Deconvolution of neutron spectrum for a DT neutron generator based on a combination of activation method, unfolding processes and numerical simulations

Abstract

Abstract Neutron generators (NGs) are available worldwide as powerful sources of neutrons suitable for a variety of applications. However, information concerning precise knowledge of the total neutron emission Yn and its energy distribution is not always provided by the manufacturer. Measurements using energy threshold diagnostics and numerical simulations may be used to determine such quantities. Here we describe our approach for neutron spectra determination of a SODERN DT NG based on combination of activation measurements, unfolding processes and numerical simulations using the FISPACT-II code. We have used these to estimate a priori neutron spectra, which have been applied as an input to unfolding codes, Gravel and MAXED. Various input values of deconvolution parameters have been investigated in this paper and results are discussed. The final reconstructed neutron spectrum of the DT NG has been derived from a combination of spectra obtained from these codes, with agreement with experimental data to within 10 %.