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merged with upstream/develop
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Sam Shaner
commit
76ceafa449
180 changed files with 4667 additions and 4932 deletions
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@ -281,6 +281,8 @@ based on the recommended value in LA-UR-14-24530_.
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.. note:: This element is not used in the multi-group :ref:`energy_mode`.
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.. _multipole_library:
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``<multipole_library>`` Element
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-------------------------------
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@ -290,8 +292,8 @@ OpenMC can use it for on-the-fly Doppler-broadening of resolved resonance range
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cross sections. If this element is absent from the settings.xml file, the
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:envvar:`OPENMC_MULTIPOLE_LIBRARY` environment variable will be used.
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.. note:: The <use_windowed_multipole> element must also be set to "true"
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for windowed multipole functionality.
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.. note:: The :ref:`temperature_method` must also be set to "multipole" for
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windowed multipole functionality.
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``<max_order>`` Element
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---------------------------
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@ -395,19 +397,16 @@ attributes or sub-elements:
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:scatterer:
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An element with attributes/sub-elements called ``nuclide``, ``method``,
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``xs_label``, ``xs_label_0K``, ``E_min``, and ``E_max``. The ``nuclide``
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attribute is the name, as given by the ``name`` attribute within the
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``nuclide`` sub-element of the ``material`` element in ``materials.xml``,
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of the nuclide to which a resonance scattering treatment is to be applied.
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``E_min``, and ``E_max``. The ``nuclide`` attribute is the name, as given
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by the ``name`` attribute within the ``nuclide`` sub-element of the
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``material`` element in ``materials.xml``, of the nuclide to which a
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resonance scattering treatment is to be applied.
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The ``method`` attribute gives the type of resonance scattering treatment
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that is to be applied to the ``nuclide``. Acceptable inputs - none of
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which are case-sensitive - for the ``method`` attribute are ``ARES``,
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``CXS``, ``WCM``, and ``DBRC``. Descriptions of each of these methods
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are documented here_. The ``xs_label`` attribute gives the label for the
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cross section data of the ``nuclide`` at a given temperature. The
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``xs_label_0K`` gives the label for the 0 K cross section data for the
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``nuclide``. The ``E_min`` attribute gives the minimum energy above
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which the ``method`` is applied. The ``E_max`` attribute gives the
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are documented here_. The ``E_min`` attribute gives the minimum energy
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above which the ``method`` is applied. The ``E_max`` attribute gives the
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maximum energy below which the ``method`` is applied. One example would
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be as follows:
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@ -419,16 +418,12 @@ attributes or sub-elements:
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<scatterer>
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<nuclide>U-238</nuclide>
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<method>ARES</method>
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<xs_label>92238.72c</xs_label>
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<xs_label_0K>92238.00c</xs_label_0K>
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<E_min>5.0e-6</E_min>
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<E_max>40.0e-6</E_max>
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</scatterer>
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<scatterer>
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<nuclide>Pu-239</nuclide>
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<method>dbrc</method>
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<xs_label>94239.72c</xs_label>
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<xs_label_0K>94239.00c</xs_label_0K>
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<E_min>0.01e-6</E_min>
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<E_max>210.0e-6</E_max>
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</scatterer>
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@ -714,6 +709,45 @@ survival biasing, otherwise known as implicit capture or absorption.
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*Default*: false
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.. _temperature_default:
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``<temperature_default>`` Element
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---------------------------------
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The ``<temperature_default>`` element specifies a default temperature in Kelvin
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that is to be applied to cells in the absence of an explicit cell temperature or
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a material default temperature.
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*Default*: 293.6 K
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.. _temperature_method:
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``<temperature_method>`` Element
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--------------------------------
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The ``<temperature_method>`` element has an accepted value of "nearest" or
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"interpolation". A value of "nearest" indicates that for each cell, the nearest
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temperature at which cross sections are given is to be applied, within a given
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tolerance (see :ref:`temperature_tolerance`). A value of "multipole" indicates
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that the windowed multipole method should be used to evaluate
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temperature-dependent cross sections in the resolved resonance range (a
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:ref:`windowed multipole library <multipole_library>` must also be available).
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*Default*: "nearest"
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.. _temperature_tolerance:
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``<temperature_tolerance>`` Element
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-----------------------------------
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The ``<temperature_tolerance>`` element specifies a tolerance in Kelvin that is
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to be applied when the "nearest" temperature method is used. For example, if a
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cell temperature is 340 K and the tolerance is 15 K, then the closest
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temperature in the range of 325 K to 355 K will be used to evaluate cross
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sections.
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*Default*: 10 K
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``<threads>`` Element
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---------------------
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@ -1090,7 +1124,9 @@ Each ``<cell>`` element can have the following attributes or sub-elements:
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specified for the "distributed temperature" feature. This will give each
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unique instance of the cell its own temperature.
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*Default*: The temperature of the coldest nuclide in the cell's material(s)
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*Default*: If a material default temperature is supplied, it is used. In the
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absence of a material default temperature, the :ref:`global default
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temperature <temperature_default>` is used.
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:rotation:
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If the cell is filled with a universe, this element specifies the angles in
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@ -1295,6 +1331,14 @@ Each ``material`` element can have the following attributes or sub-elements:
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*Default*: ""
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:temperature:
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An element with no attributes which is used to set the default temperature
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of the material in Kelvin.
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*Default*: If a material default temperature is not given and a cell
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temperature is not specified, the :ref:`global default temperature
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<temperature_default>` is used.
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:density:
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An element with attributes/sub-elements called ``value`` and ``units``. The
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``value`` attribute is the numeric value of the density while the ``units``
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@ -1315,17 +1359,16 @@ Each ``material`` element can have the following attributes or sub-elements:
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``nuclide``, ``element``, or ``sab`` quantity.
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:nuclide:
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An element with attributes/sub-elements called ``name``, ``xs``, and ``ao``
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An element with attributes/sub-elements called ``name``, and ``ao``
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or ``wo``. The ``name`` attribute is the name of the cross-section for a
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desired nuclide while the ``xs`` attribute is the cross-section
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identifier. Finally, the ``ao`` and ``wo`` attributes specify the atom or
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desired nuclide. Finally, the ``ao`` and ``wo`` attributes specify the atom or
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weight percent of that nuclide within the material, respectively. One
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example would be as follows:
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.. code-block:: xml
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<nuclide name="H-1" xs="70c" ao="2.0" />
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<nuclide name="O-16" xs="70c" ao="1.0" />
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<nuclide name="H1" ao="2.0" />
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<nuclide name="O16" ao="1.0" />
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.. note:: If one nuclide is specified in atom percent, all others must also
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be given in atom percent. The same applies for weight percentages.
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@ -1349,11 +1392,10 @@ 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 2009`_. This element has
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attributes/sub-elements called ``name``, ``xs``, and ``ao``. The ``name``
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attribute is the atomic symbol of the element while the ``xs`` attribute is
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the cross-section identifier. Finally, the ``ao`` attribute specifies the
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atom percent of the element within the material, respectively. One example
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would be as follows:
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attributes/sub-elements called ``name``, and ``ao``. The ``name``
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attribute is the atomic symbol of the element. Finally, the ``ao``
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attribute specifies the atom percent of the element within the material,
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respectively. One example would be as follows:
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.. code-block:: xml
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@ -1383,10 +1425,9 @@ Each ``material`` element can have the following attributes or sub-elements:
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multi-group :ref:`energy_mode`.
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:sab:
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Associates an S(a,b) table with the material. This element has
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attributes/sub-elements called ``name`` and ``xs``. The ``name`` attribute
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is the name of the S(a,b) table that should be associated with the material,
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and ``xs`` is the cross-section identifier for the table.
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Associates an S(a,b) table with the material. This element has one
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attribute/sub-element called ``name``. The ``name`` attribute
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is the name of the S(a,b) table that should be associated with the material.
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*Default*: None
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@ -1397,14 +1438,13 @@ Each ``material`` element can have the following attributes or sub-elements:
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recognizes that some multi-group libraries may be providing material
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specific macroscopic cross sections instead of always providing nuclide
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specific data like in the continuous-energy case. To that end, the
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macroscopic element has attributes/sub-elements called ``name``, and ``xs``.
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macroscopic element has one attribute/sub-element called ``name``.
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The ``name`` attribute is the name of the cross-section for a
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desired nuclide while the ``xs`` attribute is the cross-section
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identifier. One example would be as follows:
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desired nuclide. One example would be as follows:
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.. code-block:: xml
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<macroscopic name="UO2" xs="71c" />
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<macroscopic name="UO2" />
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.. note:: This element is only used in the multi-group :ref:`energy_mode`.
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@ -1413,18 +1453,6 @@ Each ``material`` element can have the following attributes or sub-elements:
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.. _IUPAC Isotopic Compositions of the Elements 2009:
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http://pac.iupac.org/publications/pac/pdf/2011/pdf/8302x0397.pdf
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``<default_xs>`` Element
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------------------------
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In some circumstances, the cross-section identifier may be the same for many or
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all nuclides in a given problem. In this case, rather than specifying the
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``xs=...`` attribute on every nuclide, a ``<default_xs>`` element can be used to
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set the default cross-section identifier for any nuclide without an identifier
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explicitly listed. This element has no attributes and accepts a 3-letter string
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that indicates the default cross-section identifier, e.g. "70c".
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*Default*: None
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------------------------------------
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Tallies Specification -- tallies.xml
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------------------------------------
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