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

The Radioactive Waste Management Department from IFIN-HH, Bucharest, performs the conditioning of the institutional radioactive waste in concrete matrix, in 200l drums with concrete shield, for final disposal at DNDR – Baita, Bihor county, in an old exhausted uranium mine. This paper presents a gamm...

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Published inApplied radiation and isotopes Vol. 87; pp. 380 - 383
Main Authors Done, L., Tugulan, L.C., Dragolici, F., Alexandru, C.
Format Journal Article
LanguageEnglish
Published England Elsevier Ltd 01.05.2014
Subjects
Gamma-ray spectrometry
Radioactive matrix
Radioactive waste characterization
Romania, Bucharest
Radioactive waste characterization
Gamma-ray spectrometry
Radioactive matrix
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Abstract The Radioactive Waste Management Department from IFIN-HH, Bucharest, performs the conditioning of the institutional radioactive waste in concrete matrix, in 200l 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 200l drum was used. •An equivalent matrix of a 100l radwaste cemented in a 200l 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>444keV computed activity is relatively close to certified value.
AbstractList The Radioactive Waste Management Department from IFIN-HH, Bucharest, performs the conditioning of the institutional radioactive waste in concrete matrix, in 200l 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 200l drum was used. •An equivalent matrix of a 100l radwaste cemented in a 200l 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>444keV 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.
Author Dragolici, F.
Alexandru, C.
Done, L.
Tugulan, L.C.
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Keywords Radioactive waste characterization
Gamma-ray spectrometry
Radioactive matrix
Language English
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Radioactive waste characterization
Title Gamma-ray spectrometry method used for radioactive waste drums characterization for final disposal at National Repository for Low and Intermediate Radioactive Waste – Baita, Romania
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