SABINE NEUSATZ GUILHEN

SABINE NEUSATZ GUILHEN

(Fonte: Lattes)

Resumo

Possui graduação em Química com atribuições Tecnológicas e Biotecnológicas pelo Instituto de Química da Universidade de São Paulo (2005), mestrado (2009) e doutorado (2018) em Tecnologia Nuclear (Materiais) pelo Instituto de Pesquisas Energéticas e Nucleares (IPEN), Universidade de São Paulo. Tem experiência em Química Analítica com ênfase em Análise de Traços, atuando principalmente no desenvolvimento de métodos analíticos empregando técnicas espectrofotométricas (AAS, ICP OES e ICP-MS) para caracterização de amostras ambientais, arqueológicas, biológicas, forenses e nucleares. Atualmente, ocupa o cargo de Tecnologista em "Caracterização Química" no Centro de Química e Meio Ambiente (CQMA) do IPEN (CNEN/SP), onde desempenha atividades de pesquisa e desenvolvimento tecnológico em atendimento às demandas institucionais ligadas ao Ciclo do Combustível Nuclear e aos Programas de Pesquisa de caráter multidisciplinar, em apoio a projetos de Inovação Tecnológica e ao Programa de Pós-Graduação do IPEN/USP. Além disso, atua na geração de produtos tecnológicos e no desenvolvimento de materiais adsorventes de baixo custo e alto valor agregado visando o aproveitamento de materiais e resíduos naturais e/ou renováveis no tratamento de efluentes e rejeitos. (Texto extraído do Currículo Lattes em 4 maio 2023)

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X-ray fluorescence spectrometry
2023 - SCAPIN, M.A.; TESSARI-ZAMPIERIA, M.C.; GUILHENA, S.N.; COTRIM, M.E.B.
This study aims to develop reliable analytical methodology that is, cost-effective, and requires minimal sample quantity to quantify uranium content in nuclear waste and others. The Energy Dispersive X-ray Fluorescence Spectrometry (EDXRF) technique was used, and a rigorous comparison was made between the fundamental parameters (FP) method and the empirical (EMP) method. Statistical evaluation of results demonstrated that the FP method showed a satisfactory level of confidence for precision and limit of quantification.
Direct determination of aluminum in low-enriched UAlx targets (UAlx-Al) by ICP OES
2021 - GUILHEN, S.N.; SOUZA, A.L.; COTRIM, M.E.B.; PIRES, M.A.F.
The production of molybdenum-99 (99Mo) using low-enriched uranium targets (< 20% 235U) dispersed in aluminum (UAlx) is a very promising strategy towards the independence in 99Mo local production. A thorough control must be performed to ensure that these targets meet the regulatory requirements to achieve the expected efficiency in the reactor. The determination of the targets’ composition is of high interest, because the distribution of Al in different phases may have an impact on the U concentration. Among the techniques used for this purpose, inductively coupled plasma optical emission spectrometry (ICP OES) stands out because of its high sensitivity and precision, allowing for simultaneous determination of several elements in a variety of samples and matrices. However, because U exhibits a complex emission spectrum, spectral interferences are prone to affect the analysis of Al, calling for time consuming preparation steps to remove the U from the matrix. This study proposes a method of direct determination of Al in UAlx targets through the selection of specific emission lines enabled by the evaluation of the associated interferences on the recovery values.
Application of bias correction methods to improve U3Si2 sample preparation for quantitative analysis by WDXRF
2019 - SCAPIN, M.A.; GUILHEN, S.N.; AZEVEDO, L.C.; COTRIN, M.E.B.; PIRES, M.A.F.
The determination of silicon (Si), total uranium (U) and impurities in uranium-silicide (U3Si2) samples by wavelength dispersion X-ray fluorescence technique (WDXRF) has been already validated and is currently implemented at IPEN’s X-Ray Fluorescence Laboratory (IPEN-CNEN/SP) in São Paulo, Brazil. Sample preparation requires the use of approx-imately 3 g of H3BO3 as sample holder and 1.8 g of U3Si2. However, because boron is a neutron absorber, this proce-dure precludes the recovery of U3Si2 from the samples, preventing its use as nuclear fuel. Consequently, a significant amount of uranium is wasted in this process. An estimated average of 15 samples per month is expected to be analyzed by WDXRF, resulting in approx. 320 g of U3Si2 that wouldn’t return to the nuclear fuel cycle. The purpose of this paper is to present a new preparation method, replacing H3BO3 by cellulose acetate {[C6H7O2(OH)3-m(OOCCH3)m], m = 0~3}, thus enabling the recovery of the boron-free U3Si2 from the samples. The results demonstrate that the suggested sample preparation approach is statistically satisfactory, allowing the optimization of the procedure.
Method development and validation for simultaneous determination of IEAR1 reactor's pool water U and Si content by ICP OES
2017 - ULRICH, JOAO C.; GUILHEN, SABINE N.; COTRIM, MARYCEL E.B.; PIRES, MARIA A.F.
Assessment of efficiency Allium sativum L. used in the bioremediation of metals cadmium (II) and nickel (II) in aqueous solution
2016 - SETANI, RENATA Y.; SOUSA, JOSE S. de; GUILHEN, SABINE N.; FURUSAWA, HELIO A.; COTRIM, MARYCEL E.B.; MACEDO, FERNANDA de M.; RIBEIRO FILHO, WALDEMAR A.