Radiochemical analysis of concrete samples from accelerator waste
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Dorothea Schumann
, Daniela Kiselev , Sabine Teichmann , Hans-Arno Synal and Peter Kubik
Abstract
For the decommissioning and disposal of shielding concrete from accelerator facilities, the Swiss Authorities require information on the radionuclide inventory. Besides the easy-to-measure γ-emitters 152Eu, 60Co, 44Sc, 133Ba, 154Eu, 134Cs, 144Ce, 22Na, also long-lived radionuclides emitting α- or β-radiation like 129I, 10Be, 36Cl, 239/240Pu and 238U have to be studied in order to obtain an overview to which extent they are produced and whether they represent a safety issue. In this study, we present the chemical separation and determination of selected radionuclides in shielding concrete from two different positions in the accelerator facilities at the Paul Scherrer Institute (PSI), the BX2 station, which was shut down in 1998, and the environment of the target M station, where the samples were taken in 1985 during reconstruction. The results of the measurements show that in no case the radionuclide content represents a safety risk. The components can be decommissioned corresponding to the Swiss safety regulations.
© by Oldenbourg Wissenschaftsverlag, München, Germany
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Articles in the same Issue
- The influence of f-elements' oxidizing potential and ion charge on their stability in aqueous alkaline solution
- Adjustment of valence state of Pu and Np in nitric solution containing N,N-dimethylhydroxylamine and monomethylhydrazine by electrolysis
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- Adsorption of tetravalent thorium by geomedia
- Studies on biosorption of Cr(VI) on a green resin: dry cow dung powder and tracer technique
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- Radiochemical analysis of concrete samples from accelerator waste
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- Production and separation of no-carrier-added 73As and 75Se from 7Li irradiated germanium oxide target