Method for the Determination of Neutron Field Monitor Burnup Effects by Gamma-spectrometry

Abstract

A methodological concept is developed to determine the burnup of certain neutron flux monitors in an unknown, intense reactor neutron field. In particular, it is shown how to evaluate the burnup effects involved in the neutron activation of ¹⁹⁷ Au prior to any neutron flux characterisation, based merely on the spectrometry of the ¹⁹⁸ Au and ¹⁹⁹ Au decay gamma rays. Such independent detection method of the burnup factor allows a principally correct evaluation of the specific count rate of the irradiated monitor, which serves as a basic input for the determination of neutron field parameters.