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Co-Authored-By: Paul Romano <paul.k.romano@gmail.com>
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docs/source/usersguide/materials.rst
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@ -149,8 +149,8 @@ In OpenMC it is possible to mix any number of materials to create a new material
with the correct nuclide composition and density. The
:meth:`Material.mix_materials` method takes a list of materials and
a list of their mixing fractions. Mixing fractions can be provided as atomic
fractions, weight fractions or volume fractions. The fraction type
is specifed by adding 'ao', 'wo' or 'vo' respectively as the third argument.
fractions, weight fractions, or volume fractions. The fraction type
can be specified by passing 'ao', 'wo', or 'vo' as the third argument, respectively.
For example, assuming the required materials have already been defined, a MOX
material with 3% plutonium oxide by weight could be created using the following: