Add missing xml files.

test/tests/neutronics/tallies/reaction_rates/geometry.xml

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+<?xml version='1.0' encoding='utf-8'?>
+<geometry>
+  <cell id="1" material="1" region="-1" universe="1" />
+  <cell id="2" material="2" region="-2" universe="1" />
+  <cell id="3" material="3" region="-3" universe="1" />
+  <cell id="4" material="4" region="1 2 3 4 -5 6 -7 8 -9" universe="1" />
+  <surface coeffs="0.0 0.0 0.0 1.5" id="1" type="sphere" />
+  <surface coeffs="0.0 0.0 4.0 1.5" id="2" type="sphere" />
+  <surface coeffs="0.0 0.0 8.0 1.5" id="3" type="sphere" />
+  <surface boundary="reflective" coeffs="-2.5" id="4" name="minimum x" type="x-plane" />
+  <surface boundary="reflective" coeffs="2.5" id="5" name="maximum x" type="x-plane" />
+  <surface boundary="reflective" coeffs="-2.5" id="6" name="minimum y" type="y-plane" />
+  <surface boundary="reflective" coeffs="2.5" id="7" name="maximum y" type="y-plane" />
+  <surface boundary="reflective" coeffs="-2.0" id="8" type="z-plane" />
+  <surface boundary="reflective" coeffs="10.0" id="9" type="z-plane" />
+</geometry>

test/tests/neutronics/tallies/reaction_rates/materials.xml

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+<?xml version='1.0' encoding='utf-8'?>
+<materials>
+  <material depletable="true" id="1">
+    <density units="g/cc" value="5.0" />
+    <nuclide ao="9.051308944870946e-05" name="U234" />
+    <nuclide ao="0.010126612654073502" name="U235" />
+    <nuclide ao="0.9897364895065476" name="U238" />
+    <nuclide ao="4.63847499302226e-05" name="U236" />
+    <nuclide ao="1.999242" name="O16" />
+    <nuclide ao="0.000758" name="O17" />
+  </material>
+  <material depletable="true" id="2">
+    <density units="g/cc" value="5.0" />
+    <nuclide ao="0.0004523305496680539" name="U234" />
+    <nuclide ao="0.05060678290832386" name="U235" />
+    <nuclide ao="0.948709083169038" name="U238" />
+    <nuclide ao="0.00023180337297007338" name="U236" />
+    <nuclide ao="1.999242" name="O16" />
+    <nuclide ao="0.000758" name="O17" />
+  </material>
+  <material depletable="true" id="3">
+    <density units="g/cc" value="5.0" />
+    <nuclide ao="0.0009040745407538578" name="U234" />
+    <nuclide ao="0.10114794158928406" name="U235" />
+    <nuclide ao="0.8974846777145036" name="U238" />
+    <nuclide ao="0.00046330615545845175" name="U236" />
+    <nuclide ao="1.999242" name="O16" />
+    <nuclide ao="0.000758" name="O17" />
+  </material>
+  <material depletable="true" id="4">
+    <density units="g/cc" value="0.1" />
+    <nuclide ao="1.99968852" name="H1" />
+    <nuclide ao="0.00031148" name="H2" />
+    <nuclide ao="0.999621" name="O16" />
+    <nuclide ao="0.000379" name="O17" />
+    <nuclide ao="5.4e-05" name="U234" />
+    <nuclide ao="0.007204" name="U235" />
+    <nuclide ao="0.992742" name="U238" />
+  </material>
+</materials>

test/tests/neutronics/tallies/reaction_rates/settings.xml

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+<?xml version='1.0' encoding='utf-8'?>
+<settings>
+  <run_mode>fixed source</run_mode>
+  <particles>100</particles>
+  <batches>50</batches>
+  <inactive>10</inactive>
+  <source strength="1.0">
+    <space type="box">
+      <parameters>-5.0 -5.0 0 5.0 5.0 12.0</parameters>
+    </space>
+  </source>
+  <temperature_default>600.0</temperature_default>
+  <temperature_method>nearest</temperature_method>
+  <temperature_multipole>false</temperature_multipole>
+  <temperature_range>294.0 1600.0</temperature_range>
+</settings>