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Co-Authored-By: Paul Romano <paul.k.romano@gmail.com>
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@ -149,8 +149,8 @@ In OpenMC it is possible to mix any number of materials to create a new material
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with the correct nuclide composition and density. The
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:meth:`Material.mix_materials` method takes a list of materials and
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a list of their mixing fractions. Mixing fractions can be provided as atomic
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fractions, weight fractions or volume fractions. The fraction type
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is specifed by adding 'ao', 'wo' or 'vo' respectively as the third argument.
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fractions, weight fractions, or volume fractions. The fraction type
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can be specified by passing 'ao', 'wo', or 'vo' as the third argument, respectively.
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For example, assuming the required materials have already been defined, a MOX
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material with 3% plutonium oxide by weight could be created using the following:
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@ -465,7 +465,7 @@
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"cell_type": "markdown",
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"metadata": {},
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"source": [
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"The 'wo' argument in the `mix_materials()` method specifies that the fractions are weight fractions. Materials can also be mixed by atomic and volume fractions with 'ao' and 'vo' respectively. For 'ao' and 'wo' the fractions must sum to one. For 'vo' if fractions do not sum to one, the remaining fraction is set as void."
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"The 'wo' argument in the `mix_materials()` method specifies that the fractions are weight fractions. Materials can also be mixed by atomic and volume fractions with 'ao' and 'vo', respectively. For 'ao' and 'wo' the fractions must sum to one. For 'vo', if fractions do not sum to one, the remaining fraction is set as void."
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]
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},
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{
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