In this paper the method of activity measurement of spent radionuclide sources (SRS) based on Co-60 and Cs-137 placed in well-type storage facilities, in order to forecast the SRS activity which can be placed at this facility is described. The distribution of the absorbed dose through the absorption material is measured with the help of the described absorption spectrometer. This information allows determining the activity of individual radionuclides with the help of mathematical methods.

You do not currently have access to this content.