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tidy up format
1 parent 9037d53 commit 8855e6b

2 files changed

Lines changed: 4 additions & 4 deletions

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openmc/deplete/material_depletion.py

Lines changed: 1 addition & 1 deletion
Original file line numberDiff line numberDiff line change
@@ -91,7 +91,7 @@ def deplete_materials(
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Returns
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-------
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Sequence[openmc.Materials]
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Sequence[openmc.Materials] a list of openmc.Materials containing depleted materials
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"""
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tests/unit_tests/test_deplete_material_deplete.py

Lines changed: 3 additions & 3 deletions
Original file line numberDiff line numberDiff line change
@@ -10,8 +10,6 @@
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def test_deplete_materials():
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# Ensure the OpenMC data directory is set
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openmc.data.data_directory = "data"
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mat_ni58 = openmc.Material()
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mat_ni58.add_nuclide("Ni58", 0.95)
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mat_ni58.set_density("g/cm3", 7.87)
@@ -48,7 +46,6 @@ def test_deplete_materials():
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],
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timestep_units="s",
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chain_file=Path(__file__).parents[1] / "chain_ni.xml",
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# nuclides=["Ni56", "Ni60"], # limit to two nuclides to speed up the test
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reactions=None,
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)
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@@ -108,6 +105,7 @@ def test_deplete_materials_error_handling():
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)
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mat_ni.volume = 1.0
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with pytest.raises(
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RuntimeError, match="No depletable materials were found in the model"
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):
@@ -118,6 +116,7 @@ def test_deplete_materials_error_handling():
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reactions=None,
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)
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mat_ni.depletable = True
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with pytest.raises(ValueError, match="Number of time steps"):
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deplete_materials(
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activation_data=[
@@ -133,6 +132,7 @@ def test_deplete_materials_error_handling():
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chain_file=Path(__file__).parents[1] / "chain_ni.xml",
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reactions=None,
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)
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with pytest.raises(ValueError, match="Length of flux array should be"):
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deplete_materials(
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activation_data=[

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