Make use of openmc.data.neutron.get_metadata()

Changed _get_metadata() to a public function and
used it in openmc-update-inputs

openmc/data/neutron.py

@@ -34,7 +34,7 @@ from openmc.mixin import EqualityMixin
 _RESONANCE_ENERGY_GRID = np.logspace(-3, 3, 61)
 
 
-def _get_metadata(zaid, metastable_scheme='nndc'):
+def get_metadata(zaid, metastable_scheme='nndc'):
     """Return basic identifying data for a nuclide with a given ZAID.
 
     Parameters
@@ -677,7 +677,7 @@ class IncidentNeutron(EqualityMixin):
         # If mass number hasn't been specified, make an educated guess
         zaid, xs = ace.name.split('.')
         name, element, Z, mass_number, metastable = \
-            _get_metadata(int(zaid), metastable_scheme)
+            get_metadata(int(zaid), metastable_scheme)
 
         # Assign temperature to the running list
         kTs = [ace.temperature*EV_PER_MEV]

scripts/openmc-update-inputs

@@ -241,15 +241,9 @@ def update_geometry(geometry_root):
 
 def replace_zaid(name):
     """Replace a nuclide name in the ZAID notation with the correct name."""
-    # TODO: Account for metastable and any other special cases
-    name = name.strip()
-    z = int(name[:-3])
-    a = int(name[-3:])  # Strips leading 0s
-    symbol = openmc.data.ATOMIC_SYMBOL[z]
-    name = str(symbol).title() + str(a)
+    zaid = int(name.strip())
+    name = openmc.data.neutron.get_metadata(zaid)[0]
     return name
-    
-
 
 def update_materials(root):
     """Update the given XML materials tree. Return True if changes were made."""