diff --git a/openmc/material.py b/openmc/material.py
index 7cc7e3db60..e34123e934 100644
--- a/openmc/material.py
+++ b/openmc/material.py
@@ -607,9 +607,9 @@ class Material(IDManagerMixin):
             If enrichment_target is not supplied then it is enrichment for U235
             in weight percent. For example, input 4.95 for 4.95 weight percent
             enriched U. Default is None (natural composition).
-        enrichment_target: str, optional
+        enrichment_target : str, optional
             Single nuclide name to enrich from a natural composition (e.g., 'O16')
-        enrichment_type: {'ao', 'wo'}, optional
+        enrichment_type : {'ao', 'wo'}, optional
             'ao' for enrichment as atom percent and 'wo' for weight percent.
             Default is: 'ao' for two-isotope enrichment; 'wo' for U enrichment
 
diff --git a/tests/unit_tests/test_material.py b/tests/unit_tests/test_material.py
index 8e9ebb362d..e366401827 100644
--- a/tests/unit_tests/test_material.py
+++ b/tests/unit_tests/test_material.py
@@ -58,7 +58,8 @@ def test_elements_by_name():
     assert a._nuclides == b._nuclides
     assert b._nuclides == c._nuclides
 
-def test_adding_elements_by_formula():
+
+def test_add_elements_by_formula():
     """Test adding elements from a formula"""
     # testing the correct nuclides and elements are added to a material
     m = openmc.Material()
@@ -354,4 +355,3 @@ def test_mix_materials():
     assert m3.density == pytest.approx(dens3)
     assert m4.density == pytest.approx(dens4)
     assert m5.density == pytest.approx(dens5)
-