8. Cross-sections

Total availiable amount of nuclides with cross-section data are restricted especially for neutron induced depletion with a large amout of fission products. But for calcualtion with a number of materials when cross-section data are repeated is more comfortable to store arrays in independent libriaries. Description of externals paths are provided in Configuration in the section <impxslibs>. Number of external libraries are not restricted:

<impxslibs>
<impxslib>/pathto/implib.xml</impxslib>
</impxslibs>

The structure of implib.xml is identicall to xslibs section of composition file. The minimun information is energy discrization and <xslibs> section with attribute <type> means cross-section data if equal cs or reaction rates with rx attribute value.

<xslibs ng="4" type="cs">
<energy ng="4">0.0252 0.215 0.465 1.0 2.15</energy>
<xslib name="Cm245" ng="4" reaction="fission">376.3989 237.6379 217.4472 273.0525<xslib>
</xslibs>