Measurement of dosimetrical cross sections with 14.05 MeV neutrons from compact neutron generator.

• Measurement of reaction rates in compact DT generator. • Calculation of neutron flux in targets around compact DT generator. • Determination of DD neutrons in compact DT generator. • Testing of IRDFF-II cross sections in 14.05 MeV neutrons. This paper deals with the measurement of the differential dosimetry cross sections using a small compact D-T neutron generator with 14.05 ± 0.08 MeV neutron emission (1 × 108 n/s into 4π). In spite of low neutron flux, it is possible to get measurable gamma-ray activities by irradiating a larger amount of target material placed in close geometry. 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. It is worth noting that the mean standard deviation in IRDFF-II library is about 4 %, while in the case of other data libraries they are from 5.5 % to 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. [ABSTRACT FROM AUTHOR]