Role of Accelerators in Uniform Identification of Thermal Neutrons
Control of nuclear reactors power output is centrally dependent on the level response of thermal neutrons flux as well as on their dynamic and kinetic spectra. This paper presents a set of uniform para metric properties for delayed neutrons based on accelerator experiments conducted at the Brimingham Radiation Centre. Calculations have established several patterns linking energies of accelerated incident neutrons with respect to continuous spectra of delayed neutrons, mean yield of neutrons per fission, time response of neutorn lethargy and energy spectra and delayed neutrons. Also mathematical models are secured for neutrons yeild and spectra in the time domain with respect to U235 and Pu239 material targets. Results secured in this paper are important in accelerator selectivity application as well as in the planned control of nuclear thermal reactors, for ensuring adequate compatibility between power level and reactor reactivity trajectories.