Man is continuously exposed to ionizing radiation because of the presence of naturally occurring radioactive materials (NORM) in the environment. Various technological processes of processing and using of materials that contain natural radionuclides generate materials of enhanced natural radioactivity (TENORM). The largest contribution to irradiance with natural sources of ionizing radiation is the exposure of the population to indoor radon. This gas originates from the radioactive decay of 226Ra and 224Ra that are present in the soil under houses and building materials. Depending on the type of building materials, indoor exposure to radon at dwellings and workplaces can be over a thousand times greater than in outdoor space. In Bosnia and Herzegovina, no valid and comprehensive radiological studies on the building materials have been performed that would guarantee for their dosimetric safety use for installation in residential and industrial buildings, highways, as well as their application for other purposes. The quantification of the radon levels that comes from building materials is a necessary and very important part of the global protection of the population from ionizing radiation. This paper presents the first results of a study on the radon activity concentrations in building materials used in Bosnia and Herzegovina. Measurements were performedwith a professional Alpha GUARD system. The mean values of the activity concentration of the exhaled radon of investigated building materials varied from 10 Bqm-3 to 101 Bqm-3, radon exhalation rate values ranged from 77.0 mBqm-2h-1 to 777.7 mBqm-2h-1. Gamma dose rate was in the range 57–112 nSv h−1.
Abstract The results of the specific activities of 232Th, 226Ra and 40K measured in samples of commonly used building materials in Bosnia and Herzegovina are presented. Measurements were performed by gamma-ray spectrometer with coaxial HPGe detector. The surface radon exhalation and mass exhalation rates for selected building materials were also measured. The determined values of specific activities were in range from 3.16±0.81 Bq kg−1 to 64.79±6.16 Bq kg−1 for 232Th, from 2.46±0.95 Bq kg−1 to 53.89 ±3.67 Bq kg−1 for 226Ra and from 28.44±7.28 Bq kg−1 to 557.30±93.38 Bq kg−1 for 40K. The radium equivalent activity, the activity concentration index, the external and internal hazard indices as well as the absorbed dose rate in indoor air and the corresponding annual effective dose, due to gamma-ray emission from the radioactive nuclides in the building material, were evaluated in order to assess the radiation hazards for people. The measured specific activities of the natural radioactive nuclides in all investigated building materials were compared with the published results for building materials from other European countries. It can be noted that the results from this study are similar to the data for building materials from neighbouring countries and for building materials used in the EU Member States. The radiological hazard parameters of the building materials were all within the recommended limits for safety use.
Live beings on earth have always been exposed to radiation from nature and more recently from artificial sources of radiation. The main components of radiation from nature are cosmic rays, terrestrial gamma ray, ingestion, and inhalation of natural radionuclides. On normal occasions, terrestrial sources are responsible for most of human exposure to natural radiation. These are, above all, radionuclides that are members of the three natural radioactive series: uranium-radium (238U), uranium-actinium (235U), and thorium series (232Th). Usually, the radionuclides on the beginning of these three radioactive chains are called primordial or primary natural radionuclides. All members of these series are genetically linked and are the result of the successive decay of the first member of the series, which explains the law of radioactive decay. Natural radioactivity is the occurrence of atomic core decomposition that exists in nature, without external influences, at which alpha particles (helium nucleus), beta particles (electrons and positron), and cosmic rays (photons) are emitted.
Abstract Investigations of natural radioactivity in water, air, and soil are conducted frequently and routinely. Exposure to high concentrations of natural radioactive radon gas can cause irradiation of respiratory organs, which can lead to lung cancer. This paper presents measurements of radon activity concentrations in dug wells and natural springs of the Tuzla area (Bosnia and Herzegovina), which ranged from 214 to 3702 mBq L-1. Our results have shown that the radon activity concentration did not exceed the EU reference level for radon in drinking water (100 Bq L-1).
Radon is a colorless, odorless, radioactive gas. It is formed naturally from the decay of radioactive elements, such as uranium, which are found in different amounts in soil and rock throughout the world. Radon gas in the soil and rock can move into the air and into underground water and surface water. In this paper the results of measurements of radon activity concentration in drinking water from drilled wells in Tuzla City, Bosnia and Herzegovina are presented. The obtained results of radon activity concentration in drinking water samples ranged from 182 mBqL-1 to 2368 mBqL-1 which does not exceed the value of 11.1 BqL-1 recommended by the Environmental Protection Agency for drinking water. The measurements of radon activity concentration were conducted with AlphaGUARD and AquaKIT equipment (Genitron Instruments).
Abstract With gamma spectrometric method 23 samples of mineral and thermal waters of Bosnia and Herzegovina were analyzed. Activity concentrations of the investigated radionuclides were in the range 12–346 mBq·L−1 for 40K, 1.1–791 mBq·L−1 for 226Ra, 0.2–221 mBq·L−1 for 228Ra, 13–367 mBq·L−1 for 238U, and 0.6–17 mBq·L−1 for 235U. For all investigated radionuclides annual effective dose was estimated. The estimated total annual committed effective dose received by population as a result of ingestion of water was in the range 0.11–2.51 μSv·y−1 for thermal water and in the range 0.11–38.8 μSv·y−1 for mineral water. Measurement of activity concentrations of natural radionuclides in the examined samples was carried out with a gamma-spectrometer with high-purity germanium (HPGe) detector, having a relative efficiency of 70%.
The results of activity concentration measurements of natural occurring radioactive nuclides 238U, 235U, 232Th, 226Ra, and 40K in surface soil samples collected in the area of cities Tuzla and Lukavac, northeast region of Bosnia and Herzegovina were presented. Soil sampling was conducted at the localities that are situated in the vicinity of industrial zones of these cities. The measured activity was in the range from (8 ± 4) to (95 ± 28) Bq kg–1 for 238U, from (0.41 ± 0.06) to (4.6 ± 0.7) Bq kg–1 for 235U, from (7 ± 1) to (66 ± 7) Bq kg–1 for 232Th, from (6 ± 1) to (55 ± 6) Bq kg–1 for 226Ra, and from (83 ± 12) to (546 ± 55) Bq kg–1 for 40K. In order to evaluate the radiological hazard of the natural radioactivity for people living near industrial zones, the absorbed dose rate, the annual effective dose and the radium equivalent activity have been calculated and compared with the internationally approved values.
By coal mining and exploatation, radioactive radon gas, which is captured in natural geological structures, is reallocated from the deep coal layers. Hence it is concentrated in the depots and coal seams of the mines or being transported to the surface of the earth where it can significantly change the levels of radioactivity in the working premises and residences. This paper presents the results of a three-year research of radon activity concentration in the air in hole and surface coal mines of Bosnia and Herzegovina. Detected concentrations of radon in the coal gaseous structure, atmosphere and other ambient media are in correlation with the properties of geological structures, technology for obtaining coal and meteo-climatic changes. They were measured with Alpha GUARD PQ 2000 radon portable measuring system (instruments Genitron-Frankfurt) and RadoMeter 2000 (Radosys LTD. Budapest), using the SS-NTD method.
It is often necessary to estimate the exposure rate at a distance from radionuclide emitting gamma or X rays. Such calculations may be required for planning radiation protection measures around radioactive sources, for calibration radiation monitoring instruments, for patient containing radionuclides or for estimating the absorbed dose to patients receiving brachytherapy. The factor relating activity and exposure rate has been various names: the k factor (Johns, 1961), the specific gamma ray constant (ICRU Rep. 10a, 1962), exposure rate constant (Parker et al., 1978) and gamma rate constant (Kereiakes & Rosenstein, 1980). Conversion to SI units required that this factor be replaced by the air kerma rate constant which is now defined as: = 2 l A ( air dK dt ) (1)
The aim of this paper is to identify potential exposure of the workers in the coal mine Tusnica. The results of the investigation showed increased activity of brown coal up to 1060 ± 88 Bq kg(-1) for (238)U, 976 ± 30 Bq kg(-1) for (226)Ra and 118 ± 31 Bq kg(-1) for (232)Th. Dose rate measurements ranged from 0.07 to 0.25 µSv h(-1). The annual effective dose, taking into account external exposure to ambient gamma radiation and internal exposure due to inhalation of the resuspended dust, would be 1.6 mSv a(-1). The results presented lead to the conclusion that Tusnica coal mine contains brown coal with significant radioactivity, indicating that the working hours in the area should be regulated and the use of respiratory protective equipment is obligatory.
The results of indoor radon concentration survey in the area of the municipality of Bihac are presented. The results showed the average indoor radon activity concentration value of 82.1 Bq/m3. This result leads to the annual dose estimate of 1.65 mSv/y. There are localities in the municipality of Bihac with high concentration of indoor radon activity (above 150 Bq/m3) due to the fact that whole Bihac valley is situated on sediment rocks, which are of porous structure, and the most of the houses are built by the construction material manufactured from sediment rocks.
In Europe, officially until now, there have not existed pyramids built by ancient civilisations. In central Bosnia and Herzegovina, about 30 kilometres north from Sarajevo, there are suspected stone pyramids of monumental proportions. The hypothesis that Visocica Hill, having a noticeable pyramidal shape and rising over the town of Visoko, hides inside itself a step pyramid was developed by Semir Osmanagic, a brilliant Bosnian explorer and expert in pyramidal structures which he studied at locations around the world. Aiming to confirm this hypothesis, intensive researches were carried out at the sites of Visoko town and its vicinity in 2005 and 2006, through combination of classic geo-archeological methods and high-technology methods (satellite imagery, thermal analysis, georadar, seismic and electromagnetic methods, 3D topographic and geodetic high-resolution maps). Tens of world experts (including the leading Egyptian archeologists) undoubtedly confirmed that central B&H hides extraordinary important archeological site on a world scale. The idea of the researches shown in this paper is to determine with nuclear measuring methods whether the regular geometric stone blocks, some weighting over 25 tons, which were excavated at this site, originated from natural geologic processes or these are phenomena made by human hands. For that purpose samples were taken for analysis from stone blocks, soil, as well as from soil and stone structures in the network of underground corridors. In this paper we presented results of gamma spectrometry analysis of these samples, obtained with HPGe detectors.
It is often required to estimate the dose rate at a distance from radionuclides that are sources of X rays and gamma rays. Such calculations may be required for planning radiation protection measures in the vicinity of radioactive sources or patients containing radionuclides, calibrations of radiation instruments or for estimating the absorbed dose rate to patients receiving brachytherapy. The factor relating activity and air kerma rate is called air kerma rate constant--gamma(delta). In this paper, the results of recalculation of this quantity for unfiltered point sources of radionuclides in practice used most often are given. The calculations included corrections for internal conversion of X rays and gamma rays and detailed accounting of the generation of the K and L series X rays from internal conversion and electron capture. Particular air kerma rate constants were calculated for each discrete line in the photon spectrum of radionuclide with a yield per decay event >0.01% and the energy >20 keV. Since the energy structure of the photon spectra and accessible discrete numerical values of the mass energy-transfer coefficient for air are not the same, the cubic spline interpolation was used to obtained the coefficient, where the photon spectrum data are available. In the calculation, the latest gamma ray spectral data for all radionuclides and latest data for the mass energy-transfer coefficient for air are used. Air kerma rate constants for the following 35 radionuclides are calculated: 11C, 13N, 15O, 18F, 24Na, 42K, 43K, 51Cr, 52Fe, 59Fe, 57Co, 58Co, 60Co, 67Ga, 68Ga, 75Se, 99Mo, 99mTc, 111In, 113mIn, 123I, 125I, 131I, 127Xe, 133Xe, 137Cs, 152Eu, 154Eu, 170Tm, 182Ta, 192Ir, 197Hg, 198Au, 201Tl and 241Am.
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