diff --git a/openmc/data/neutron.py b/openmc/data/neutron.py
index 842dfe735..fb00bccb9 100644
--- a/openmc/data/neutron.py
+++ b/openmc/data/neutron.py
@@ -682,10 +682,6 @@ class IncidentNeutron(EqualityMixin):
                          'cross section is given.'.format(mt))
                     continue
 
-                # Don't duplicate fission cross sections
-                if mt == 18:
-                    continue
-
                 # Create redundant reaction with appropriate cross section
                 rx = Reaction(mt)
                 mts = data.get_reaction_components(mt)
diff --git a/openmc/data/reaction.py b/openmc/data/reaction.py
index 26b51363f..547208dae 100644
--- a/openmc/data/reaction.py
+++ b/openmc/data/reaction.py
@@ -576,14 +576,7 @@ def _get_photon_products_ace(ace, rx):
         # Determine corresponding reaction
         neutron_mt = photon_mts[i] // 1000
 
-        # Restrict to photons that match the requested MT. Note that if the
-        # photon is assigned to MT=18 but the file splits fission into
-        # MT=19,20,21,38, we assign the photon product to each of the individual
-        # reactions
-        if neutron_mt == 18:
-            if rx.mt not in (18, 19, 20, 21, 38):
-                continue
-        elif neutron_mt != rx.mt:
+        if neutron_mt != rx.mt:
             continue
 
         # Create photon product and assign to reactions
diff --git a/scripts/openmc-get-photon-data b/scripts/openmc-get-photon-data
index ae268a4cc..39e44b177 100755
--- a/scripts/openmc-get-photon-data
+++ b/scripts/openmc-get-photon-data
@@ -1,4 +1,4 @@
-#!/usr/bin/env python
+#!/usr/bin/env python3
 
 """
 Download ENDF/B-VII.1 ENDF data from NNDC for photo-atomic and atomic