Combined determination of 99Tc and 108mAg in L/ILW liquid wastes

The low- and intermediate-activity level liquid wastes produced by the Paks Nuclear Power Plant (NPP) contain routinely measureable gamma-emitting (e.g., 54 Mn, 60 Co, 110m Ag, and 137 Cs) as well as many so-called “difficult-to-measure” radionuclides. Despite of their low specific activity compared...

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Published inJournal of radioanalytical and nuclear chemistry Vol. 286; no. 3; pp. 759 - 763
Main Authors Bihari, Arpad, Szucs, Zoltan, Mogyorosi, Magdolna, Pinter, Tamas
Format Journal Article
LanguageEnglish
Published Dordrecht Springer Netherlands 01.12.2010
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Summary:The low- and intermediate-activity level liquid wastes produced by the Paks Nuclear Power Plant (NPP) contain routinely measureable gamma-emitting (e.g., 54 Mn, 60 Co, 110m Ag, and 137 Cs) as well as many so-called “difficult-to-measure” radionuclides. Despite of their low specific activity compared to the total, the reliable determination of these radionuclides is an important issue of nuclear waste management. The increasing amount of waste samples to be qualified yearly by our laboratory put a pressure on revising the existing procedure of 99 Tc separation applied. We have managed to halve the initial amount of the sample required to achieve the same level of detection of technetium. Furthermore, one of the new purifying steps introduced have proved to be able to separate 108m Ag (and 110m Ag) better than 99% keeping the 99 Tc content of the product almost intact. Means of separation of 99 Tc from 106 Ru and 124+125 Sb have also been successfully investigated. As intended, this new procedure has a major impact on the chemical reagent as well as the electricity requirement of the separation making it more cost-effective.
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ISSN:0236-5731
1588-2780
DOI:10.1007/s10967-010-0718-y