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Co-Authored-By: Paul Romano <paul.k.romano@gmail.com>
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Jonathan Shimwell 2020-03-25 14:58:02 +00:00 • committed by GitHub
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2 changed files with 4 additions and 4 deletions
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4
openmc/material.py
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@ -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

4
tests/unit_tests/test_material.py
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@ -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)