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Added documentation on <natural_elements>.
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@ -182,6 +182,29 @@ performed. It has the following attributes/sub-elements:
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*Default*: None
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.. _natural_elements:
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``<natural_elements>`` Element
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------------------------------
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The ``<natural_elements>`` element indicates to OpenMC what nuclides are
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available in the cross section library when expanding an ``<element>`` into
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separate isotopes (see :ref:`material`). The accepted values are:
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- ENDF/B-VII.0
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- ENDF/B-VII.1
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- JEFF-3.1.1
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- JEFF-3.1.2
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- JEFF-3.2
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- JENDL-3.2
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- JENDL-3.3
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- JENDL-4.0
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Note that the value is case-insensitive, so "ENDF/B-VII.1" is equivalent to
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"endf/b-vii.1".
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*Default*: ENDF/B-VII.1
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``<no_reduce>`` Element
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-----------------------
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@ -741,6 +764,8 @@ sub-elements:
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Materials Specification -- materials.xml
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----------------------------------------
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.. _material:
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``<material>`` Element
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----------------------
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@ -781,7 +806,7 @@ Each ``material`` element can have the following attributes or sub-elements:
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Specifies that a natural element is present in the material. The natural
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element is split up into individual isotopes based on IUPAC Isotopic
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Compositions of the Elements 1997. This element has attributes/sub-elements
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Compositions of the Elements 2009. This element has attributes/sub-elements
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called ``name``, ``xs``, and ``ao``. The ``name`` attribute is the atomic
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symbol of the element while the ``xs`` attribute is the cross-section
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identifier. Finally, the ``ao`` attribute specifies the atom percent of the
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@ -794,6 +819,10 @@ Each ``material`` element can have the following attributes or sub-elements:
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<element name="Mn" ao="2.7426e-05" />
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<element name="Cu" ao="1.6993e-04" />
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In some cross section libraries, certain naturally occurring isotopes do not
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have cross sections. The :ref:`natural_elements` option determines how a
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natural element is split into isotopes in these cases.
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*Default*: None
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