0])
+plot.setWidth([4, 4])
+plot.setPixels([400, 400])
+plot.setColor('mat')
+
+# Instantiate a PlotsFile, add Plot, and export to XML
+plot_file = openmc.PlotsFile()
+plot_file.addPlot(plot)
+plot_file.exportToXML()
+
+
+###############################################################################
+#                   Exporting to OpenMC tallies.xml File
+###############################################################################
+
+# Instantiate a tally mesh
+mesh = openmc.Mesh(mesh_id=1)
+mesh.setType('rectangular')
+mesh.setDimension([4, 4])
+mesh.setLowerLeft([-2, -2])
+mesh.setWidth([1, 1])
+
+# Instantiate tally Filter
+mesh_filter = openmc.Filter()
+mesh_filter.setMesh(mesh)
+
+# Instantiate the Tally
+tally = openmc.Tally(tally_id=1)
+tally.addFilter(mesh_filter)
+tally.addScore('total')
+
+# Instantiate a TalliesFile, register Tally/Mesh, and export to XML
+tallies_file = openmc.TalliesFile()
+tallies_file.addMesh(mesh)
+tallies_file.addTally(tally)
+tallies_file.exportToXML()
diff --git a/examples/python/lattice/nested/geometry.xml b/examples/python/lattice/nested/geometry.xml
deleted file mode 100644
index f223cf3bb..000000000
--- a/examples/python/lattice/nested/geometry.xml
+++ /dev/null
@@ -1,45 +0,0 @@
-<?xml version="1.0"?>
-<geometry>
-
-  <cell id="1"                fill="6" surfaces="1 -2 3 -4" />
-  <cell id="2"   universe="5" fill="4" surfaces="1 -2 3 -4" />
-  <cell id="101" universe="1" material="1" surfaces="-5" />
-  <cell id="102" universe="1" material="2" surfaces="5" />
-  <cell id="201" universe="2" material="1" surfaces="-6" />
-  <cell id="202" universe="2" material="2" surfaces="6" />
-  <cell id="301" universe="3" material="1" surfaces="-7" />
-  <cell id="302" universe="3" material="2" surfaces="7" />
-
-  <!-- 4 x 4 assembly -->
-  <lattice id="4">
-    <type>rectangular</type>
-    <dimension>2 2</dimension>
-    <lower_left>-1.0 -1.0</lower_left>
-    <width>1.0 1.0</width>
-    <universes>
-      1 2
-      2 3
-    </universes>
-  </lattice>
-
-  <!-- 4 x 4 core -->
-  <lattice id="6">
-    <type>rectangular</type>
-    <dimension>2 2</dimension>
-    <lower_left>-2.0 -2.0</lower_left>
-    <width>2.0 2.0</width>
-    <universes>
-      5 5
-      5 5
-    </universes>
-  </lattice>
-
-  <surface id="1" type="x-plane" coeffs="-2.0" boundary="vacuum" />
-  <surface id="2" type="x-plane" coeffs="2.0" boundary="vacuum" />
-  <surface id="3" type="y-plane" coeffs="-2.0" boundary="vacuum" />
-  <surface id="4" type="y-plane" coeffs="2.0" boundary="vacuum" />
-  <surface id="5" type="z-cylinder" coeffs="0.0 0.0 0.4" />
-  <surface id="6" type="z-cylinder" coeffs="0.0 0.0 0.3" />
-  <surface id="7" type="z-cylinder" coeffs="0.0 0.0 0.2" />
-
-</geometry>
diff --git a/examples/python/lattice/nested/materials.xml b/examples/python/lattice/nested/materials.xml
deleted file mode 100644
index b64922136..000000000
--- a/examples/python/lattice/nested/materials.xml
+++ /dev/null
@@ -1,19 +0,0 @@
-<?xml version="1.0"?>
-<materials>
-
-  <default_xs>71c</default_xs>
-
-  <!-- Definition of materials -->
-  <material id="1">
-    <density value="4.5" units="g/cc" />
-    <nuclide name="U-235" ao="1.0" />
-  </material>
-
-  <material id="2">
-    <density value="1.0" units="g/cc" />
-    <nuclide name="H-1"  ao="2.0" />
-    <nuclide name="O-16" ao="1.0" />
-    <sab name="HH2O" xs="71t" />
-  </material>
-
-</materials>
diff --git a/examples/python/lattice/nested/plots.xml b/examples/python/lattice/nested/plots.xml
deleted file mode 100644
index a8c6fbb7c..000000000
--- a/examples/python/lattice/nested/plots.xml
+++ /dev/null
@@ -1,10 +0,0 @@
-<?xml version="1.0"?>
-<plots>
-
-  <plot id="1" color="mat">
-    <origin>0. 0. 0.</origin>
-    <width>4.0 4.0</width>
-    <pixels>400 400</pixels>
-  </plot>
-
-</plots>
diff --git a/examples/python/lattice/nested/settings.xml b/examples/python/lattice/nested/settings.xml
deleted file mode 100644
index 2a6aaaf42..000000000
--- a/examples/python/lattice/nested/settings.xml
+++ /dev/null
@@ -1,18 +0,0 @@
-<?xml version="1.0"?>
-<settings>
-
-  <!-- Parameters for k-eigenvalue calculation -->
-  <eigenvalue>
-    <batches>20</batches>
-    <inactive>10</inactive>
-    <particles>10000</particles>
-  </eigenvalue>
-
-  <!-- Starting source -->
-  <source>
-    <space type="box">
-      <parameters>-1 -1 -1  1  1  1</parameters>
-    </space>
-  </source>
-
-</settings>
diff --git a/examples/python/lattice/nested/tallies.xml b/examples/python/lattice/nested/tallies.xml
deleted file mode 100644
index 5730e6b12..000000000
--- a/examples/python/lattice/nested/tallies.xml
+++ /dev/null
@@ -1,16 +0,0 @@
-<?xml version="1.0"?>
-<tallies>
-
-  <mesh id="1">
-    <type>rectangular</type>
-    <dimension>4 4</dimension>
-    <lower_left>-2.0 -2.0</lower_left>
-    <width>1.0 1.0</width>
-  </mesh>
-
-  <tally id="1">
-    <filter type="mesh" bins="1" />
-    <scores>total</scores>
-  </tally>
-
-</tallies>