This study investigates the radioactivity concentrations in contaminated soil samples, comprising TENORM-contaminated soil from an oilfield and artificially contaminated soil containing 137Cs. The primary objective was to examine the correlation between soil grain size distribution and radionuclide concentrations within these samples. Radioactivity measurements were conducted using a broad-energy HPGe gamma-spectroscopy system with 50 % relative efficiency. Both soil samples were systematically fractionated into seven distinct size categories through mechanical sieving, ranging from < 37 ?m (400 mesh) to >900?m (20 mesh) in diameter. Results demonstrate that radionuclide activity concentrations in TENORM samples exhibit significant variation across particle size fractions, with the exception of ^{40}\mathrm{K} . The highest activity concentrations were consistently observed in the finest particle fraction (?37.5 ?m). Similarly, ^{137}\mathrm{Cs} activity in the artificially contaminated soil exhibits fraction-dependent distribution, with peak concentrations in particles ?63 ?m. Statistical analysis revealed strong reverse correlations between particle size and radionuclide concentration: correlation coefficients of r = -0.647 and r = -0.710 were obtained for ^{228}\mathrm{Ra} and ^{226}\mathrm{Ra} , respectively (p-value ? 0.008 and p ? 0.04), while ^{137}\mathrm{Cs} demonstrated an even stronger reverse correlation (r = -0.930, p ? 0.02). These findings provide essential guidance for advancing targeted soil remediation strategies and optimizing mechanical separation techniques at radioactively contaminated sites, with direct implications for radiation protection practices and environmental risk assessment.
ERRATUM. In the article. ASSESSMENT OF REFERRING PHYSICIANS AWARENESS AND KNOWLEDGE OF RADIATION PROTECTION AND PATIENT EXPOSURE IN DIAGNOSTIC IMAGING by Radmila R. ZERAVICA, Jelena J. SAMAC, Marija V. VUKMIROVIC PAPUGA, Ana J. JAKOVLJEVIC, Dragan V. BURIC, Veljko M. CRNOBRNJA, and Tanja M. SASIC OSTOJIC published in the journal Nuclear Technology & Radiation Protection, 40 (2025), 3, pp. 246-252, the e-mail address of corresponding author was printed inncorrectly. It should be as folows: jelena.samac@mf.uns.ac.rs Editorial Board offers an apology for this mistake to the corresponding author and readers of the Nuclear Technology & Radiation Protection journal. Link to the corrected article 10.2298/NTRP2503246Z
In this study, a PbO, MnO2, PbO + MnO2 thin film (nano layer) was deposited onto a microscope glass, indium tin oxide glass, and aluminum with thicknesses 0.1 mm and 0.5 mm substrate, samples were prepared by the thermal spray technique. The coating of thin films was carried out onto the substrate at a temperature of 35?C, furthermore, the prepared shield films were annealed at 100?C and 250?C for one hour. The shielding efficiency of each thin film on each substrate at different temperatures was analyzed using radioactive source 60Co and NaI(Tl) well-type scintillation detector. The experimental results obtained were summarized: adding PbO or MnO2 thin film together or separately to the substrate increases the attenuation of gamma-rays depending on the type of samples and annealed temperature. The minimum gamma reduction rate was found 0.3 % for indium tin oxide glass deposited with MnO2 and annealed at 250?C while the maximum was found in Al with thickness 0.1 mm (9.6 %) deposited with both PbO or MnO 2 together. This means that shielding efficiency increases by increasing the thickness of the thin film, annealed temperature and substrate type.
Oil-based mud is one of the primary wastes produced in oil industries that may contain elevated amounts of naturally occurring radioactive material. In this study, MCNPX simulations and gamma-ray spectrometry measurements were combined and a quick and sensitive method was developed for the non-destructive radiological characterization of spent oil-based mud originating from the oil industry by using a 3.81 cm x 3.81 cm LaBr3(Ce) scintillator. By this method, one cubic meter of packaged oil-based mud can be radiologically characterized in less than 20 minutes.
This paper aims to determine the need for additional imaging verification when using the auto beam hold function in radiotherapy of prostate cancer patients with inserted gold fiducial markers. Forty patients who underwent irradiation of the prostate and twenty with prostate and pelvic lymph node radiotherapy were included in the retrospective study. Intrafraction shifts during irradiation were compared with the auto beam hold function in the translational directions. The function was used with time tracking (5 seconds), a tolerance limit for marker deviations (4 mm), and bone structures in the large irradiation field (5 mm). The need for additional image verification was higher in the larger irradiation field group. When translational shifts were analysed, a statistically significant difference in the vertical direction was found in the group with only prostate irradiation (p = 0.013). A statistically significant difference in the lateral direction was found in the group with a larger irradiation field (p = 0.021). Translational shifts were not statistically significantly different between the two groups (p > 0.05). Conclusion: Intrafraction shifts of the prostate increase the need for additional imaging verification. The use of the auto beam hold function is effective in reducing errors.
Sergei Ivannikov, Nikita Markin, Veniamin Zheleznov
A determination option for 238U in solutions by the neutron activation analysis was investigated. A radionuclide treatment based on 252Cf was used as a neutron source. The limit for the determination of uranium using thermal neutrons of 0.1 mgL?1 was determined within the research framework. With the help of the preliminary concentration of the sample via the evaporation method, it is possible to further reduce the detection limit by 2-5 times. It is defined that the optimal time for measuring the induced activity of the sample when working with a short-life isotope of 239U, is 30 minutes. The influence of the effects of scattering and self-absorption of gamma radiation of the uranium line 74.6 keV on the results of the neutron activation analysis was determined. The studies conducted made it possible to determine uranium by the neutron activation analysis method in solutions of various compositions, in a wide range of concentrations.
Ghonche Baghban, Mohsen Shayesteh, Majid Bahonar
et al.
An accurate analysis of the flow transient is very important in safety evaluation of a nuclear power plant. In this study, analysis of a WWER-1000 reactor is investigated. In order to perform this analysis, a model is developed to simulate the coupled kinetics and thermal-hydraulics of the reactor with a simple and accurate numerical algorithm. For thermal-hydraulic calculations, the four-equation drift-flux model is applied. Based on a multi-channel approach, core is divided into some regions. Each region has different characteristics as represented in a single fuel pin with its associated coolant channel. To obtain the core power distribution, point kinetic equations with different feedback effects are utilized. The appropriate initial and boundary conditions are considered and two situations of decreasing the coolant flow rate in a protected and unprotected core are analyzed. In addition to analysis of normal operation condition, a full range of thermal-hydraulic parameters is obtained for transients too. Finally, the data obtained from the model are compared with the calculations conducted using RELAP5/MOD3 code and Bushehr nuclear power plant data. It is shown that the model can provide accurate predictions for both steady-state and transient conditions.
Mladen Nikolic, David Simovic, Milija Zecevic
et al.
Building materials are the second major source of indoor radon, after soil. The contribution of building materials to indoor radon amount depends upon the radium content and exhalation rates, which can be used as a primary index for radon levels in the dwellings. This paper presents the results of using the experimentally determined exhalation rates of siporex blocks and concrete plates, to assess the radiation exposure in dwellings built of siporex blocks. The annual doses in rooms have been estimated depending on the established modes of ventilation. Realistic scenario was created to predict an annual effective dose for an old person, a housewife, a student, and an employed tenant, who live in the same apartment, spending different periods of time in it. The results indicate the crucial importance of good ventilation of the living space.
Gholamreza Moradi, Asghar Sadighzadeh, Rasoul Yarahmadi
et al.
The objectives of this research were to determine the levels of radioactivity in the Tehran research reactor containment and to investigate the mass-size distribution, composition, and concentration of radionuclides during operation of the reactor. A cascade impactor sampler was used to determine the size-activity distributions of radioactive aerosols in each of the sampling stations. Levels of a and b activities were determined based on a counting method using a liquid scintillation counter and smear tests. The total average mass fractions of fine particles (particle diameter dp < 1 mm) in all of the sampling stations were approximately 26.75 %, with the mean and standard deviation of 52.15 ? 19.75 mg/m3. The total average mass fractions of coarse particles were approximately 73.2%, with the mean and standard deviation of 71.34 ? 24.57 mg/m3. In addition to natural radionuclides, artificial radionuclides, such as 24Na, 91Sr, 131I, 133I, 103Ru, 82Br, and 140La, may be released into the reactor containment structure. Maximum activity was associated with accumulation-mode particles with diameters less than 400 nm. The results obtained from liquid scintillation counting suggested that the mean specific activity of alpha particles in fine and coarse-modes were 89.7 % and 10.26 %, respectively. The mean specific activity of beta particles in fine and coarse-modes were 81.15 % and 18.51 %, respectively. A large fraction of the radionuclides' mass concentration in the Tehran research reactor containment was associated with coarse-mode particles, in addition, a large fraction of the activity in the aerosol particles was associated with accumulation-mode particles.
The objective of this study is to model the impact of uncertainties in the engineering specifications of a typical p-type HPGe detector on the efficiency values when the measured soil sample is in contact geometry with the detector. We introduce a parameter named the normalized sensitivity impact which allows a comparative analysis to be made of the impact of the detector specification uncertainties and develop a correction factor table for the most important parameters. The areas of the detector most susceptible to error were found to be the crystal geometry, vacuum layer above the crystal and the bulletizing radius. In all cases the major impacts were mathematically modeled - for the first time - and found to vary either quadratically or logarithmically over the energy range of 180 keV to 1500 keV. Finally, we propose a set of detector characterization values that may be used in ANGLE for generating a reference efficiency curve using the efficiency transfer method inherent in this software. These values are to be used with the understanding that their uncertainty impact on the full-peak efficiency though not very significant in this counting arrangement, is not non-zero.
Radioactivity levels in building materials, collected from the Islamabad capital territory have been determined by using a gamma spectrometric technique. Measured specific activities of 226Ra, 232Th, and 40K in material samples ranged from 8 ? 1 to 116 ? 6 Bq/kg, 9 ? 1 to 152 ? ? 5 Bq/kg, and 29 ? 6 to 974 ? 23 Bq/kg, respectively. The radium equivalent activity, absorbed dose rate, annual effective dose, and gamma index were evaluated from the measured amounts of radioactivity to assess the radiation hazard associated with the studied building materials. The mean radium equivalent activity, the absorbed dose rate and annual effective dose estimated ranged from 81 ? 6 to 221 ? 11 Bq/kg, 38 ? 3 to 104 ? 5 nGy/h, and 0.23 ? 0.02 to 0.64 ? 0.03 mSv, respectively. The ranges of the calculated Raeq were found to be lower than the values recommended for construction materials (370 Bq/kg). The mean values of the internal and external hazard indices were found in the range of 0.30 ? 0.02 to 0.78 ? 0.05 and 0.22 ? 0.02 to 0.60 ? 0.03, respectively. The results of the materials examined indicate no significant radiological hazards arise from using such material in building construction.
Nevenka Antovic, Danilo Boskovic, Nikola Svrkota
et al.
Soil samples from Mojkovac, Montenegro, were analyzed by standard gamma-spectrometry for radioactivity due to 226Ra, 232Th, 40K, and 137Cs. Average activity concentrations have been found to be 28.6, 43.1, 620.8, and 55 Bq/kg, respectively. In order to evaluate the radiation hazard, radium equivalent activity, absorbed dose rate, annual effective dose, external and internal hazard indexes, and the annual gonadal dose equivalent were determined and found to be at an average of 133.79 Bq/kg, 65.18 nGy/h, 79.93 mSv/y, 0.37, 0.45, and 0.46 mSv/y, respectively. With life expectancy taken to be 70 years, a mean lifetime outdoor gamma radiation was calculated as 5.6 mSv, yielding a lifetime cancer risk of 2.8?10-4.
Marija Jankovic, Dragana Todorovic, Zita Keleman
et al.
Tritium (3H) present in the environment decreased in the last decades and nowadays it has low activity concentrations. Measurement of low-level tritium activities in natural waters, e. g. in precipitation, groundwater, and river water requires special techniques for water pretreatment and detection of low-level radioactivity. In order to increase the tritium concentration to an easily measurable level, electrolytic enrichment must be applied. This paper presents the enrichment method performed by electrolysis in a battery of 18 cells, giving an enrichment factor of 5.84 (calculated from 59 electrolyses). The calculated mean values of the separation factor and enrichment parameter were 4.10 and 0.84, respectively. Results for tritium activity in precipitation and surface water collected in Belgrade during 2008 and 2009 are presented. The Radiation and Environmental Protection Department of the Vinca Institute of Nuclear Sciences, participated in the IAEA TRIC2008 international intercomparison exercise. The participation in the intercomparisons for any laboratory doing low-level 3H measurements in the waters is very important and useful. It is considered the best way to check the entire procedure and methods of the measurements and the reliability of the standard used. The analysis of the reported 3H activity results showed that all results for five intercomparison samples, for which electrolytic enrichment were applied prior to the 3H measurement, are acceptable.
Nenad Stevanovic, Vladimir Markovic, Momir Arsenijevic
et al.
In this paper the stopping power was calculated, representing the electrons of the target atom as an assembly of quantum oscillators. It was considered that the electrons in the atoms have some velocity before interaction with the projectile, which is the main contribution of this paper. The influence of electron velocity on stopping power for different projectiles and targets was investigated. It was found that the velocity of the electron stopping power has the greatest influence at low energies of the projectile.