.. _xslib_xml: ========== Xslibs.xml ========== Multigroup cross-section data could be presented both as an element of reactions.xml file and independent from ```` which filename and path are described in configure.xml. The only one common condition assumed is presence of ```` sections. ---------------------- ```` Element ---------------------- The energies stored in dictionary like manner where attribute :ng: the number of energy group is a key and values is a real type array in text section separated by blank space with size ``ng + 1``. -------------------- ```` Element -------------------- The ```` element contains data specification and `` elements :type: Define type of reaction description: by reaction-rates "rxs" or by cross-section presentation "cs" *Default*: "rxs" :ng: number of energy multigroups ------------------- ```` Element ------------------- The ```` can store energy-dependent either cross-sections or reactions rates in form of the ``ng`` values separated by blank space. :name: Name of nuclide with data :type: Type of interaction in form "(p, r)" where p is the radiation particle, r - the result of interacation. The name to take account into depletion equation should match with reaction name in ```` ``chain`` element. :ng: number of energy multigroup