Initial implementation with trio of MGXS IPython Notebooks

.gitignore

@@ -71,4 +71,6 @@ docs/source/pythonapi/examples/*.xml
 docs/source/pythonapi/examples/*.png
 docs/source/pythonapi/examples/*.xls
 docs/source/pythonapi/examples/mgxs
-docs/source/pythonapi/examples/tracks
+docs/source/pythonapi/examples/tracks
+docs/source/pythonapi/examples/fission-rates
+docs/source/pythonapi/examples/plots

docs/source/pythonapi/examples/pandas-dataframes.ipynb

@@ -126,7 +126,7 @@
    "cell_type": "markdown",
    "metadata": {},
    "source": [
-    "Now let's move on to the geometry. This problem will be a square array of fuel pins, which we can use OpenMC's lattice/universe feature for. The basic universe will have three regions for the fuel, the clad, and the surrounding coolant. The first step is to create the bounding surfaces for fuel and clad, as well as the outer bounding surfaces of the problem."
+    "Now let's move on to the geometry. This problem will be a square array of fuel pins and control rod guide tubes for which we can use OpenMC's lattice/universe feature. The basic universe will have three regions for the fuel, the clad, and the surrounding coolant. The first step is to create the bounding surfaces for fuel and clad, as well as the outer bounding surfaces of the problem."
    ]
   },
   {
@@ -155,7 +155,7 @@
    "cell_type": "markdown",
    "metadata": {},
    "source": [
-    "With the surfaces defined, we can now create cells that are defined by intersections of half-spaces created by the surfaces."
+    "With the surfaces defined, we can now construct a fuel pin cell from cells that are defined by intersections of half-spaces created by the surfaces."
    ]
   },
   {

openmc/opencg_compatible.py

@@ -882,7 +882,7 @@ def get_opencg_lattice(openmc_lattice):
     outer = openmc_lattice.outer
 
     if len(pitch) == 2:
-        new_pitch = np.ones(3, dtype=np.float64)
+        new_pitch = np.ones(3, dtype=np.float64) * np.inf
         new_pitch[:2] = pitch
         pitch = new_pitch