Optimization of a new radiochemical method based on extraction chromatographic resins and plastic scintillation for measurement of <sup>90</sup>Sr in nuclear waste
A purification method is developed to determine <sup>90</sup>Sr in radioactive waste. A separation based on Sr-resin® with a pretreatment using TRU-resin® provides satisfactory Sr recovery yields before the <sup>90</sup>Sr measurement by liquid...
| Autores: | , , , , , , |
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| Formato: | artículo |
| Estado: | Versión aceptada para publicación |
| Fecha de publicación: | 2024 |
| País: | España |
| Recursos: | Universidad de Barcelona |
| Repositorio: | Dipòsit Digital de la UB |
| OAI Identifier: | oai:dnet:ubarcelona__::62e7e4a99471d72cc6c89d89230ec2b2 |
| Acesso em linha: | https://hdl.handle.net/2445/229378 |
| Access Level: | acceso abierto |
| Palavra-chave: | Estronci Anàlisi radioquímica Residus radioactius Strontium Radiochemical analysis Radioactive wastes |
| Resumo: | A purification method is developed to determine <sup>90</sup>Sr in radioactive waste. A separation based on Sr-resin® with a pretreatment using TRU-resin® provides satisfactory Sr recovery yields before the <sup>90</sup>Sr measurement by liquid scintillation counting (LSC) regardless the analyzed samples with low or high activity level. The selectivity of the procedure is checked by measuring the 90Y ingrowth after different days of separation without waiting for secular equilibrium. In order to obtain a REACH compliant method without scintillation cocktails, a plastic scintillation resin selective for Sr is implemented on the basis of the developed protocol. The optimized method is applied successfully to representative nuclear waste including samples with high Pu content (effluents, concretes and sludges). |
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