Abstract
This paper presents preliminary integral cross section data recently measured at the ASP 14 MeV neutron irradiation facility. Reaction cross sections were derived from neutron activated elemental foils following measurement of resulting activation product gamma emissions as a function of time and energy using a HPGe detector, with associated signal processing and data post processing tools. Selected measurements are compared with facility spectrum-averaged cross sections, calculated using the latest release of the FISPACT-II inventory code and TENDL-2011 groupwise cross section data. Examples are shown as plots of the C/E ratio. Measurements are compared with integral data derived from other neutron irradiation facilities. Together, with differential cross section measurements taken from the EXFOR database maintained by the IAEA, we briefly highlight how C/E plots contribute to validation and improvement of activation libraries.
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