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Add missing suggestion by @paulromano

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This commit is contained in:
Mikolaj Adam Kowalski 2020-03-19 16:08:42 +00:00
parent 671c902350
commit 9c8e22add8
1 changed files with 4 additions and 2 deletions
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6
docs/source/usersguide/geometry.rst
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@ -185,8 +185,10 @@ the :class:`openmc.Cell` class::
In this example, an instance of :class:`openmc.Material` is assigned to the
:attr:`Cell.fill` attribute. One can also fill a cell with a :ref:`universe
<usersguide_universes>` or :ref:`lattice <usersguide_lattices>`. If no fill
is provided to a cell, it will be filled with void by default::
<usersguide_universes>` or :ref:`lattice <usersguide_lattices>`. If you provide
no fill to a cell or assign a value of `None`, it will be treated as a "void"
cell with no material within. Particles are allowed to stream through the cell but
will undergo no collisions::
# This cell will be filled with void on export to XML
gap = openmc.Cell(region=pellet_gap)