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1.
Radiat Prot Dosimetry ; 105(1-4): 317-20, 2003.
Article in English | MEDLINE | ID: mdl-14526977

ABSTRACT

The mining, milling and processing of uranium and thorium bearing minerals may result in radiation doses to workers. The control of occupational exposures from these natural sources of radiation imposes a challenge to regulators and radiation protection advisers. A survey pilot programme, which included six mines in Brazil and a monazite plant, was established, consisting of the collection and analysis of concentrations of uranium, thorium and polonium in urine, faeces and air samples. Results from workers were compared to background data from their families living in the same area and from residents from the population of Rio de Janeiro. Positive exposure results were identified among the coal miners, the niobium miners and the monazite sand workers. Difficulties in the application of internal dosimetry programmes are discussed in relation to the control of NORM workers.


Subject(s)
Air Pollution, Radioactive/analysis , Inhalation Exposure/analysis , Mining , Occupational Exposure/analysis , Radioisotopes/pharmacokinetics , Radiometry/methods , Administration, Inhalation , Administration, Oral , Humans , Pilot Projects , Polonium/administration & dosage , Polonium/analysis , Polonium/pharmacokinetics , Radiation Dosage , Radiation Protection/methods , Radioisotopes/analysis , Thorium/administration & dosage , Thorium/analysis , Thorium/pharmacokinetics , Uranium/administration & dosage , Uranium/analysis , Uranium/pharmacokinetics
2.
Radiat Prot Dosimetry ; 105(1-4): 483-5, 2003.
Article in English | MEDLINE | ID: mdl-14527013

ABSTRACT

The Whole Body Counter Facility (WBC) of IRD-CNEN in Brazil has been operating since 1986. The first system installed to perform in vivo measurements of low energy photon emitters radionuclides used Phoswich detectors. In 1998, the WBC unit was upgraded by the installation of an array of four low energy high purity germanium detectors. The performance and suitability of the detection system for lung measurements were evaluated by comparison with the annual dose limits and the detection limits obtained for 238U, 235U, 226Ra and 241Am. This evaluation determined whether the in vivo measurements are adequate. In order to compare the dose limit of 20 mSv y(-1), recommended by the International Commission on Radiological Protection (ICRP), with the in vivo monitoring technique, the minimum detectable intake (MDI) was calculated using the appropriate biokinetic models described in the ICRP Publications. The results were obtained for a single intake through inhalation. The AMAD considered was 5 microm.


Subject(s)
Equipment Failure Analysis , Lung/metabolism , Radiation Protection/instrumentation , Radioisotopes/analysis , Radioisotopes/pharmacokinetics , Transducers , Whole-Body Counting/instrumentation , Humans , Occupational Exposure/analysis , Photons , Radiation Dosage , Radiation Protection/methods , Radiometry/instrumentation , Radiometry/methods , Radiometry/standards , Reproducibility of Results , Sensitivity and Specificity , Whole-Body Counting/methods
3.
Radiat Prot Dosimetry ; 105(1-4): 549-52, 2003.
Article in English | MEDLINE | ID: mdl-14527025

ABSTRACT

A Monte Carlo program, Visual Monte Carlo (VMC) in vivo, was written to simulate photon transport through an anthropomorphic phantom and to detect radiation emitted from the phantom. VMC in vivo uses a voxel phantom provided by Yale University and may be used to calibrate in vivo systems. This paper shows the application of VMC in vivo to the measurement of 241Am deposited simultaneously in the thoracic region, the bones, the liver and in the rest of the body. The percentages of 241Am in the four body regions were calculated using the biokinetic models established by the ICRP, for a single intake via inhalation. The four regions of the voxel phantom were then 'contaminated' in accordance with the calculated percentages. The calibration factor of the in vivo system was then obtained. This procedure was repeated for the radionuclide distributions obtained 5, 30, 120, 240 and 360 days after intake. VMC in vivo was also used to calculate the calibration factor of the in vivo system in which the radionuclide was assumed to be deposited only in the lung, as is normally done. The activities calculated with the radionuclide distributed in the four body regions as a factor of time, and the activities calculated with the radionuclide deposited in the lung only are compared.


Subject(s)
Americium/pharmacokinetics , Knee Joint/metabolism , Liver/metabolism , Lung/metabolism , Models, Biological , Models, Statistical , Whole-Body Counting/methods , Americium/analysis , Computer Simulation , Humans , Inhalation Exposure/analysis , Metabolic Clearance Rate , Monte Carlo Method , Organ Specificity , Phantoms, Imaging , Photons , Radiation Dosage , Whole-Body Counting/standards
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