RESUMO
The computer code VARSKIN, version 5.3, is widely used to calculate superficial dose caused by the routine handling of radioactive substances or in skin contamination incidents. It allows a variety of source configurations, points, volume, surface and syringe-like (cylindrical) and a variety of exposure situations such as direct skin contact or exposure through clothing. However, there is a need for more benchmarking data of VARSKIN, especially for beta particles, with complex irradiation geometries. Dose calculations using MCNP5 and VARSKIN 5.3 for a variety of mass-less point beta-emitting sources were performed. Both programs gave comparable results that are in good agreement with published dose rate conversion factors for sources on contact with the skin or with fabric. However, important differences appear, with VARSKIN 5.3 values as much as 40% below the Monte Carlo results, when an air gap of a few mm is introduced between the fabric and skin.
Assuntos
Partículas beta , Exposição à Radiação/análise , Pele/efeitos da radiação , Vestuário , Simulação por Computador , Humanos , Método de Monte CarloRESUMO
On leaving the irradiated fuel bay at Pickering A nuclear power station, a worker triggered a whole body monitor alarm with activity in or on his head, and despite careful decontamination techniques he subsequently swallowed a hot particle. Over the next 3 d, the radioactivity was tracked through the body. It was then excreted in a single faecal sample and recovered for physical and radiochemical analysis. This analysis demonstrated that the particle contained 330 kBq of 60Co and only traces of other radioactivity. Its dimensions were approximately 50-130 microm and its composition was consistent with that of Stellite 6. A dose assessment was carried out taking into account the residence time of the particle in the mouth and its transit through the body. The estimated committed effective dose was 1.4 mSv, and the equivalent dose to the maximally exposed 1 cm2 of skin, 81 mSv.
Assuntos
Radioisótopos de Cobalto/análise , Radioisótopos de Cobalto/farmacocinética , Modelos Biológicos , Exposição Ocupacional/análise , Radiometria/métodos , Contagem Corporal Total , Carga Corporal (Radioterapia) , Canadá , Radioisótopos de Cobalto/química , Simulação por Computador , Humanos , Reatores Nucleares , Especificidade de Órgãos , Tamanho da Partícula , Doses de Radiação , Eficiência Biológica Relativa , Reprodutibilidade dos Testes , Sensibilidade e EspecificidadeRESUMO
The energy response of standard (TLD-100) and high-sensitivity (TLD-100H) LiF thermoluminescence dosemeters (TLDs) has been studied for photon beams with mean energies from about 25 keV to 1100 keV. Canadian primary standards for air kerma were used to establish the air kerma rates for each of the photon beams. TLDs were mounted in a PMMA holder and the air kerma response was measured as a function of energy. The EGSnrc Monte Carlo code was used to model the TLD holder and calculate the absorbed dose to the TLD chip per unit air kerma for each beam. The measured and calculated results were combined to obtain the intrinsic dose response of the TLD chip. Broadly, our results are consistent with existing data, which show a marked difference in the energy dependence of the two materials. However, the precision of our measurements (standard uncertainty of about 0.6%) has permitted the identification of features that have not been noted before. In particular, the energy dependence of the two materials is quite different in the important energy region delimited by 137Cs and 60Co gamma rays.
