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corrected isotope names, removed -
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shimwell committed Apr 19, 2024
1 parent c06c36e commit a656ea5
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68 changes: 34 additions & 34 deletions src/neutronics_material_maker/data/pnnl_materials.json
Original file line number Diff line number Diff line change
Expand Up @@ -4911,9 +4911,9 @@
"percent_type": "ao",
"comment": "https://www.pnnl.gov/main/publications/external/technical_reports/PNNL-15870Rev2.pdf",
"isotopes": {
"U-234": 5.085502186733834e-06,
"U-235": 0.002531900683843523,
"U-238": 0.9974630138139697
"U234": 5.085502186733834e-06,
"U235": 0.002531900683843523,
"U238": 0.9974630138139697
}
},
"Uranium, Enriched, Typical Commercial": {
Expand All @@ -4922,9 +4922,9 @@
"percent_type": "ao",
"comment": "https://www.pnnl.gov/main/publications/external/technical_reports/PNNL-15870Rev2.pdf",
"isotopes": {
"U-234": 0.0003101065341391381,
"U-235": 0.029967161284771438,
"U-238": 0.9697227321810894
"U234": 0.0003101065341391381,
"U235": 0.029967161284771438,
"U238": 0.9697227321810894
}
},
"Uranium, HEU, Health Physics Society": {
Expand All @@ -4933,10 +4933,10 @@
"percent_type": "ao",
"comment": "https://www.pnnl.gov/main/publications/external/technical_reports/PNNL-15870Rev2.pdf",
"isotopes": {
"U-234": 0.010582182219656016,
"U-235": 0.9323616914686151,
"U-236": 0.002052627251378336,
"U-238": 0.05500349906035039
"U234": 0.010582182219656016,
"U235": 0.9323616914686151,
"U236": 0.002052627251378336,
"U238": 0.05500349906035039
}
},
"Uranium, HEU, Russian Average": {
Expand All @@ -4945,10 +4945,10 @@
"percent_type": "ao",
"comment": "https://www.pnnl.gov/main/publications/external/technical_reports/PNNL-15870Rev2.pdf",
"isotopes": {
"U-234": 0.009722065226720615,
"U-235": 0.8989824415853601,
"U-236": 0.0037979831861608107,
"U-238": 0.08749751000175858
"U234": 0.009722065226720615,
"U235": 0.8989824415853601,
"U236": 0.0037979831861608107,
"U238": 0.08749751000175858
}
},
"Uranium, HEU, US Average": {
Expand All @@ -4957,10 +4957,10 @@
"percent_type": "ao",
"comment": "https://www.pnnl.gov/main/publications/external/technical_reports/PNNL-15870Rev2.pdf",
"isotopes": {
"U-234": 0.009848508306917338,
"U-235": 0.9321662318993514,
"U-236": 0.004483868829572206,
"U-238": 0.05350139096415908
"U234": 0.009848508306917338,
"U235": 0.9321662318993514,
"U236": 0.004483868829572206,
"U238": 0.05350139096415908
}
},
"Uranium, Low Enriched (LEU)": {
Expand All @@ -4969,10 +4969,10 @@
"percent_type": "ao",
"comment": "https://www.pnnl.gov/main/publications/external/technical_reports/PNNL-15870Rev2.pdf",
"isotopes": {
"U-234": 0.0002714687801617951,
"U-235": 0.03037195174141948,
"U-236": 0.0001391181270638639,
"U-238": 0.9692174613513548
"U234": 0.0002714687801617951,
"U235": 0.03037195174141948,
"U236": 0.0001391181270638639,
"U238": 0.9692174613513548
}
},
"Uranium, Natural (NU)": {
Expand All @@ -4981,9 +4981,9 @@
"percent_type": "ao",
"comment": "https://www.pnnl.gov/main/publications/external/technical_reports/PNNL-15870Rev2.pdf",
"isotopes": {
"U-234": 5.797118485704071e-05,
"U-235": 0.007295479504390431,
"U-238": 0.9926465493107526
"U234": 5.797118485704071e-05,
"U235": 0.007295479504390431,
"U238": 0.9926465493107526
}
},
"Uranium-Plutonium, Mixed Oxide (MOX)": {
Expand All @@ -4995,15 +4995,15 @@
"O": 0.666666
},
"isotopes": {
"Pu-238": 0.0003895015879848798,
"Pu-239": 0.008486551573364549,
"Pu-240": 0.0040324454812675995,
"Pu-241": 0.0014616410522738021,
"Pu-242": 0.0011031849547918496,
"U-234": 3.847219596060759e-06,
"U-235": 0.0008047904974259019,
"U-236": 0,
"U-238": 0.31705161553032307
"Pu238": 0.0003895015879848798,
"Pu239": 0.008486551573364549,
"Pu240": 0.0040324454812675995,
"Pu241": 0.0014616410522738021,
"Pu242": 0.0011031849547918496,
"U234": 3.847219596060759e-06,
"U235": 0.0008047904974259019,
"U236": 0,
"U238": 0.31705161553032307
}
},
"Uranyl Fluoride": {
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4 changes: 2 additions & 2 deletions src/neutronics_material_maker/material.py
Original file line number Diff line number Diff line change
Expand Up @@ -610,8 +610,8 @@ def volume_in_cm3(self, value):

def _make_openmc_material(self):
"""Makes an openmc.Material() object that is used to make other
material tpyes (e.g. Serpent, MCNP, Shift, Fispact). If elements are
specified then makes material using natural adundances of isotopes.
material types (e.g. Serpent, MCNP, Shift, Fispact). If elements are
specified then makes material using natural abundances of isotopes.
This is slightly different to the native openmc method that uses
isotopes available in the cross_sections.xml file"""

Expand Down
2 changes: 1 addition & 1 deletion tests/test_utils.py
Original file line number Diff line number Diff line change
Expand Up @@ -195,7 +195,7 @@ def test_isotope_to_zaid(self):
def test_entries_from_each_json_file_get_into_the_internal_dict(self):
all_mats = nmm.AvailableMaterials().keys()

assert "A-150 Tissue-Equivalent Plastic (A150TEP)" in all_mats
assert "A-150 Tissue-Equivalent Plastic" in all_mats
assert "Zirconium Hydride (ZrH2)" in all_mats
assert "Pb842Li158" in all_mats
assert "FLiNaBe" in all_mats
Expand Down

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