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Home » Archive of journals » 2021, ¹ 3 (16) » Approaches to Graphite Block Characterization by Gamma Radionuclides and their Packaging During UGR Stack Dismantlement

APPROACHES TO GRAPHITE BLOCK CHARACTERIZATION BY GAMMA RADIONUCLIDES AND THEIR PACKAGING DURING UGR STACK DISMANTLEMENT

JOURNAL: 2021, ¹ 3 (16), p. 30-43

AUTHORS: A.O. Paviluk, S.G. Kotlyarevskij, R.I. Kan, A.G. Volkova, E.V. Zakharova, Å.A. Komarov

ANNOTATION:
This paper presents technical and methodological approaches developed by PDC UGR to characterize the removed graphite blocks by gamma-emitting radionuclides during graphite stack dismantlement and to enable their packaging. It overviews the experimental testing of the characterization method and its findings. It also presents container design option allowing to achieve the maximum filling efficiency.
 
Keywords: radioactive waste, irradiated graphite, non-destructive testing method, characterization, packaging.

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Pavliuk À. Î., Kotlyarevsky S. G., Kan R. I., Volkova À. G., Zakcharova E. V., Komarov Å. À. Approaches to graphite block characterization by gamma radionuclides and their packaging during UGR stack dismantlement. Radioactive Waste, 2021, no. 3 (16), pp. 30—43. DOI: 10.25283/2587-9707-2021-3-30-43.
(In Russian).


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