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dc.contributor.authorTemba, Eliane Silvia Codo-
dc.contributor.authorKastner, Geraldo Frederico-
dc.contributor.authorReis Júnior, Aluísio Souza-
dc.contributor.authorMonteiro, Roberto Pelaccani Guedes-
dc.contributor.authorMoreira, Rubens Martins-
dc.date.accessioned2018-01-15T17:05:28Z-
dc.date.available2018-01-15T17:05:28Z-
dc.date.issued2017-
dc.identifier.citationTEMBA , Eliane S. C. ; KASTNER, Geraldo F. ; REIS JR, Aluísio S.; MONTEIRO, Roberto P. G.; MOREIRA, Rubens M. Determination of 94Nb in radioactive wastes using extraction chromatography and gamma spectrometry. Journal of Radioanalytical and Nuclear Chemistry, v. 311, n. 3, p. 1627–1631, 2017.pt_BR
dc.identifier.issn0236-5731pt_BR
dc.identifier.urihttp://www.repositorio.cdtn.br:8080/jspui/handle/123456789/1226-
dc.description.abstractA radiochemical methodology for the determination of 94nb in low-level radioactive wastes from nuclear power plant was proposed. Although 94Nb is a strong gamma emitter, its concentration in radioactive waste samples is usually several orders of magnitude lower than that of other β–γ emitters, whose emissions interferes in the detection of the emission lines of 94Nb. The procedure involves acid digestion, precipitation, cation exchange chromatography by using Amberlite IRA120 resin, extraction chromatography by using TEVA resin to isolate the Nb and the gamma spectrometry to its measurement. The chemical yield was 70% in average. Samples of evaporator concentrate and spent resin were analyzed. For the samples of the evaporator concentrate, the results obtained were below L D = 9.59 × 10−4 Bq g−1. For the spent resin an average result of 1.54 × 102 Bq g−1 was obtained.pt_BR
dc.format.extent1627–1631pt_BR
dc.language.isoen_USpt_BR
dc.rightsLpt_BR
dc.subjectNiobiumpt_BR
dc.subjectTEVA resinpt_BR
dc.subjectRadioactive wastespt_BR
dc.subjectExtractionpt_BR
dc.subjectchromatographypt_BR
dc.subjectGamma spectrometrypt_BR
dc.titleDetermination of 94Nb in radioactive wastes using extraction chromatography and gamma spectrometrypt_BR
dc.typeArtigo Periódicopt_BR
dc.coverageIpt_BR
dc.creator.affiliationCentro de Desenvolvimento da Tecnologia Nuclear/CDTN, Belo Horizonte, MG, Brasil.pt_BR
dc.identifier.vol311pt_BR
dc.title.journalJournal of Radioanalytical and Nuclear Chemistrypt_BR
Appears in Collections:Artigo de periódico



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