Dose assessment for releases from medical installations in the city of Rio de Janeiro.

The values of effluent releases to urban sewage system in Brazilian regulation were investigated and compared with the current International Atomic Energy Agency recommended criteria, using the city of Rio de Janeiro as a case study. Deterministic and probabilistic assessments were performed for two conservative scenarios, considering the exposure of the population in general and the exposure of workers in sewage treatment plants. The results from the deterministic assessment were found to be more restrictive than those from the probabilistic assessment. Although currently the doses for the inhabitants of Rio de Janeiro are lower than the dose limit for the public, the approach currently in use in Brazil is not adequate to fulfill the international requirements and nuclide-specific values needing to be adopted.

Spectrally average conversion coefficients for air kerma to ambient dose equivalent for clinical linear accelerator.

This work aims to calculate the conversion coefficients from air kerma to ambient dose equivalent, H*(10)/K(air) for photon beams produced by linear accelerators, such as the Clinac-4, Clinac-6, Clinac-18 and Clinac-2500, after transmission through primary barriers of radiotherapy treatment rooms. Concrete walls of thickness 1.0, 1.5 and 2.0m were irradiated with 30cmx30cm primary beam spectra. The transmitted spectra were calculated to obtain the conversion coefficients for beams found in radiotherapy services. The calculations were done using the MCNP-4B Monte Carlo code. The results indicate the need to use a factor of about 1.20 to obtain the ambient dose equivalent for radiation surveys near primary barriers using instruments calibrated in air kerma.

Use of a bioindicator system in the study of the mutagenetical effects in the neighborhoods of deposits of radioactive waste.

The purpose of the research described in this paper was to analyze the biological mutational effects caused by low doses of ionizing radiation on biological samples placed nearby and around deposits of radioactive waste, as a way of monitoring the environment close to them. In order to do this, the plant Tradescantia pallida was chosen, and through micronuclei tests the sensitivity of the dose/response to bio-monitoring could be observed. The plants were exposed for a period of 24h in previously chosen sites around Brazil, within the proximity of nuclear waste deposits. In each location, three points were chosen for bio-monitoring. The results obtained at these locations showed a small increment in the frequency of micronuclei per cell of the biosensor. From these data, a scale of mutagenesis effects due to low-dose radiation was built up. T. pallida is a good alternative for environmental bio-monitoring in tropical climates, as it is an excellent alternative tool in the studies of the effects of ionizing radiation on the environment.

Calculation of dose components in head phantom for boron neutron capture therapy.

Application of neutrons to cancer treatment has been a subject of considerable clinical and research interest since the discovery of the neutron by Chadwick in 1932 (3). Boron neutron capture therapy (BNCT) is a technique of radiation oncology which is used in treating brain cancer (glioblastoma multiform) or melanoma and that consists of preferentially loading a compound containing 10B into the tumor location, followed by the irradiation of the patient with a beam of neutron. Dose distribution for BNCT is mainly based on Monte Carlo simulations. In this work, the absorbed dose spatial distribution resultant from an idealized neutron beam incident upon ahead phantom is investigated using the Monte Carlo N-particles code, MCNP 4B. The phantom model used is based on the geometry of a circular cylinder on which sits an elliptical cylinder capped by half an ellipsoid representing the neck and head, both filled with tissue-equivalent material. The neutron flux and the contribution of individual absorbed dose components, as a function of depths and of radial distance from the beam axis (dose profiles) in phantom model, is presented and discussed. For the studied beam the maximum thermal neutron flux is at a depth of 2 cm and the maximum gamma dose at a depth of 4 cm.

The use of neutron radiography in agriculture to improve the food quality.

The report presented in the 7th ONU's Conference (USA, 2001) about climatic changes that took place at the end of 2001 informs that, in less than 50 years, more than 45% of the world population will be suffering from lack of water. This fact occurs by the absence of management on water resources, mainly, in agriculture. As the excess as the lack of humidity in soil can change the harvest quality, causing physiologic anomalies in food and promoting soil diseases incidence caused by bacteria and fungus. In order to establish a larger control in the food quality, a study has been performed, through the neutron radiographic technique, that proposes the optimization of agricultural harvests in relation to the minimum quantity of water necessary for the plant to develop and, also, of the soil compactness. Thus, neutron radiographic images of the system root-soil can be produced so that each root will be evaluated for its ability to penetrate in the soil layers, having the advantage of not interfering in this system what it is not possible through the usual techniques yet. The initial tests using bean roots showed that the soil thickness, which involved the roots, resulted in low contrast images, what impeded their visualization with enough clearness so that their grow could not be observed. For this reason, it was opted to the gadolinium as a contrast agent so that we have been studying its transport through the roots.