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Added section to user guide on Mixing materials.

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Sam Powell-Gill 2020-03-03 10:53:02 +00:00
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docs/source/usersguide/materials.rst
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@ -141,6 +141,34 @@ attribute, e.g.,
:attr:`Material.temperature` or :attr:`Cell.temperature`
attributes, respectively.
-----------------
Material Mixtures
-----------------
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.
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:
::
mox = openmc.Material()
mox.mix_materials([uo2, puo2], [0.97, 0.03], 'wo')
It should be noted that if mixing fractions are specifed as atomic or weight
fractions, the sum of the given fractions should be one. If volume fractions
are provided and the sum fractions is less than one, the remaining fraction is
set as void material.
.. warning:: Materials with :math:`S(\alpha,\beta)` thermal scattering data
cannot be used in :meth:`Material.mix_materials`. However, thermal
scattering data can be added to a material created by
:meth:`Material.mix_materials`.
--------------------
Material Collections
--------------------