Comparison of Real and Generated by MCNP Simulation Spectrums for Validation of Neutron Activation Calculations

The objective for decommissioning planning, is to obtain a radiological understanding of the involved installation. characterization at this stage could be carried out by means of: (a) neutron activation calculations based on reactor design and flux; (b) dose rate measurements; (c) in-situ gamma spectrometry; (d) sampling determination scaling factors in activated contaminated components.Neutron contains several uncertainties. These uncertainties are input data - such as material (composition impurities), flux energy, nuclear libraries methodology process simulation codes.Taking into consideration all these modeling uncertainties, work focused development technique validation calculations. A non-destructive spectrometry using MCNP6 simulations under interpretation resulting gamma-ray spectra radionuclides components. In particular, spectrum will produced, activities main component results simulations. This compared with experimental spectrum.Furthermore, components, which appeared surface contamination, essential decision making during decommissioning. cutting techniques followed order reduce production secondary waste limit doses personnel selection decontamination should accurate inside and/ or contamination. proposed method also helpful case. components determined comparing that produced simulations, arisen from measurements.