SABINE NEUSATZ GUILHEN

Resumo

Possui graduaĆ§Ć£o em QuĆ­mica com atribuiƧƵes TecnolĆ³gicas e BiotecnolĆ³gicas pelo Instituto de QuĆ­mica da Universidade de SĆ£o Paulo (2005), mestrado (2009) e doutorado (2018) em Tecnologia Nuclear (Materiais) pelo Instituto de Pesquisas EnergĆ©ticas e Nucleares (IPEN), Universidade de SĆ£o Paulo. Tem experiĆŖncia em QuĆ­mica AnalĆ­tica com ĆŖnfase em AnĆ”lise de TraƧos, atuando principalmente no desenvolvimento de mĆ©todos analĆ­ticos empregando tĆ©cnicas espectrofotomĆ©tricas (AAS, ICP OES e ICP-MS) para caracterizaĆ§Ć£o de amostras ambientais, arqueolĆ³gicas, biolĆ³gicas, forenses e nucleares. Atualmente, ocupa o cargo de Tecnologista em "CaracterizaĆ§Ć£o QuĆ­mica" no Centro de QuĆ­mica e Meio Ambiente (CQMA) do IPEN (CNEN/SP), onde desempenha atividades de pesquisa e desenvolvimento tecnolĆ³gico em atendimento Ć s demandas institucionais ligadas ao Ciclo do CombustĆ­vel Nuclear e aos Programas de Pesquisa de carĆ”ter multidisciplinar, em apoio a projetos de InovaĆ§Ć£o TecnolĆ³gica e ao Programa de PĆ³s-GraduaĆ§Ć£o do IPEN/USP. AlĆ©m disso, atua na geraĆ§Ć£o de produtos tecnolĆ³gicos e no desenvolvimento de materiais adsorventes de baixo custo e alto valor agregado visando o aproveitamento de materiais e resĆ­duos naturais e/ou renovĆ”veis no tratamento de efluentes e rejeitos. (Texto extraĆ­do do CurrĆ­culo Lattes em 4 maio 2023)

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  • Artigo IPEN-doc 27907
    Brazilian clays for environmental solutions applied to radioactive waste management
    2021 - MACHADO, G.G.; KRUPSKAYA, V.V.; ZAKUSIN, S.V.; HARADA, J.; VICENTE, R.; SOUZA, R.P.; ARAUJO, L.G.; MONTALVAN, E.T.; ESPINOSA, D.C.R.; KAHN, H.; GUILHEN, S.N.
    Clayey materials have been adopted in most nuclear waste producing countries as a key constituent in engineered barrier systems for final disposal facilities at all levels of radioactive wastes (LILW-SL, LILW-LL, and HLW). The following study presents a thorough characterization upon five Brazilian clay-rich deposits, mostly smectite bearing clays, aiming to evaluate their expected performance as barrier under the conditions associated to a Low and Intermediate Level Waste Repository; being the former a matter of national strategic interest. Samples coming from the Brazilian states of ParanĆ”, Bahia, ParaĆ­ba, and MaranhĆ£o were treated and analyzed by means of X-Ray diffraction as main technique. Other techniques such as FTIR, LALLS, XRF, and SEM-EDS, were performed in order to establish the mineralogical composition, particle size distribution, and chemical composition. Moreover, several standard clay treatments over the <1 Ī¼m size fraction were carried out to reveal information regarding layer charge, major interlayer cations, unit formula and other crystal features of smectite species present in a mineralogical assembly, aiming to provide information for the construction of a molecular model over which would be realistic to simulate the diffusion of radionuclides. Results obtained on 133Cs adsorption experiments indicate that mineralogical composition would probably be the single most influential factor controlling transport capacity of positively charged radionuclides in the current setup. The composition is especially expressed in terms of smectite contents, favoring montmorillonite rich materials containing majorly Na+ as compensating cation in interlayer position. All tested samples can be considered as suitable candidates to be used in the design of final destination storage for nuclear waste. Thus, efficiency on 133Cs adsorption trials also indicate that these materials could have potential uses as sorptive matrices (Sorbents) for water treatment of radionuclide polluted waters such as TENORM waste waters. However, these trends are yet to be contrasted against hydraulic conductivity measurements and swelling pressure in order to have a more comprehensive perspective of this clayey prospects as barrier enhanced layer; aligned to the multilayer barrier system approach for nuclear waste management.