diff --git a/docs/source/pythonapi/examples/tally-arithmetic.ipynb b/docs/source/pythonapi/examples/tally-arithmetic.ipynb
index 64681b424..9d2a81493 100644
--- a/docs/source/pythonapi/examples/tally-arithmetic.ipynb
+++ b/docs/source/pythonapi/examples/tally-arithmetic.ipynb
@@ -572,7 +572,7 @@
       "      Copyright:      2011-2015 Massachusetts Institute of Technology\n",
       "      License:        http://mit-crpg.github.io/openmc/license.html\n",
       "      Version:        0.6.2\n",
-      "      Date/Time:      2015-08-10 06:51:18\n",
+      "      Date/Time:      2015-08-10 13:21:32\n",
       "      MPI Processes:  4\n",
       "\n",
       " ===========================================================================\n",
@@ -628,20 +628,20 @@
       "\n",
       " =======================>     TIMING STATISTICS     <=======================\n",
       "\n",
-      " Total time for initialization     =  8.9900E-01 seconds\n",
-      "   Reading cross sections          =  2.5700E-01 seconds\n",
-      " Total time in simulation          =  9.5070E+00 seconds\n",
-      "   Time in transport only          =  8.6890E+00 seconds\n",
-      "   Time in inactive batches        =  1.0080E+00 seconds\n",
-      "   Time in active batches          =  8.4990E+00 seconds\n",
-      "   Time synchronizing fission bank =  7.8300E-01 seconds\n",
-      "     Sampling source sites         =  4.4000E-02 seconds\n",
-      "     SEND/RECV source sites        =  0.0000E+00 seconds\n",
-      "   Time accumulating tallies       =  3.0000E-03 seconds\n",
+      " Total time for initialization     =  1.4260E+00 seconds\n",
+      "   Reading cross sections          =  3.8800E-01 seconds\n",
+      " Total time in simulation          =  9.0700E+00 seconds\n",
+      "   Time in transport only          =  8.3270E+00 seconds\n",
+      "   Time in inactive batches        =  1.4110E+00 seconds\n",
+      "   Time in active batches          =  7.6590E+00 seconds\n",
+      "   Time synchronizing fission bank =  6.7300E-01 seconds\n",
+      "     Sampling source sites         =  1.1000E-02 seconds\n",
+      "     SEND/RECV source sites        =  2.0000E-03 seconds\n",
+      "   Time accumulating tallies       =  1.0000E-03 seconds\n",
       " Total time for finalization       =  2.0000E-03 seconds\n",
-      " Total time elapsed                =  1.0410E+01 seconds\n",
-      " Calculation Rate (inactive)       =  12400.8 neutrons/second\n",
-      " Calculation Rate (active)         =  4412.28 neutrons/second\n",
+      " Total time elapsed                =  1.0500E+01 seconds\n",
+      " Calculation Rate (inactive)       =  8858.97 neutrons/second\n",
+      " Calculation Rate (active)         =  4896.20 neutrons/second\n",
       "\n",
       " ============================>     RESULTS     <============================\n",
       "\n",
@@ -726,7 +726,8 @@
    "metadata": {},
    "source": [
     "We have a tally of the total fission rate and the total absorption rate, so we can calculate k-infinity as:\n",
-    "$$k_\\infty = \\frac{\\nu \\Sigma_f \\phi}{\\Sigma_a \\phi}$$"
+    "$$k_\\infty = \\frac{\\langle \\nu \\Sigma_f \\phi \\rangle}{\\langle \\Sigma_a \\phi \\rangle}$$\n",
+    "In this notation, $\\langle \\cdot \\rangle^a_b$ represents an OpenMC that is integrated over region $a$ and energy range $b$. If $a$ or $b$ is not reported, it means the value represents an integral over all space or all energy, respectively."
    ]
   },
   {
@@ -794,7 +795,7 @@
    "source": [
     "Notice that even though the neutron production rate and absorption rate are separate tallies, we still get a first-order estimate of the uncertainty on the quotient of them automatically!\n",
     "\n",
-    "Now, let's analyze of few of the classic factors in the four-factor formula, starting with the resonance escape probability, which we'll define as $$p=\\frac{\\Sigma_{a,thermal}\\phi}{\\Sigma_a\\phi}$$"
+    "Now, let's analyze of few of the classic factors in the four-factor formula, starting with the resonance escape probability, which we'll define as $$p=\\frac{\\langle\\Sigma_a\\phi\\rangle_T}{\\langle\\Sigma_a\\phi\\rangle}$$ where the subscript $T$ means thermal energies."
    ]
   },
   {
@@ -860,7 +861,7 @@
    "metadata": {},
    "source": [
     "The fast fission factor can be calculated as\n",
-    "$$\\epsilon=\\frac{\\Sigma_f\\phi}{\\Sigma_{f,thermal}\\phi}$$"
+    "$$\\epsilon=\\frac{\\langle\\Sigma_f\\phi\\rangle}{\\langle\\Sigma_f\\phi\\rangle_T}$$"
    ]
   },
   {
@@ -927,8 +928,8 @@
    "metadata": {},
    "source": [
     "The thermal flux utilization is calculated as\n",
-    "$$f=\\frac{\\Sigma_{a,thermal}^F\\phi}{\\Sigma_a\\phi}$$\n",
-    "where $F$ denotes fuel."
+    "$$f=\\frac{\\langle\\Sigma_a\\phi\\rangle^F_T}{\\langle\\Sigma_a\\phi\\rangle_T}$$\n",
+    "where the superscript $F$ denotes fuel."
    ]
   },
   {
@@ -946,6 +947,8 @@
        "  <thead>\n",
        "    <tr style=\"text-align: right;\">\n",
        "      <th></th>\n",
+       "      <th>energy [MeV]</th>\n",
+       "      <th>cell</th>\n",
        "      <th>nuclide</th>\n",
        "      <th>score</th>\n",
        "      <th>mean</th>\n",
@@ -957,24 +960,28 @@
        "      <th></th>\n",
        "      <th></th>\n",
        "      <th></th>\n",
+       "      <th></th>\n",
+       "      <th></th>\n",
        "    </tr>\n",
        "  </thead>\n",
        "  <tbody>\n",
        "    <tr>\n",
        "      <th>0</th>\n",
+       "      <td>0.0e+00 - 6.2e-01</td>\n",
+       "      <td>10000</td>\n",
        "      <td>total</td>\n",
        "      <td>absorption</td>\n",
-       "      <td>0.769263</td>\n",
-       "      <td>0.004172</td>\n",
+       "      <td>0.802094</td>\n",
+       "      <td>0.004432</td>\n",
        "    </tr>\n",
        "  </tbody>\n",
        "</table>\n",
        "</div>"
       ],
       "text/plain": [
-       "    nuclide       score      mean  std. dev.\n",
-       "bin                                         \n",
-       "0     total  absorption  0.769263   0.004172"
+       "          energy [MeV]   cell nuclide       score      mean  std. dev.\n",
+       "bin                                                                   \n",
+       "0    0.0e+00 - 6.2e-01  10000   total  absorption  0.802094   0.004432"
       ]
      },
      "execution_count": 29,
@@ -985,7 +992,7 @@
    "source": [
     "# Compute thermal flux utilization factor using tally arithmetic\n",
     "fuel_therm_abs_rate = sp.get_tally(name='fuel therm. abs. rate')\n",
-    "therm_util = fuel_therm_abs_rate / abs_rate\n",
+    "therm_util = fuel_therm_abs_rate / therm_abs_rate\n",
     "therm_util.get_pandas_dataframe()"
    ]
   },