Non-Destructive Assay of Nuclide Composition in Spent Fuel Assemblies from a Research Reactor by Repeat Irradiation and Gamma-Spectrometric Measurement

This paper presents a method for the experimental determination of reactor. The method is based on a repeat short-term irradiation of the spent fuel assembly followed by measurement of gamma-radiation spectra. The paper describes the experiments carried out with spent fuel assemblies from the research reactor IRT-MEPhI. The results obtained in the measurements and an analysis of experimental errors are presented. Based on the results obtained it is concluded that the proposed method is superior to other non-destructive methodologies both in accuracy and the scope of information available about the nuclide composition of spent fuel. 235U, 236U, 237Np, and 238U content in spent fuel of a research