  Dosimetry cross sections are fundamental quantities necessary for neutron
dosimetry using the neutron activation method. It is worth noting that the
uncertainty in cross sections is the major source of uncertainty in
calculational predictions using nuclear data in simulations thus, cross section
validation is a key issue in any aims for refinement of any predictions. A
small compact neutron generator is a promising tool for performing integral
experiments and even for differential experiments. This paper deals with the
measurement of the differential dosimetry cross sections using a small compact
D-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 a
larger amount of activation material placed in close measurement geometry
during decay gamma measurement. The experimentally determined cross sections
are in good agreement with the cross sections in the IRDFF-II dosimetry
library. The comparison with other nuclear data libraries was performed as
well. Its worth noting, the mean standard deviation in IRDFF-II library is
about 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 MeV
neutrons and also a confirmation of the applicability of small compact
generators in the measurement of activation cross sections.
