RESUMO
The use of radioactive nanoparticles as imaging and therapeutic agents is increasing globally. Indeed, the use of these nanoparticles as perfect theranostic agent is highly anticipated in the pharmaceutical market. Among the radioactive nanoparticles, liposomes, solid lipid nanoparticles and polymeric nanoparticles are the most studied. However little information among adverse reactions, absorbed dose and correct dose to achieve the theranostic goal in a translational application is available. We developed a radioactive polymeric nanoparticle and calculated the absorbed dose in animal model (Wistar rats) using the OLINDA/EXM program. The results showed that some nanoparticle were uptake in five organs and minor elimination through the gastrointestinal and urinary pathways. The data corroborates the safe use in terms of blood-brain barrier and did not show high uptake by liver. The dosimetry data support the safe use of radioactive nanoparticles as theranostic agent. Graphical abstract á .
Assuntos
Nanopartículas/uso terapêutico , Doses de Radiação , Nanomedicina Teranóstica , Animais , Marcação por Isótopo , Ratos , Ratos Wistar , Distribuição TecidualRESUMO
This work compared the predicted dose to an individual due to exposure from a radioactive patient using three models (point, line, and volume), for three therapeutic regimens (hyperthyroidism, thyroid cancer, and non-Hodgkin's lymphoma). For the volume source calculations, Monte Carlo simulations employing the Visual Monte Carlo (VMC) code and the voxel phantom FAX were used. For hyperthyroid patients, the point, line, and volume source models predicted doses to exposed individuals of 54, 24, and 14 mSv, respectively, at a distance of 0.3 m, and 4.8, 4.0 and 3.3 mSv at a distance of 1 m. For thyroid cancer patients, the dose values were 85, 38, and 18 mSv at 0.3 m, and 7.6, 6.4, and 4.4 mSv at 1 m, respectively. For non-Hodgkin's lymphoma (NHL) subjects, the doses were 230, 103, and 36 mSv at 0.3 m, and 21, 17, and 10 mSv at 1 m. These results show that patient release based on point source calculations involves unnecessary conservatism.
Assuntos
Exposição Ambiental/análise , Modelos Biológicos , Medicina Nuclear , Doses de Radiação , Adulto , Feminino , Humanos , Hipertireoidismo/radioterapia , Dosagem Radioterapêutica , Neoplasias da Glândula Tireoide/radioterapiaRESUMO
Radioactive patients may expose others after radiopharmaceutical administrations, and evaluation of the absorbed dose or exposure rates close to patients is important in keeping radiation doses as low as reasonably achievable. Two theoretical exposure models, point source and line source models, are frequently used to calculate exposure or dose rates without the support of actual measurements. If measurements of exposure rates were performed near patients, an experimental exposure model could be implemented. When measurements of exposure rates are performed, these measurements are made inside therapy rooms or other confined places, in which case scattered radiation may significantly influence the measurements. In this study we measured exposure rates from radioactive patients without the influence of scattered radiation and determined correction factors for the theoretical exposure models. The exposure rates from a total of 110 radioactive patients were measured at 1.0 h after oral administration of Na131I for thyroid therapy; the results +/-1 SD at distances of 0.5, 1.0, 1.5, 2.0, 3.0, and 4.0 m in front of the patients were (29 +/- 6), (9.9 +/- 1.7), (4.6 +/- 0.9), (2.7 +/- 0.5), (1.31 +/- 0.25) and (0.74 +/- 0.12) x 10(-10) C kg(-1) MBq(-1) h(-1) [1.0 x 10(-10) C kg(-1) MBq(-1) h(-1) = 14.34 x 10(-6) R mCi(-1) h(-1)], respectively. To obtain more accurate estimates of the actual exposure rates from patients using the theoretical exposure models, we found that correction factors should be applied; the functions CFEM = 1.19 + 32.80e(5.92D) and CFLS = 0.022LnD + 0.639 describe these correction factors for distances less than or equal to 1.0 m from the patients for experimental and line source exposure models, respectively. The function that describes the correction factors to the point source model is CFPS = 0.224LnD + 0.638 at the same distances; applying these correction factors leads to a reduction from 56% to 1% in the difference between measured exposure rates and theoretical exposure rates calculated by the point source exposure model at a distance of 1.0 m from patients. The results given here provide more accuracy in evaluation of exposure rates and consequently absorbed doses near radioactive patients and allow for more effective radiological protection procedures during patient management.
Assuntos
Radioisótopos do Iodo/uso terapêutico , Monitoramento de Radiação , Proteção Radiológica , Compostos Radiofarmacêuticos/uso terapêutico , Adolescente , Adulto , Idoso , Idoso de 80 Anos ou mais , Feminino , Humanos , Hipertireoidismo/radioterapia , Radioisótopos do Iodo/efeitos adversos , Masculino , Pessoa de Meia-Idade , Compostos Radiofarmacêuticos/efeitos adversos , Neoplasias da Glândula Tireoide/radioterapiaRESUMO
The measurement of exposure rates is fundamentally important in the release of patients given radioactive materials and for keeping the exposures of others as low as reasonable achievable. Similar measurement methodologies have generally been used for point and extended sources, but this approach may lead to methodological errors in calculating radiation dose estimates. In this study, nuclear medicine patients who received high activities of Na131I for therapy were monitored using different measurement methodologies, and the results showed that the usual measurement performed at 1.0 m in front of the body resulted in a mean error of 40% between experimental and theoretical exposure rates. The best measurements were obtained when performed at 2.0 m in front of the patients. With this approach, the error was about 2% between experimental and theoretical values. These findings suggest a new methodology for patients' measurement in nuclear medicine and could be useful for personal monitoring in cases of radiological emergencies involving 131I ingestion.
Assuntos
Hipertireoidismo/radioterapia , Proteção Radiológica , Neoplasias da Glândula Tireoide/radioterapia , Adolescente , Adulto , Idoso , Idoso de 80 Anos ou mais , Feminino , Humanos , Radioisótopos do Iodo/uso terapêutico , Masculino , Pessoa de Meia-Idade , Medicina Nuclear , Doses de Radiação , Monitoramento de Radiação , Radiometria , Reprodutibilidade dos Testes , Estudos RetrospectivosRESUMO
The evaluation of the absorbed dose from radioactive patients during the treatment of thyroid disease is an important factor in establishing precautions in these procedures, and the I retention/excretion by patients' bodies provides additional information to medical and radioprotection service. In 94 patients, the measurement of exposure rates was performed over 7 d following NaI administration, and the rates permitted the study of the dynamics of excretion and the potential dose evaluation. The administered activities ranged from 3.7 GBq (100 mCi) to 16.65 GBq (450 mCi), and the results proved that the majority of the activity is excreted by patients in the first 3 d after NaI administration. The average (131)I activity excreted at 24, 48, 72, 96, and 120 h after oral administration was (72 +/- 10), (91 +/- 6), (97 +/- 3), (98.9 +/- 1.5), and (99.6 +/- 0.7)%, respectively. According to the administered activity, the evaluation of the accumulated absorbed dose from patients ranged from 3.0 +/- 0.7 to 8.4 +/- 1.1 mSv at 1 m and 1.2 +/- 0.4 to 3.2 +/- 0.4 mSv at 2 m. The data reported here are important to radioprotection policy and to add to and improve on the guidelines reported in U.S. NRC Regulatory Guide 8.39.
Assuntos
Radioisótopos do Iodo/farmacocinética , Radioisótopos do Iodo/uso terapêutico , Modelos Biológicos , Medição de Risco/métodos , Neoplasias da Glândula Tireoide/metabolismo , Neoplasias da Glândula Tireoide/radioterapia , Contagem Corporal Total/métodos , Adolescente , Adulto , Idoso , Idoso de 80 Anos ou mais , Carga Corporal (Radioterapia) , Brasil/epidemiologia , Simulação por Computador , Feminino , Meia-Vida , Humanos , Radioisótopos do Iodo/análise , Radioisótopos do Iodo/química , Masculino , Taxa de Depuração Metabólica , Pessoa de Meia-Idade , Compostos Radiofarmacêuticos/análise , Compostos Radiofarmacêuticos/química , Compostos Radiofarmacêuticos/farmacocinética , Compostos Radiofarmacêuticos/uso terapêutico , Eficiência Biológica Relativa , Estudos Retrospectivos , Fatores de RiscoRESUMO
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.