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Dosimetry cross sections are fundamental quantities necessary for neutrondosimetry using the neutron activation method. It is worth noting that theuncertainty in cross sections is the major source of uncertainty incalculational predictions using nuclear data in simulations thus, cross sectionvalidation is a key issue in any aims for refinement of any predictions. Asmall compact neutron generator is a promising tool for performing integralexperiments and even for differential experiments. This paper deals with themeasurement of the differential dosimetry cross sections using a small compactD-T neutron generator with 14.05 MeV neutron emission (10E8 n/s into 4pi).Achieving measurable activation at such a low flux field is allowed by using alarger amount of activation material placed in close measurement geometryduring decay gamma measurement. The experimentally determined cross sectionsare in good agreement with the cross sections in the IRDFF-II dosimetrylibrary. The comparison with other nuclear data libraries was performed aswell. Its worth noting, the mean standard deviation in IRDFF-II library isabout 4 %, while in case of other data libraries they are from 5.5 % - 7.5 %.This result can be understood as a validation of IRDFF-II using 14.05 MeVneutrons and also a confirmation of the applicability of small compactgenerators in the measurement of activation cross sections.

Measurement of Dosimetrical Cross Sections with 14.05 MeV Neutrons From Compact Neutron Generator