added tally getting for filter types

GuySten · Sep 30, 2025 · Sep 26, 2025 · Sep 26, 2025 · Sep 26, 2025 · Sep 30, 2025
commit 11f4ca9296d0ddd1a6919add6fab993581033bdc
diff --git a/openmc/statepoint.py b/openmc/statepoint.py
@@ -531,7 +531,7 @@ def add_volume_information(self, volume_calc):
     def get_tally(self, scores=[], filters=[], nuclides=[],
                   name=None, id=None, estimator=None, exact_filters=False,
                   exact_nuclides=False, exact_scores=False,
-                  multiply_density=None, derivative=None):
+                  multiply_density=None, derivative=None, filter_type=None):
         """Finds and returns a Tally object with certain properties.
 
         This routine searches the list of Tallies and returns the first Tally
@@ -575,6 +575,9 @@ def get_tally(self, scores=[], filters=[], nuclides=[],
             to the same value as this parameter.
         derivative : openmc.TallyDerivative, optional
             TallyDerivative object to match.
+        filter_type : type, optional
+            If not None, the Tally must have at least one Filter that is an
+            instance of this type. For example `openmc.MeshFilter`.
 
         Returns
         -------
@@ -648,6 +651,10 @@ def get_tally(self, scores=[], filters=[], nuclides=[],
                 if not contains_filters:
                     continue
 
+            if filter_type is not None:
+                if not any(isinstance(f, filter_type) for f in test_tally.filters):
+                    continue
+
             # Determine if Tally has the queried Nuclide(s)
             if nuclides:
                 if not all(nuclide in test_tally.nuclides for nuclide in nuclides):

diff --git a/tests/unit_tests/test_statepoint.py b/tests/unit_tests/test_statepoint.py
@@ -0,0 +1,57 @@
+import openmc
+
+
+def test_get_tally_filter_type():
+    """Test various ways of retrieving tallies from a StatePoint object."""
+
+    mat = openmc.Material()
+    mat.add_nuclide('H1', 1.0)
+    mat.set_density('g/cm3', 10.0)
+
+    sphere = openmc.Sphere(r=10.0, boundary_type='vacuum')
+    cell = openmc.Cell(fill=mat, region=-sphere)
+    model = openmc.Model()
+    model.geometry = openmc.Geometry([cell])
+    model.settings.particles = 10
+    model.settings.batches = 2
+    model.settings.run_mode = 'fixed source'
+
+    reg_mesh = openmc.RegularMesh().from_domain(cell)
+    tally1 = openmc.Tally(tally_id=1)
+    mesh_filter = openmc.MeshFilter(reg_mesh)
+    tally1.filters = [mesh_filter]
+    tally1.scores = ['flux']
+
+    tally2 = openmc.Tally(tally_id=2, name='heating tally')
+    tally2.filters = [openmc.CellFilter(cell)]
+    tally2.scores = ['heating']
+
+    model.tallies = openmc.Tallies([tally1, tally2])
+
+    sp_filename = model.run()
+
+    sp = openmc.StatePoint(sp_filename)
+
+    tally_found = sp.get_tally(filter_type=openmc.MeshFilter)
+    assert tally_found.id == 1
+
+    tally_found = sp.get_tally(filter_type=openmc.CellFilter)
+    assert tally_found.id == 2
+
+    tally_found = sp.get_tally(filters=[mesh_filter])
+    assert tally_found.id == 1
+
+    tally_found = sp.get_tally(scores=['heating'])
+    assert tally_found.id == 2
+
+    tally_found = sp.get_tally(name='heating tally')
+    assert tally_found.id == 2
+
+    tally_found = sp.get_tally(name=None)
+    assert tally_found.id == 1
+
+    tally_found = sp.get_tally(id=1)
+    assert tally_found.id == 1
+
+    tally_found = sp.get_tally(id=2)
+    assert tally_found.id == 2