From 1e5cfe09613cf8260840d56900408702e662eba8 Mon Sep 17 00:00:00 2001
From: Andrew Johnson <drewej@protonmail.com>
Date: Thu, 22 Aug 2019 15:32:45 -0500
Subject: [PATCH] Return list of str from FY helpers update_tally_nuclides

---
 openmc/deplete/abc.py                           | 8 ++++----
 tests/unit_tests/test_deplete_fission_yields.py | 4 ++--
 2 files changed, 6 insertions(+), 6 deletions(-)

diff --git a/openmc/deplete/abc.py b/openmc/deplete/abc.py
index 16d2d7abbd..fb638e5c21 100644
--- a/openmc/deplete/abc.py
+++ b/openmc/deplete/abc.py
@@ -458,13 +458,13 @@ class FissionYieldHelper(ABC):
 
         Returns
         -------
-        nuclides : tuple of str
+        nuclides : list of str
             Union of nuclides that the :class:`openmc.deplete.Operator`
             says have non-zero densities at this stage and those that
             have yield data. Sorted by nuclide name
 
         """
-        return tuple(sorted(self._chain_set & set(nuclides)))
+        return sorted(self._chain_set & set(nuclides))
 
     @classmethod
     def from_operator(cls, operator, **kwargs):
@@ -550,7 +550,7 @@ class TalliedFissionYieldHelper(FissionYieldHelper):
 
         Returns
         -------
-        nuclides : tuple of str
+        nuclides : list of str
             Union of input nuclides and those that have multiple sets
             of yield data.  Sorted by nuclide name
 
@@ -562,7 +562,7 @@ class TalliedFissionYieldHelper(FissionYieldHelper):
         assert self._fission_rate_tally is not None, (
                 "Run generate_tallies first")
         overlap = set(self._chain_nuclides).intersection(set(nuclides))
-        nuclides = tuple(sorted(overlap))
+        nuclides = sorted(overlap)
         self._tally_nucs = [self._chain_nuclides[n] for n in nuclides]
         self._fission_rate_tally.nuclides = nuclides
         return nuclides
diff --git a/tests/unit_tests/test_deplete_fission_yields.py b/tests/unit_tests/test_deplete_fission_yields.py
index 2842043d12..d3faec35bf 100644
--- a/tests/unit_tests/test_deplete_fission_yields.py
+++ b/tests/unit_tests/test_deplete_fission_yields.py
@@ -206,7 +206,7 @@ def test_cutoff_helper(materials, nuclide_bundle, therm_frac):
 
     non_zero_nucs = [n.name for n in nuclide_bundle]
     tally_nucs = helper.update_tally_nuclides(non_zero_nucs)
-    assert tally_nucs == ("Pu239", "U235",)
+    assert tally_nucs == ["Pu239", "U235",]
 
     # Check tallies
     fission_tally = helper._fission_rate_tally
@@ -249,7 +249,7 @@ def test_averaged_helper(materials, nuclide_bundle, avg_energy):
     helper.generate_tallies(materials, [0])
     tallied_nucs = helper.update_tally_nuclides(
         [n.name for n in nuclide_bundle])
-    assert tallied_nucs == ("Pu239", "U235")
+    assert tallied_nucs == ["Pu239", "U235"]
 
     # check generated tallies
     fission_tally = helper._fission_rate_tally