Navegação Periódicos - Artigos por autor "10132"

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  • IPEN-DOC 26878

    TESSARO, ANA P.G. ; ARAUJO, LEANDRO G. de ; VICENTE, ROBERTO . Inventorying the radionuclides in spent cartridge filters from the primary circuit of a nuclear research reactor by the dose-to-activity method. Radiation Physics and Chemistry, v. 171, p. 1-6, 2020. DOI: 10.1016/j.radphyschem.2020.108710

    Abstract: The high activity of spent cartridge filters from the cooling water polishing system of a nuclear research reactor precludes, in routine work of a waste characterization program, the usual method of radiochemical analysis of filter samples. For this waste, the dose-to-activity method, using a gamma spectrometer and a dose rate meter, is an alternative for the determination of the activities of the gamma emitters with acceptable accuracy. The ratio of photon peak-areas from different radionuclides, corrected by the detector energy-dependent efficiency, allowed estimating the proportions between the activities of the different radionuclides present. Finally, the simulation of the counting geometry, using the point-kernel method to estimate the air dose rate resulting from an arbitrary concentration of those radionuclides and the comparison of the calculated with the measured air dose rate have yielded the needed estimates of the activity concentrations. The aim of this paper is to report the development of the method applied for the determination of the concentration of the gamma-emitters present in cartridge filters from the IEA-R1 Nuclear Research Reactor.

    Palavras-Chave: radioactive waste management; calculation methods; radioisotopes; gamma spectrometers; filters; iear-1 reactor; inventories; solid wastes; dose rates

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  • IPEN-DOC 27144

    ARAUJO, LEANDRO G. de ; PRADO, EDUARDO S.P. ; MIRANDA, FELIPE de S.; VICENTE, ROBERTO ; SILVA SOBRINHO, ARGEMIRO S. da; PETRACONI FILHO, GILBERTO; MARUMO, JULIO T. . Physicochemical modifications of radioactive oil sludge by ozone treatment. Journal of Environmental Chemical Engineering, v. 8, n. 5, p. 1-8, 2020. DOI: 10.1016/j.jece.2020.104128

    Abstract: An experimental study on the degradation of organic compounds from radioactive oil sludge by the ozonation process is presented. The effects of different concentrations of ozone in the oil sludge degradation over time were investigated. The experiments were performed in a 0.125 L glass reactor with magnetic stirring and a diffuser plate at the bottom to feed the ozone. The ozone concentration varied from 13 to 53 mg L−1 and the total interaction time was 1 h. To investigate the physicochemical properties of the oil sludge (solid and liquid components) prior to and after the treatment, multiple analytical characterization methods were used: Thermal Gravimetric Analysis, X-ray diffraction, Scanning Electron Microscopy coupled with Energy-Dispersive X-ray Spectroscopy, Fourier Transform Infrared spectroscopy, Spectrophotometer, and Residual Gas Analyzer. The most perceptive change is in the color of the liquid medium turned from dark brown to light yellow, especially under ozone concentrations higher than 33 mg L−1. Absorbance values decreased about 3.5 times after 30 min of treatment with [O3] =53 mg L−1. FTIR spectroscopy showed that the bands associated with the CH3 and CeH in CH2 disappeared during treatment. On the other hand, a greater presence of C]C aromatics was observed. By residual gas analysis, various organic and inorganic gases were identified during the treatment, such as CH4, H2, CO2, and H2S. Finally, the ozonation of the oil sludge proved to be effective, due to its high reaction capacity.

    Palavras-Chave: ozone; therapy; ozonization; radioactivity; sludges; oxidation; naturally occurring radioactive materials; fourier transformation; thermal gravimetric analysis

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  • IPEN-DOC 27429

    GERALDO, BIANCA ; ARAUJO, LEANDRO G. de ; VICENTE, ROBERTO ; TADDEI, MARIA H.T.; CHEBERLE, SANDRA M.; MARUMO, JULIO T. . Radioanalytical methods for sequential analysis of actinide isotopes in activated carbon filter‑bed waste. Journal of Radioanalytical and Nuclear Chemistry, v. 326, p. 1559-1568, 2020. DOI: 10.1007/s10967-020-07435-8

    Abstract: In this work, we compare methods for the sequential determination of U and the transuranium elements Np, Pu, Am, and Cm. The chemical yield, the time spent in the analysis, the amount of secondary waste, and the costs of each method are the aspects of interest. Two methods were compared: extraction chromatography (EC) and ion exchange plus extraction chromatography (IE + EC). The chemical yields of (EC) and (IE + EC) were similar for all radionuclides. The (EC) method is the more effective with respect to time of analysis, the amount of secondary waste and costs.

    Palavras-Chave: radioisotopes; radiochemistry; cost benefit analysis; ion exchange; radiopharmaceuticals; tracer techniques

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  • IPEN-DOC 26681

    GERALDO, BIANCA ; ARAUJO, LEANDRO G. de ; TADDEI, MARIA H.T.; FERREIRA, MARCELO T.; MADUAR, MARCELO F. ; VICENTE, ROBERTO ; MARUMO, JULIO T. . Radiochemical characterization of spent filter cartridges from the primary circuit of a research reactor. Journal of Radioanalytical and Nuclear Chemistry, v. 322, n. 3, p. 1941-1951, 2019. DOI: 10.1007/s10967-019-06864-4

    Abstract: Radiochemical-based analyses have been used for the characterization of radioactive waste. Nevertheless, the determination of alpha, beta and gamma emitters by radiochemical analysis of spent cartridge filters from a swimming-pool type reactor has not been previously addressed. This work aims at identifying and quantifying the radionuclides present in this waste, including the difficult to measure radionuclides. The distribution of the radionuclides in the filter was investigated by the determination of gamma-emitting nuclides and the z-score of the measured activity concentrations. The results indicated that all the filters are homogeneous, meeting the homogeneity criteria recommended by the International Atomic Energy Agency.

    Palavras-Chave: alpha decay radioisotopes; beta decay radioisotopes; filters; gamma decay; pool type reactors; radioactive waste management; radioactive wastes; radioactivity; radiochemical analysis; research reactors

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  • IPEN-DOC 27250

    MEDEIROS, VINICIUS L.; ARAUJO, LEANDRO G. de ; RATERO, DAVI R.; PAULA, ALEX S.; MOLINA, EDUARDO F.; JAEGER, CHRISTIAN; MARUMO, JULIO T. ; NERY, JOSE G.. Synthesis and physicochemical characterization of a novel adsorbent based on yttrium silicate: a potential material for removal of lead and cadmium from aqueous media. Journal of Environmental Chemical Engineering, v. 8, n. 4, p. 1-10, 2020. DOI: 10.1016/j.jece.2020.103922

    Abstract: A new metallosilicate based on yttrium was synthesized and characterized by XRD, FT-IR, 29Si MAS-NMR, and 89Y MAS-NMR. The mixed framework of the material was confirmed by the detection of distinct chemical shift groups using 29Si MAS-NMR (at -82 to -87 ppm, -91 to -94 ppm, -96 to -102 ppm, and -105 to -108 ppm), as well as four distinct chemical shifts in the 89Y MAS-NMR spectrum (at -89, -142, -160, and -220 ppm). Adsorption and kinetic analyses indicated the potential of the new material for the removal of lead and cadmium from aqueous media. The adsorption results for lead indicated that dynamic equilibrium was reached after five hours, with total lead removal of around 94 %, while for cadmium it was reached in the first hour, with total cadmium removal of around 74 %. The adsorptions of lead and cadmium were modeled using pseudo-first order (PFO) and pseudo-second order (PSO) kinetic models. Although both models provided high R2 values (0.9903 and 0.9980, respectively), the PSO model presented a much lower χ2 red value (4.41×10−4), compared to the PFO model (2.12×10−3), which indicated that the rate-limiting step was probably due to the chemisorption of lead from the solution onto the yttrium-based metallosilicate.

    Palavras-Chave: adsorbents; yttrium silicates; chemisorption; adsorption; aqueous solutions; lead; cadmium; silicon 29; yttrium 89; nuclear magnetic resonance

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  • IPEN-DOC 27180

    FERREIRA, RAFAEL V. de P.; ARAUJO, LEANDRO G. de ; CANEVESI, RAFAEL L.S.; SILVA, EDSON A. da; FERREIRA, EDUARDO G.A. ; PALMIERI, MAURICIO C.; MARUMO, JULIO T. . The use of rice and coffee husks for biosorption of U (total), 241Am, and 137Cs in radioactive liquid organic waste. Environmental Science and Pollution Research, v. 27, n. 29, SI, p. 36651-36663, 2020. DOI: 10.1007/s11356-020-09727-8

    Abstract: Rice and coffee husks (raw and chemically activated) are examined as potential biosorption materials regarding their capacity to remove U (total), 241Am, and 137Cs. The physical parameters evaluated were the morphological characteristics of the biomass, real and apparent density, and surface area. Contact times for the batch experiments were 0.5, 1, 2, and 4 h, and the concentrations tested ranged between 10% of the total concentration and the radioactive waste itself without any dilution. The results were evaluated by experimental sorption capacity, ternary isotherm, and kinetics models. The kinetics results showed that equilibrium was reached after 2 h for all biomass. Raw coffee husk showed the best adsorption results in terms of maximum capacity (qmax) for all three radionuclides, which were 1.96, 39.4 × 10−6, and 46.6 × 10−9 mg g−1 for U, Am, and Cs, respectively. The biosorption process for the raw and activated rice husks was best represented by the Langmuir ternary isotherm model with two sites. For the coffee husk, in the raw and activated states, the biosorption process was best described by the modified Jain and Snoeyink ternary model. These results suggest that biosorption with these biomaterials can be applied in the treatment of liquid organic radioactive waste containing mainly uranium and americium.

    Palavras-Chave: bioadsorbents; biomass; fourier transformation; infrared radiation; rice; liquid wastes; organic compounds; uranium; americium; cesium; coffee beans; gamma spectroscopy

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  • IPEN-DOC 27397

    PRADO, EDUARDO S.P.; MIRANDA, FELIPE S.; ARAUJO, LEANDRO G. de ; PETRACONI, GILBERTO; BALDAN, MAURICIO R.. Thermal plasma technology for radioactive waste treatment: a review. Journal of Radioanalytical and Nuclear Chemistry, v. 325, n. 2, p. 331-342, 2020. DOI: 10.1007/s10967-020-07269-4

    Abstract: In this paper, a review of radioactive wastes treatment using thermal plasma technology is presented as a treatment method for radioactive waste management.Virtually all waste streams can be treated by the thermal plasma technologies, resulting in a conditioned product, free from organics and liquids, definitely meeting the acceptance criteria for safe storage and disposal. The application of the thermal plasma system in the nuclear area is still one of the current research topics due to the theoretical and practical complexity of the treatment. This paper discusses the performance of the thermal plasma systems, addressing the advantages and limitations of the method.

    Palavras-Chave: plasma technology; radioactive waste management; radioactive waste processing; management; processing

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  • IPEN-DOC 27387

    ARAUJO, LEANDRO G. de ; BORBA, TANIA R. de ; FERREIRA, RAFAEL V. de P.; CANEVESI, RAFAEL L.S.; SILVA, EDSON A. da; DELLAMANO, JOSE C. ; MARUMO, JULIO T. . Use of calcium alginate beads and Saccharomyces cerevisiae for biosorption of 241Am. Journal of Environmental Radioactivity, v. 223-224, p. 1-10, 2020. DOI: 10.1016/j.jenvrad.2020.106399

    Abstract: Calcium alginate beads, inactivated Saccharomyces cerevisiae and inactivated S. cerevisiae immobilized in calcium alginate beads (S. cerevisiae–calcium alginate beads) are examined as potential biosorption materials as regards their capacity to remove 241Am. In this study, initial experiments were carried out to evaluate the effects of pH (2 and 4) and 241Am initial concentration: 75, 150, and 300 Bq mL-1. The experiments were conducted in a batch reactor. Higher removal capacity was observed at pH 2 with the use of S. Cerevisiae, whereas pH 4 performed better for the essays with calcium alginate beads and S. Cerevisiae-calcium alginate beads. The pseudo-first-order kinetic model described the kinetics of biosorption. Calcium alginate was the adsorbent of choice to further experiments with synthetic organic liquid waste. A lower removal rate was observed in the organic waste, although calcium alginate beads have also been able to achieve high sorption capacity in less than 4 h. With the organic waste, the highest value of sorption capacity of 241Am was 4.38 × 10−7 mmol g−1 with an initial 241Am concentration of 2.31 × 10−8 mmol L−1.

    Palavras-Chave: bioadsorbents; sorption; adsorbents; americium 241; saccharomyces cerevisiae; calcium; alginates; ph value

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  • IPEN-DOC 27194

    BELLINI, MARIA H. ; SOUZA, ALEXANDRE L. de ; SILVA, FABIO F. da; GUILHEN, SABINE N. ; FERREIRA, RAFAEL V. de P.; ARAUJO, LEANDRO G. de ; OLIVEIRA, JOAO E. de ; MARUMO, JULIO T. . Variations in essential elements after malignant transformation of kidney epithelial tubular cells. Medical & Clinical Research, v. 5, n. 6, p. 114-117, 2020. DOI: 10.33140/MCR.05.06.04

    Abstract: Cell line-based research is a valuable tool for the study of cancer physiopathology and the discovery of new drugs for use in clinical practice. In this study, inductively coupled plasma mass spectrometry (ICP-MS) was used to estimate Ca, Co, Cu, Fe, K, Mg, Mn, Na, P, S, Se, and Zn in epithelial tubular cells (HK-2) and kidney tumor cells (Caki-1 cells). The most relevant difference was a decrease in the contents of Ca, Cu, Fe, K, Mg, Mn, Na, P, S, and Zn. A significant accumulation of Co was also detected in Caki-1 cells. The fold change variation of each element concentration between HK-2 and Caki-1 cells was Ca (‒0.40), Co (1.37), Cu (‒0.68), Fe (‒0.56), K (‒0.40), Mg (‒0.41), Mn (-0.54), Na (‒0.33), P (‒0.31), S (‒0.26), and Zn (‒0.73). These findings indicate that the elements mainly affect the metabolic pathways of epithelial kidney cells. Thus, our findings open a new avenue for RCC target therapy

    Palavras-Chave: kidneys; carcinomas; elements; transition elements; icp mass spectroscopy; transformations; tumor cells; lyophilization

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A elaboração do projeto do RI do IPEN foi iniciado em novembro de 2013, colocado em operação interna em julho de 2014 e disponibilizado na Internet em junho de 2015. Utiliza o software livre Dspace, desenvolvido pelo Massachusetts Institute of Technology (MIT). Para descrição dos metadados adota o padrão Dublin Core. É compatível com o Protocolo de Arquivos Abertos (OAI) permitindo interoperabilidade com repositórios de âmbito nacional e internacional.

1. Portaria IPEN-CNEN/SP nº 387, que estabeleceu os princípios que nortearam a criação do RDI, clique aqui.


2. A experiência do Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP) na criação de um Repositório Digital Institucional – RDI, clique aqui.