Improvement of the WBC calibration of the Internal Dosimetry Laboratory of the CDTN/CNEN using the physical phantom BOMAB and MCNPX code.

The Laboratory of Internal Dosimetry of the Center for Development of Nuclear Technology (LDI/CDTN) is responsible for routine internal monitoring of occupationally exposed individuals. The determination of photon emitting radionuclides in the human body requires calibration of the detector in specific counting geometries. The calibration process uses physical phantoms containing certified activities of the radionuclides of interest. The objective of this work was to obtain calibration efficiency curves of the Whole Body Counter in operation at the LDI/CDTN using a BOMAB physical phantom and Monte Carlo simulations.

Internal dosimetry of nuclear medicine workers through the analysis of (131)I in aerosols.

(131)I is widely used in nuclear medicine for diagnostic and therapy of thyroid diseases. Depending of workplace safety conditions, routine handling of this radionuclide may result in a significant risk of exposure of the workers subject to chronic intake by inhalation of aerosols. A previous study including in vivo and in vitro measurements performed recently among nuclear medicine personnel in Brazil showed the occurrence of (131)I incorporation by workers involved in the handling of solutions used for radioiodine therapy. The present work describes the development, optimization and application of a methodology to collect and analyze aerosol samples aiming to assess internal doses based on the activity of (131)I present in a radiopharmacy laboratory. Portable samplers were positioned at one meter distant from the place where non-sealed liquid sources of (131)I are handled. Samples were collected over 1h using high-efficiency filters containing activated carbon and analyzed by gamma spectrometry with a high-purity germanium detection system. Results have shown that, although a fume hood is available in the laboratory, (131)I in the form of vapor was detected in the workplace. The average activity concentration was found to be of 7.4Bq/m(3). This value is about three orders of magnitude below the Derived Air Concentration (DAC) of 8.4kBq/m(3). Assuming that the worker is exposed by inhalation of iodine vapor during 1h, (131)I concentration detected corresponds to an intake of 3.6Bq which results in a committed effective dose of 7.13×10(-5)mSv. These results show that the radiopharmacy laboratory evaluated is safe in terms of internal exposure of the workers. However it is recommended that the presence of (131)I should be periodically re-assessed since it may increase individual effective doses. It should also be pointed out that the results obtained so far reflect a survey carried out in a specific workplace. Thus, it is suggested to apply the methodology developed in this work to other nuclear medicine services where significant activities of (131)I are routinely handled as an effective means to optimize individual exposures and improve occupational radiation protection safety.

Evaluation of a technique for in vivo internal monitoring of (18)F within a Brazilian laboratory network.

(18)FDG, an analogue of glucose labelled with the radionuclide (18)F, is the most widely used radiopharmaceutical in positron emission tomography/computed tomography technique. In Brazil, there are currently eight (18)FDG plants in operation and other facilities are expected to start their production in the near future. The growth in the production and clinical use of (18)FDG represents an increasing risk of worker exposures. According to national regulations and international recommendations, internal exposures should be effectively controlled in order to keep doses as low as possible. The implementation of a routine monitoring programme towards the estimation of internal doses related to the incorporation of (18)F is difficult, mainly due to its short physical half-life, the cost of a bioassay laboratory and the need of a monitoring service promptly available near the production plant. This paper describes the implementation and evaluation of a methodology for in vivo brain monitoring of (18)F to be applied in cases of suspected incorporation of (18)FDG. The technique presented a minimum detectable effective dose in the order of nanoSieverts, which allows its application for occupational monitoring purposes.

Internal exposure in nuclear medicine: application of IAEA criteria to determine the need for internal monitoring

The manipulation of unsealed sources in nuclear medicine poses significant risks of internal exposure to the staff. According to the International Atomic Energy Agency, the radiological protection program should include an evaluation of such risks and an individual monitoring plan, assuring acceptable radiological safety conditions in the workplace. The IAEA Safety Guide RS-G-1.2 recommends that occupational monitoring should be implemented whenever it is likely that committed effective doses from annual intakes of radionuclides would exceed 1 mSv. It also suggests a mathematical criterion to determine the need to implement internal monitoring. This paper presents a simulation of the IAEA criteria applied to commonly used radionuclides in nuclear medicine, taking into consideration usual manipulated activities and handling conditions. It is concluded that the manipulation of 131I for therapy presents the higher risk of internal exposure to the workers, requiring the implementation of an internal monitoring program by the Nuclear Medicine Centers.

A manipulação de fontes abertas em Serviços de Medicina Nuclear envolve riscos de exposição externa e contaminação interna. O plano de proteção radiológica das Instalações licenciadas pela CNEN deve incluir a avaliação de tais riscos e propor um programa de monitoração individual de forma a controlar as exposições e garantir a manutenção das condições de segurança radiológica. As recomendações da AIEA apresentadas no Safety Guide RS-G-1.2 sugerem que seja implementado um programa de monitoração interna do trabalhador sempre que houver possibilidade da contaminação interna conduzir a valores de dose efetiva comprometida anual igual ou superior a 1 mSv. Este trabalho apresenta a simulação da aplicação de tais critérios para os radionuclídeos mais utilizados na área de Medicina Nuclear, levando-se em consideração as condições usuais de manipulação das fontes e as faixas de atividade autorizadas pela CNEN. Conclui-se que a manipulação de iodo 131 para fins terapêuticos é a prática que apresentada maior risco de exposição interna dos trabalhadores, requerendo a adoção de um programa de monitoração interna por parte dos Serviços de Medicina Nuclear.

Biodistribution of 99Mo in rats

The modification of 99Mo standard metabolism in the presence of MDP would alter the dosimetry of this radionuclide in nuclear medicine patients. Therefore, the objective of this work is to evaluate the influence of MDP in the biodistribution of 99Mo. Wistar rats were divided in two groups of six animals, being inoculated respectively 99Molibdate and 99Mo+MDP via plex ocular. The biodistribution study was carried out after 10 and 120 minutes respectively. The organs were counted with a NaI(Tl) detector. The uptake values did not present significant differences among the groups. An in vitro study through planar chromatography was carried out to determine the affinity between molybdenum and MDP. The results show that 99Mo has low affinity both to propanone and NaCl-0.9 percent solution. However, 99Mo in the presence of MDP presented affinity to NaCl-0.9% solution and low affinity to propanone suggesting that 99Mo was bound to MDP under the conditions of the experiment.

A modificação do metabolismo padrão do 99Mo em presença de MDP levaria a alterações na dosimetria deste radionuclídeo em pacientes de medicina nuclear. Assim, o objetivo deste trabalho é avaliar a influência do MDP na biodistribuição de 99Mo. Ratos Wistar foram divididos em dois grupos de seis animais, sendo inoculados respectivamente com 99Molibdato e 99Molibdato+MDP via plexo ocular. O estudo de biodistribuição foi realizado após 10 e 120 minutos respectivamente. Os órgãos foram contados com detector NaI(Tl). Os valores de uptake não apresentaram diferenças significativas entre os grupos. Foi realizado um estudo in vitro através de cromatografia planar para determinar a afinidade entre o molibdênio e o MDP. Os resultados mostraram que o molibdênio tem baixa afinidade tanto pela propanona quanto pela solução 0.9 por cento de NaCl. Entretanto, o molibdênio em presença de MDP apresentou afinidade pela solução 0.9% de NaCl e baixa afinidade pela propanona, sugering ter ocorrido ligação entre o 99Mo e o MDP nas condições do experimento.

Proposta de metodologia para tratamento individualizado com iodo-131 em pacientes portadores de hipertireoidismo da doença de Graves / Proposal of a methodology for individualized iodine-131 therapy for Graves' disease in patients with hyperthyroidism

OBJETIVO: Diferentes métodos são usados para determinar atividade do radioiodo para tratamento de hipertireoidismo (doença de Graves). Alguns não consideram a dose absorvida pela tireóide ou os parâmetros necessários para este cálculo. A relação entre dose absorvida e atividade administrada depende da meia-vida efetiva, da captação do iodo e da massa da tireóide de cada paciente. O objetivo deste trabalho é propor uma metodologia para tratamento individualizado com 131I em pacientes portadores de hipertireoidismo da doença de Graves. MATERIAIS E MÉTODOS: Usou-se um simulador de tireóide-pescoço desenvolvido no Instituto de Radioproteção e Dosimetria contendo solução de 131I, para calibração da gama-câmara e sonda cintilométrica do Serviço de Medicina Nuclear do Hospital Universitário Clementino Fraga Filho da Universidade Federal do Rio de Janeiro. RESULTADOS: O campo de visão colimador-detector apresentou valores compatíveis com o tamanho da glândula para as distâncias de 25 cm (sonda de captação) e 45,8 cm (gama-câmara). Os fatores de calibração (cpm/kBq) foram 39,3 ± 0,78 e 4,3 ± 0,17, respectivamente. O intervalo entre 14 e 30 horas da curva de retenção permite o cálculo de atividade entre dois pontos, para determinação da meia-vida efetiva do iodo na tireóide. CONCLUSÃO: A utilização de equipamentos usualmente disponíveis em serviços de medicina nuclear é viável, tornando esta metodologia simples, eficaz e de baixo custo.

OBJECTIVE: Several methods are utilized for determining the radioiodine activity in the treatment of Graves' disease (hyperthyroidism). Some of this methods do not take into consideration the thyroid absorbed dose or the necessary parameters for this estimation. The association between absorbed dose and administered activity depends on effective half-life, iodine uptake and thyroid mass of each patient. The present study was aimed at developing a methodology for individualized 131I therapy for Graves' disease in patients with hyperthyroidism of the Graves' disease. MATERIALS AND METHODS: A neck-thyroid phantom developed at Instituto de Radioproteção e Dosimetria, containing a standard solution of 131I, was utilized for calibrating the scintillation gamma camera and uptake probe installed in the Department of Nuclear Medicine of the Hospital Universitário Clementino Fraga Filho da Universidade Federal do Rio de Janeiro. RESULTS: The view angle of the collimator/detector assembly presented values compatible with the thyroid gland size for distances of 25 cm (uptake probe) and 45.8 cm (scintillation gamma camera). Calibration factors were 39.3 ± 0.78 and 4.3 ± 0.17 cpm/kBq, respectively. The 14-30-hour interval in the retention curve allows the estimation of activity between two points for determining the effective iodine half-life in the thyroid. CONCLUSION: The utilization of equipment usually available in nuclear medicine clinics is feasible, so this is a simple, effective and low cost methodology.

Determination of 99Mo contamination in a nuclear medicine patient submitted to a diagnostic procedure with 99mTc

99mTc is a radionuclide widely used for imaging diagnosis in nuclear medicine. In Brazil it is obtained by elution from 99Mo-99mTc generators supplied by the Nuclear Energy Research Institute (IPEN). The elution is carried out in radiopharmacy laboratories located in hospitals and clinics. Depending of the quality of the generator and conditions of use during the elution process, 99Mo can be extracted from the column of the generator, becoming a radionuclidic impurity of the eluate used for the obtention of the radiopharmaceutical to be administered to the patient. 99Mo emits high-energy photons and beta particles and its presence degrades the quality of the image and unnecessarily increases the radiation dose delivered to the patient. An in-vivo measurement technique was developed to verify the occurrence of internal contamination by 99Mo in nuclear medicine patients. Direct measurements were made in a volunteer who underwent myocardial scintigraphy with 99mTc-sestamibi. The results indicated the presence of internal contamination of the patien by 99Mot. The activity was tracked for several days, and an assessment of the radiation dose from the contaminant 99Mo was made.

O 99mTc é um radionuclídeo largamente utilizado em diagnósticos por imagem em medicina nuclear. No Brasil, ele é obtido por eluição de um gerador de 99Mo-99mTc fornecido pelo IPEN. A eluição do gerador é feita nas clínicas onde se realizam os exames. Durante a eluição o 99Mo pode ser carreado da coluna, tornando-se uma impureza radionuclídica do eluato a ser utilizado para a obtenção do radiofármaco administrado ao paciente. O 99Mo emite fótons de alta energia e partículas beta, e sua presença, além de provocar degradação na qualidade da imagem do exame, aumenta desnecessariamente a dose de radiação no paciente. Assim, com o objetivo de verificar a possível ocorrência de contaminação interna por 99Mo em pacientes de medicina nuclear, foi desenvolvida uma técnica de medida in vivo e monitorado um paciente voluntário submetido a cintilografia do miocárdio com 99mTc-sestamibi. Os resultados revelaram a presença de 99Mo no corpo do paciente monitorado.