ABSTRACT
Inhalation is the main route of internal exposure to radioactive aerosols in the nuclear industry. To assess the radiation dose from the intake of these aerosols, it is necessary to know their physical (aerodynamic diameter distribution) and chemical (dissolution rate in extracellular lung fluid) characteristics. Air samples were taken from the uranium processing plant at the Nuclear Research Center, Negev. Measurements of aerodynamic diameter distribution using a cascade impactor indicated an average activity median aerodynamic diameter value close to 5 microm, in accordance with the recent recommended values of International Commission on Radiological Protection (ICRP) model. Solubility profiles of these aerosols were determined by performing in vitro solubility tests over 100 d in a simultant solution of the extracellular fluid. The tests indicated that the uranium aerosols should be assigned to an absorption between Types M and S (as defined by the ICRP Publication 66 model).
Subject(s)
Aerosols/chemistry , Air Pollutants, Radioactive/analysis , Nuclear Reactors , Occupational Exposure/analysis , Radiometry , Uranium/chemistry , Aerosols/analysis , Israel , Particle Size , Radiation Dosage , Solubility , Uranium/analysisABSTRACT
For dose assessment of workers at Nuclear Research Center Negev exposed to natural uranium, spot urine samples are analysed and the results are normalised to 24-h urine excretion based on 'standard' man urine volume of 1.6 l d(-1). In the present work, the urine volume, uranium level and creatinine concentration were determined in two or three 24-h urine collections from 133 male workers (319 samples) and 33 female workers (88 samples). Three volunteers provided urine spot samples from each voiding during a 24-h period and a good correlation was found between the relative level of creatinine and uranium in spot samples collected from the same individual. The results show that normalisation of uranium concentration to creatinine in a spot sample represents the 24-h content of uranium better than normalisation to the standard volume and may be used to reduce the uncertainty of dose assessment based on spot samples.
Subject(s)
Occupational Exposure , Radiation Monitoring , Uranium/urine , Adult , Creatinine/urine , Female , Humans , Male , Middle AgedABSTRACT
The Organic Bound Tritium (OBT) amount in the body may induce changes in the evaluation of the internal exposure to tritium, due to its different retention time relative to HTO. OBT measurements for urine are not performed routinely, mainly because of the lengthy work needed in preparation of the samples, when using the standard oxygen combustion method. A simpler and more rapid method based on liquid scintillation counting (LSC) was employed, and an evaluation was performed to check its suitability for urine samples. The principle of the proposed method is based on subtracting the LSC counts of the water phase sample (HTO) from the total activity of the urine sample (OBT+HTO). A good correlation was found between the results obtained when applying the proposed direct method and the Gold standard method. The minimum detectable activity when using this method was determined.
Subject(s)
Biological Assay/methods , Models, Biological , Organic Chemicals/urine , Radiation Monitoring/methods , Radiation Protection/methods , Scintillation Counting/methods , Tritium/urine , Urinalysis/methods , Algorithms , Computer Simulation , Environmental Exposure/analysis , Humans , Internationality , Radiation Dosage , Reproducibility of Results , Sensitivity and SpecificityABSTRACT
A practical and simple method was employed to improve the minimum detectable activity (MDA) for lung counting measurements by summing several accumulated spectra. The method was checked for natural uranium, which produces peaks due to photon energies of 63.3, 92.6 and 185.7 keV. By combining nine measurements, an overall improvement of the MDA by a factor of about 3 was achieved. Uranium contamination levels lower than the MDA of a single spectrum could be detected with acceptable accuracy when analyzing the sum spectra. Specific results are given for four workers occupationally exposed to natural uranium.
Subject(s)
Biological Assay/methods , Lung/metabolism , Models, Biological , Nuclear Reactors , Occupational Exposure/analysis , Radiation Monitoring/methods , Uranium/pharmacokinetics , Algorithms , Computer Simulation , Humans , Internationality , Israel , Radiation Dosage , Radiation Protection/methods , Reproducibility of Results , Sensitivity and Specificity , Uranium/analysisABSTRACT
The recoil fragments from an alpha-emitting source may cause significant detector contamination. The simplest method to avoid the problem is to use a source coating. The influence of Mylar film coatings of different thickness on the resolution, efficiency and minimum detection level of an alpha spectrometry system was investigated. No significant deterioration of the system characteristics was observed when using thin films of about 0.25 mg/cm2.
