Add tests for from_xml methods

openmc/material.py

@@ -936,14 +936,6 @@ class Material(IDManagerMixin):
             elif 'wo' in nuclide.attrib:
                 mat.add_nuclide(name, float(nuclide.attrib['wo']), 'wo')
 
-        # Get each element
-        for element in elem.findall('element'):
-            name = element.attrib['name']
-            if 'ao' in element.attrib:
-                mat.add_element(name, float(element.attrib['ao']))
-            elif 'wo' in element.attrib:
-                mat.add_element(name, float(element.attrib['wo']), 'wo')
-
         # Get each S(a,b) table
         for sab in elem.findall('sab'):
             fraction = float(sab.get('fraction', 1.0))

tests/unit_tests/conftest.py

@@ -60,3 +60,54 @@ def cell_with_lattice():
     return ([inside_cyl, outside_cyl, main_cell],
             [m_inside[0], m_inside[1], m_inside[3], m_outside],
             univ, lattice)
+
+@pytest.fixture
+def mixed_lattice_model(uo2, water):
+    cyl = openmc.ZCylinder(R=0.4)
+    c1 = openmc.Cell(fill=uo2, region=-cyl)
+    c1.temperature = 600.0
+    c2 = openmc.Cell(fill=water, region=+cyl)
+    pin = openmc.Universe(cells=[c1, c2])
+
+    empty = openmc.Cell()
+    empty_univ = openmc.Universe(cells=[empty])
+
+    hex_lattice = openmc.HexLattice()
+    hex_lattice.center = (0.0, 0.0)
+    hex_lattice.pitch = (1.2, 10.0)
+    outer_ring = [pin]*6
+    inner_ring = [empty_univ]
+    axial_level = [outer_ring, inner_ring]
+    hex_lattice.universes = [axial_level]*3
+    hex_lattice.outer = empty_univ
+
+    cell_hex = openmc.Cell(fill=hex_lattice)
+    u = openmc.Universe(cells=[cell_hex])
+    rotated_cell_hex = openmc.Cell(fill=u)
+    rotated_cell_hex.rotation = (0., 0., 30.)
+    ur = openmc.Universe(cells=[rotated_cell_hex])
+
+    d = 6.0
+    rect_lattice = openmc.RectLattice()
+    rect_lattice.lower_left = (-d, -d)
+    rect_lattice.pitch = (d, d)
+    rect_lattice.outer = empty_univ
+    rect_lattice.universes = [
+        [ur, empty_univ],
+        [empty_univ, u]
+    ]
+
+    xmin = openmc.XPlane(x0=-d, boundary_type='periodic')
+    xmax = openmc.XPlane(x0=d, boundary_type='periodic')
+    xmin.periodic_surface = xmax
+    ymin = openmc.YPlane(y0=-d, boundary_type='periodic')
+    ymax = openmc.YPlane(y0=d, boundary_type='periodic')
+    main_cell = openmc.Cell(fill=rect_lattice,
+                            region=+xmin & -xmax & +ymin & -ymax)
+
+    # Create geometry and use unique material in each fuel cell
+    geometry = openmc.Geometry([main_cell])
+    geometry.determine_paths()
+    c1.fill = [water.clone() for i in range(c1.num_instances)]
+
+    return openmc.model.Model(geometry)

tests/unit_tests/test_geometry.py

@@ -244,3 +244,14 @@ def test_determine_paths(cell_with_lattice):
     for i in range(4):
         assert geom.get_instances(cells[0].paths[i]) == i
         assert geom.get_instances(mats[-1].paths[i]) == i
+
+def test_from_xml(run_in_tmpdir, mixed_lattice_model):
+    # Export model
+    mixed_lattice_model.export_to_xml()
+
+    # Import geometry
+    geom = openmc.Geometry.from_xml()
+    assert isinstance(geom, openmc.Geometry)
+    ll, ur = geom.bounding_box
+    assert ll == pytest.approx((-6.0, -6.0, -np.inf))
+    assert ur == pytest.approx((6.0, 6.0, np.inf))

tests/unit_tests/test_material.py

@@ -182,3 +182,37 @@ def test_borated_water():
     # Test the density override
     m = openmc.model.borated_water(975, 566.5, 15.51, density=0.9)
     assert m.density == pytest.approx(0.9, 1e-3)
+
+
+def test_from_xml(run_in_tmpdir):
+    # Create a materials.xml file
+    m1 = openmc.Material(1, 'water')
+    m1.add_nuclide('H1', 1.0)
+    m1.add_nuclide('O16', 2.0)
+    m1.add_s_alpha_beta('c_H_in_H2O')
+    m1.set_density('g/cm3', 0.9)
+    m1.isotropic = ['H1']
+    m2 = openmc.Material(2, 'zirc')
+    m2.add_nuclide('Zr90', 1.0, 'wo')
+    m2.set_density('kg/m3', 10.0)
+    m3 = openmc.Material(3)
+    m3.add_nuclide('N14', 0.02)
+
+    mats = openmc.Materials([m1, m2, m3])
+    mats.cross_sections = 'fake_path.xml'
+    mats.multipole_library = 'fake_multipole/'
+    mats.export_to_xml()
+
+    # Regenerate materials from XML
+    mats = openmc.Materials.from_xml()
+    assert len(mats) == 3
+    m1 = mats[0]
+    assert m1.id == 1
+    assert m1.name == 'water'
+    assert m1.nuclides == [('H1', 1.0, 'ao'), ('O16', 2.0, 'ao')]
+    assert m1.isotropic == ['H1']
+    m2 = mats[1]
+    assert m2.nuclides == [('Zr90', 1.0, 'wo')]
+    assert m2.density == 10.0
+    assert m2.density_units == 'kg/m3'
+    assert mats[2].density_units == 'sum'