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 in | Applied radiation and isotopes Vol. 87; pp. 380 - 383 |
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Main Authors | , , , |
Format | Journal Article |
Language | English |
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England
Elsevier Ltd
01.05.2014
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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. |
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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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BackLink | https://www.ncbi.nlm.nih.gov/pubmed/24331854$$D View this record in MEDLINE/PubMed |
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CitedBy_id | crossref_primary_10_1007_s10967_016_4939_6 crossref_primary_10_1016_j_anucene_2022_109240 crossref_primary_10_1007_s10967_014_3666_0 crossref_primary_10_1016_j_apradiso_2023_110901 |
Cites_doi | 10.1063/1.3322467 10.1016/j.apradiso.2011.08.018 10.1016/j.apradiso.2004.03.032 10.1016/S0168-9002(01)02198-2 10.1016/j.apradiso.2009.11.027 10.1016/j.apradiso.2012.02.085 |
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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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