Gamma-ray spectrometry method used for radioactive waste drums characterization for final disposal at National Repository for Low and Intermediate Radioactive Waste – Baita, Romania

• An equivalent matrix of a 100 l radwaste cemented in a 200 l drum was measured.
• Vertical channels for hosting standard sources were drilled in the concrete matrix.
• Drum was measured with 152Eu sources placed in different configurations in channels.
• Activity was calculated assuming a homogeneous radioactive matrix.
• For photons with E>444 keV computed activity is relatively close to certified value.

The Radioactive Waste Management Department from IFIN-HH, Bucharest, performs the conditioning of the institutional radioactive waste in concrete matrix, in 200 l drums with concrete shield, for final disposal at DNDR – Baita, Bihor county, in an old exhausted uranium mine. This paper presents a gamma-ray spectrometry method for the characterization of the radioactive waste drums' radionuclides content, for final disposal. In order to study the accuracy of the method, a similar concrete matrix with Portland cement in a 200 l drum was used.