Evaluation of two 99mTc-DTPA radioaerosols with different characteristics in lung ventilation studies

Two radioaerosol preparations, TechneScan®-DTPA (99mTc-DTPA, 40 mCi/3 ml; IPEN-CNEN, São Paulo, SP, Brazil) and TechneScan®-DTPA/AEROSOL (99mTc-DTPA/A, 15 mCi/1.5 ml with 0.5 ml ethanol; Mallinckrodt Medical, St. Louis, MO, USA), were compared in pulmonary ventilation studies in terms of total radiocounts and clearance after inhalation. An aerosol with ethanol is supposed to better distribute the radioparticles in the lungs. Twenty normal nonsmoking volunteers (10 men and 10 women), mean age of 23.2 years (range: 20 to 35 years), were studied. Images were obtained immediately and 30, 60 and 90 min after inhalation. Total and regional counts were obtained and the clearance half-lives of both lungs were determined. There was no difference in total counts between the two types of radioaerosol at any time (mean of ~188,000 cpm for male and female subjects at time zero in both aerosols). The highest count was obtained in the middle region of both lungs (P<0.001) with both preparations. The clearance half-life did not differ between aerosols (mean of ~80-88 min for male and female subjects for both aerosols). Small nonsignificant regional differences were observed. No differences between genders or between right and left lung were observed. 99mTc-DTPA/A generated the highest output of radioaerosol. 99mTc-DTPA with alcohol costs approximately five times more than the aerosol without alcohol. The present results show that either kind of aerosol may be adopted routinely for use in pulmonary examinations without affecting diagnosis. We suggest that the amount of 740 mBq (20 mCi) of 99mTc-DTPA in 1.5 ml saline can be used for routine examinations resulting in reduction of costs in pulmonary ventilation studies without diagnostic impairment.

Natural radiation levels in powdered milk samples

The control and monitoring of radioactive elements in foodstuffs is fundamental for human health maintenance. This work presents procedures to measure radioactivity levels in powdered milk samples and also a brief discussion of radionuclide transference from the environment to mankind. The measurements were performed utilizing a high-resolution gamma-ray spectrometer using an HPGe detector. The results allowed the quantification of 40K, 137Cs and 208Tl radionuclides. For 40K the average activity was 482 ± 37 Bq/kg and for 137Cs and 208Tl the lower level of detection was, respectively, 3.7 ± 1.1 and 0.5 ± 0.2 (Bq/kg). The results obtained for the milk samples were compared to data found in the literature and to the limits established by the Brazilian National Commission of Nuclear Energy (CNEN) to assure its safety to human consuption.

Fractal structures in nonlinear plasma physics

Fractal structures appear in many situations related to the dynamics of conservative as well as dissipative dynamical systems, being a manifestation of chaotic behaviour. In open area-preserving discrete dynamical systems we can find fractal structures in the form of fractal boundaries, associated to escape basins, and even possessing the more general property of Wada. Such systems appear in certain applications in plasma physics, like the magnetic field line behaviour in tokamaks with ergodic limiters. The main purpose of this paper is to show how such fractal structures have observable consequences in terms of the transport properties in the plasma edge of tokamaks, some of which have been experimentally verified. We emphasize the role of the fractal structures in the understanding of mesoscale phenomena in plasmas, such as electromagnetic turbulence.

Blowout bifurcation and spatial mode excitation in the bubbling transition to turbulence

The transition to turbulence (spatio-temporal chaos) in a wide class of spatially extended dynamical system is due to the loss of transversal stability of a chaotic attractor lying on a homogeneous manifold (in the Fourier phase space of the system) causing spatial mode excitation Since the latter manifests as intermittent spikes this has been called a bubbling transition We present numerical evidences that this transition occurs due to the so called blowout bifurcation whereby the attractor as a whole loses transversal stability and becomes a chaotic saddle We used a nonlinear three-wave interacting model with spatial diffusion as an example of this transition (C) 2010 Elsevier B V All rights reserved

Triple- and quadruple-escape peaks in HPGe detectors: Experimental observation and Monte Carlo simulation

The triple- and quadruple-escape peaks of 6.128 MeV photons from the (19)F(p,alpha gamma)(16)O nuclear reaction were observed in an HPGe detector. The experimental peak areas, measured in spectra projected with a restriction function that allows quantitative comparison of data from different multiplicities, are in reasonably good agreement with those predicted by Monte Carlo simulations done with the general-purpose radiation-transport code PENELOPE. The behaviour of the escape intensities was simulated for some gamma-ray energies and detector dimensions; the results obtained can be extended to other energies using an empirical function and statistical properties related to the phenomenon. (C) 2010 Elsevier B.V. All rights reserved.

Determination of Very Slow Diffusion of Paramagnetic Ions by NMR Spectroscopy

In this paper, we propose a new method of measuring the very slow paramagnetic ion diffusion coefficient using a commercial high-resolution spectrometer. If there are distinct paramagnetic ions influencing the hydrogen nuclear magnetic relaxation time differently, their diffusion coefficients can be measured separately. A cylindrical phantom filled with Fricke xylenol gel solution and irradiated with gamma rays was used to validate the method. The Fricke xylenol gel solution was prepared with 270 Bloom porcine gelatin, the phantom was irradiated with gamma rays originated from a (60)Co source and a high-resolution 200 MHz nuclear magnetic resonance (NMR) spectrometer was used to obtain the phantom (1)H profile in the presence of a linear magnetic field gradient. By observing the temporal evolution of the phantom NMR profile, an apparent ferric ion diffusion coefficient of 0.50 mu m(2)/ms due to ferric ions diffusion was obtained. In any medical process where the ionizing radiation is used, the dose planning and the dose delivery are the key elements for the patient safety and success of treatment. These points become even more important in modern conformal radio therapy techniques, such as stereotactic radiosurgery, where the delivered dose in a single session of treatment can be an order of magnitude higher than the regular doses of radiotherapy. Several methods have been proposed to obtain the three-dimensional (3-D) dose distribution. Recently, we proposed an alternative method for the 3-D radiation dose mapping, where the ionizing radiation modifies the local relative concentration of Fe(2+)/Fe(3+) in a phantom containing Fricke gel and this variation is associated to the MR image intensity. The smearing of the intensity gradient is proportional to the diffusion coefficient of the Fe(3+) and Fe(2+) in the phantom. There are several methods for measurement of the ionic diffusion using NMR, however, they are applicable when the diffusion is not very slow.

Optical and electrical characterization of samaria-doped ceria

Ce(0.8)SM(0.2)O(1.9) and CeO(2) nanomaterials were prepared by a solution technique to produce an ultrafine particulate material with high sinterability. In this work, the structural characteristics, the photoluminescent behavior and the ionic conductivity of the synthesized materials are focused. The thermally decomposed material consists of less than 10 nm in diameter nanoparticles. The Raman spectrum of pure CeO(2) consists of a single triple degenerate F(2g) model characteristic of the fluorite-like structure. The full width at half maximum of this band decreases linearly with increasing calcination temperature. The photoluminescence spectra show a broadened emission band assigned to the ligand-to-metal charge-transfer states O -> Ce(4+). The emission spectra of the Ce(0.8)Sm(0.2)O(1.9) specimens present narrow bands arising from the 4G(5/2) -> (6)H(J) transitions (J = 5/2, 7/2, 9/2 and 11/2) of Sm(3+) ion due to the efficient energy transfer from the O -> Ce(4+) transitions to the emitter 4G(5/2) level. The ionic conductivity of sintered specimens shows a significant dependence on density. (C) 2009 Elsevier B.V. All rights reserved.

Calorimetric investigations of luminescent films polycarbonate (PC) doped with europium complex [Eu(TTA)(3)(H(2)O)(2)]

Polymers doped with rare earth complexes are advantaged in film production for many applications in the luminescent field. In this luminescent polycarbonate (PC) films doped with diaquatris(thenoyltrifluoroacetonate)europium(III) complex [Eu(TTA)(3)(H(2)O)(2)] were prepared and their calorimetric and luminescent properties in the solid state are reported. The thermal behavior was investigated by utilization of differential scanning calorimetry (DSC) and thermogravimetry (TG). Due of the addition of rare earth [Eu(TTA)(3)(H(2)O)(2)] into PC matrix, changes were observed in the thermal behavior concerning the glass transition and thermal stability. Characteristic broadened narrow bands arising from the (5)D(0) -> (7)F(J) transitions (J = 4-0) of Eu(3+) ion indicate the incorporation of the Eu(3+) ions in the polymer. The luminescent films show enhancement emission intensity with an increase of rare earth concentration in polymeric matrix accompanied by decrease in thermal stability.

Processamento e interpretação de dados aerogeofísicos magnetométricos e gamaespectrométricos no estudo do controle das mineralizações auríferas na região do Complexo Bossoroca, São Sepé, RS

Sete ocorrências auriferas estão inseridas na Seqüência Campestre do Complexo Bossoroca, no Escudo Sul-rio-grandense, municípios de São Sepé, no Estado do Rio Grande do Sul. Nessa região, foi realizado um aerolevantamento geofisico no qual foram coletados dados magnetométricos e aerogamaespectrométricos (K, U, Th e contagem total), em convênio finnado entre órgãos federais brasileiros (CPRM, DNPM e CNEN) e a empresa canadense Texas Instruments no período 1972-1973. Nessa dissertação são apresentados as interpretações e resultados dos dados e a metodologia utilizada para a interpretação das principais estruturas magnéticas e radiométricas visando aplicação na exploração mineral de ouro. Esse tipo de processamento, correlacionado aos dados geológicos, é uma prática usual de campanhas de prospecção mineral desde 1940 e é considerada como uma ferramenta de grande potencial para esse propósito. O processamento de dados magnetométricos forneceu mapas de primeira e segunda derivadas verticais, sinal analítico, gradiente horizontal, integral vertical, continuação para cima (1000, 2000 e 3000 metros) e seus principais lineamentos do campo magnético residual. Os dados foram tratados e posterionnente transfonnados em mapas de contorno e imagens pseudocoloridos e em tons de cinza com relevo sombreado (iluminação N, NE e SE) para realçar os principais lineamentos. Os mapas produzidos a partir dos dados aerogamaespectrométricos foram os de contagem total, K, U e Th, suas razões Th/K, U/K e UITh; mapas temários nos padrões RGB e CMY, potássio e urânio anômalos e parfunetro F, também foram transfonnados em mapas de contorno, pseudocolridos e tons de cinza com relevo sombreado (iluminação a N, NE e SE) e um mapa geológico interpretativo da região do Complexo Bossoroca As imagens magnetométricas mostraram-se importantes na caracterização estrutural regional, possibilitando a identificação de lineamentos NE-SW e NW-SE, não mapeados anterionnente e que podem estar relacionadas diretamente às ocorrências auriferas da região do Complexo Bossoroca. A aplicação das técnicas de processamento e interpretação de estruturas magnéticas por meio dos filtros como gradiente horizontal, primeira e segunda derivada, sinal analítico, continuação para cima, possibilitaram a determinação de descontinnidades fisicas que podem ser traduzidas em estruturas geológicas. O processamento de dados aerogamaespectrométricos possibilitou a caracterização de unidades geológicas regionais, a identificação de possíveis trends e zonas anômalas em potássio, relacionadas com as principais ocorrências auriferas da região. As imagens ternárias nos padrões RGB e CMY pennitiram a distinção e a caracterização das grandes unidades geológicas. Pode-se individualizar três regiões principais dentro da Seqüência Campestre, não mapeadas anterionnente, onde se encontram as ocorrências auriferas.

Análise dos acidentes radiológicos dentro do contexto das empresas de radiografia industrial

A expectativa deste trabalho é discutir a questão da segurança em radiografia industrial, sob o contexto geral da atividade, procurando contribuir para a busca de melhores padrões de segurança para os profissionais que atuam em operações com fontes de radiação. Tomou-se como ponto de partida os dados divulgados pela Comissão Nacional de Energia Nuclear (CNEN), no encontro sobre Segurança Radiológica em Radiografia Industrial (Rio de Janeiro, 1998) e contrapôs-se a opinião dos profissionais de radiografia industrial na região metropolitana de Porto Alegre, sobre os aspectos que afetam os padrões de segurança na atividade. Estes dados foram coletados com base na técnica do Design Macroergonômico proposto por Fogliatto e Guimarães (1999). Além dos problemas diretamente relacionados à segurança radiológica, ficou evidente a importância das questões de natureza gerencial e organizacional, que não são consideradas nos atuais padrões de segurança das empresas brasileiras de radiografia industrial.

Regulação estatal do setor nuclear: estudo comparativo dos modelos da Argentina e do Brasil

Este estudo apresenta uma análise comparativa dos modelos de regulação dos setores nucleares da Argentina - a cargo da Autoridad Regulatoria Nuclear (ARN), e do Brasil- sob a responsabilidade da Comissão Nacional de Energia Nuclear (CNEN), que procura identificar, por meio de critérios de análise selecionados a partir do referencial teórico, qual modelo é o mais adequado objetivando o uso seguro da energia nuclear. O Capítulo I apresenta uma breve descrição dos modelos de regulação dos setores nucleares do Brasil e da Argentina, bem como os objetivos, a delimitação do estudo e a relevância da pesquisa. O referencial teórico, Capítulo 2, contém tópicos sobre a reforma do Estado, os tipos de regulação, a regulação no Brasil e as características do setor nuclear internacional e brasileiro. A seguir, foram selecionados critérios de análise que correspondem às características das agências reguladoras brasileiras criadas para outros setores da economia, no bojo da reforma de Estado implementada no Brasil a partir de meados dos anos 90. Posteriormente, estes critérios de análise foram utilizados como parâmetros de comparação entre os modelos de regulação dos setores nucleares da Argentina e do Brasil. A metodologia de pesquisa é descrita no Capítulo 3, definindo-se o tipo de pesquisa, o universo e a amostra, a forma de coleta e tratamento dos dados e as limitações do método empregado. No Capítulo 4 é descrito o modelo de regulação do setor nuclear argentino, apresentando-se também um breve histórico sobre a criação da ARN. O Capítulo 5 apresenta a descrição do modelo de regulação do setor nuclear brasileiro, os estudos e recomendações existentes sobre a regulação do setor e os resultados da pesquisa empírica realizada junto aos servidores da CNEN. Com base na análise comparativa, Capítulo 6, pode-se concluir, Capítulo 7, que a estrutura regulatória e fiscalizadora do setor nuclear argentino, sob responsabilidade da ARN, mostra-se mais adequada no que tange ao uso seguro da energia nuclear, do que o modelo adotado no Brasil pela CNEN, pois incorpora os critérios de independência funcional, institucional e financeira, definição de competências, excelência técnica e transparência, necessários ao desempenho de suas funções de forma autônoma, ética, isenta e ágil.

Fission-track dating of Macusanite glasses with plateau and size correction methods

Two Macusanite pebbles (MB1 and MB2) were dated with the fission-track method. Six irradiations were carried out in different nuclear reactors: Pavia (Italy), IPEN-CNEN (Brazil) and IPEN-Lima (Peru). Measurements of the thorium and uranium induced-fission per target nucleus using natural thorium thin films and natural U-doped glasses calibrated against natural uranium thin films, together with lambda(F) of 8.46 x 10(-17) a(-1) were used to determine the ages. The apparent ages were corrected using the plateau and size correction methods. Track measurements were performed by different analysts, using different counting criteria. In addition, tracks were measured on samples which had been submitted to thermal treatment as well as on samples which had not been heated. Thermal treatments were carried out to erase the fossil tracks before neutron irradiation. No significant differences have been found in individual results, using the two Macusanite pebbles and the different nuclear reactors, age correction techniques, analysts, track-counting criteria, and thermal treatments before neutron irradiation. The great majority of the results (14/17) is compatible with the Ar-Ar ages of 5.12 +/- 0.11 and 5.10 +/- 0.11 Ma, Macusanite MB1 and MB2, respectively. However, the fission-track ages are systematically less (similar to8%) than the Ar-Ar ages of the two Macusanite samples studied. (C) 2003 Published by Elsevier Ltd.

Thermoluminescence measurements of entrance surface skin dose in exams of dog's chest in veterinary radiology

This study aims to determine the entrance surface skin doses in dogs (with suspected pulmonary metastasis) submitted to chest X-rays using the technique of thermoluminescence (TL) dosimetry. Twenty seven radiologic exams of dogs of different breed and sizes were performed. The radiation doses were assessed using thermoluminescent dosimeters of calcium sulphate doped with dysprosium (CaSO(4):Dy) produced at Instituto de Pesquisas Energeticas e Nucleares (IPEN-CNEN). The entrance surface skin dose range evaluated in this type of procedure was between 0.43 mGy to small size dogs and 4.22 mGy to big size dogs with repeated exams. The obtained results indicate that is extremely important the assessment of radiation doses involved in veterinary diagnostic radiology procedures, to evaluate the delivered doses to the animals, to be used as a parameter in the individual monitoring of pet's owners, who assist the animal positioning, and to protect occupationally exposed workers at the Veterinary Radiology Clinics. (C) 2010 Elsevier Ltd. All rights reserved.

Problems related to the employment of thin uranium films as neutron dosimeters

Thin uranium films built on muscovite mica basis and obsidian samples having known ages were irradiated with thermal neutrons at the IPEN/CNEN reactor, São Paulo. Comparing thin film performance with the obsidian one, it was observed that the latter feel a greater neutron fluence. Nominal fluences at the used facility are in agreement with the results obtained analysing the obsidian samples. A probable hypothesis to explain this disagreement, namely, the uranium loss from the thin films, was ruled out. © 1995.

The licensing of a laboratory for manipulating radionuclides in Brazil

Radionuclides take a major role in guidelines of environmental agencies/national organizations of countries worldwide. In Brazil, CNEN-Comissão Nacional de Energia Nuclear is responsible for managing all subjects related to nuclear energy in the country. Thus, laboratories employing radionuclides for the development of their activities must submit a Radioprotection Plan to CNEN in order to get an operation license. Such plan must indicate that the laboratory is exempt of risks to the people involved and designed to fit all related environmental aspects. This was the case of LABIDRO-Hydrochemical and Isotopes Laboratory that belongs to IGCE-Geosciences and Exact Sciences Institute from UNESP - the University of the State of São Paulo Júlio de Mesquita Filho, located at Rio Claro city, São Paulo State, Brazil. The total monthly activity of the radionuclides utilized during the laboratorial activities held at LABIDRO corresponds to 0.01 μCi. This paper describes all information provided by LABIDRO in order to get the CNEN license. The LABIDRO plan also showed the expected radioactive waste released when the experiments take place and CNEN decided that it fits the guidelines established by Brazilian legislation. Therefore, LABIDRO received its license for utilizing radionuclides, which is valid until September 2016. © 2013 WIT Press.