Measurement of fast reactor type neutron spectra by foil activation techniques

Abstract

Four unfolding methods are described in order to evaluate from integral activation data, the differential neutron spectrum of the fast reactor type.A simulated experiment is exccuted. In five prechosen, 16-group spectra, activation data are calculated for a series of foil detectors. Each of the unfolding methods is tested, using these activation data as input.The resulting differential spectra are compared between each other. The unfolding methods are experimentally verified. The spectra measured are the transmission of thermal reactor spectra through a 10B capsule.In the experiments standard spectra for intercalibration of detectors are used in order to eliminate the error of absolute counting and first order errors in activation cross sections.