The work was aimed to evaluate the adaptation of acute radiation sickness patients, victims of the Chernobyl Nuclear Power Plant (ChNPP) accident and different radiation accidents, who underwent follow-up psychophysiological examination. Clinical and psychophysiological follow-up examination covered 32 acute radiation sickness patients –11 with severe and extremely severe grade, who underwent Chernobyl nuclear power station accident, and 21 acute radiation sickness patients from other radiation accidents. The authors demonstrated the leading role of such psychological traits as hypochondriasis, anxiety about health, emotional tension, anxiety, inclination to depression, frustration tension, low self-confidence, suspiciousness, diffidence, affective rigidity, discontentment about the situation and personal position in it, restriction of contact with others - decrease of the stenicity and integration of behavior, that caused adaptation disorders in a distant period among acute radiation sickness patients victims of the Chernobyl nuclear power station accident and in acute radiation sickness patients from other radiation accidents. Intellectual faculties (according to the Cattell test) and imaginative and logic thinking (Raven’s test) in the patients who underwent radiation accidents were not affected, but were higher than the average in acute radiation sickness patients victims of the Chernobyl nuclear power station accident, especially in the first 15 years of observation, and equaled to the intellectual level of acute radiation sickness patients from other radiation accidents in the following 15 years of observation.

1. Ф. Б. Березин, М. П Мирошников, Е. Д. Соколовa, Методика многостороннего исследования личности. Структура, основы интерпретации, некоторые области применения, 3. изд., Москва, Россия: Феликс Борисович, 2011. (F. B. Berezin, M. P. Miroshnikov, E. D. Sokolova, Method of multilateral study of personality. Structure, basis of interpretation, some areas of application, 3rd ed., Moscow, Russia: Felix Borsivich, 2011.)
2. К. Н. Логановский, А. И. Нягу, “Характеристика психических расстройств у пострадавших вследствие Чернобыльской катастрофы в свете МКБ-10 Социальная и клиническая психиатрия,” т. 5, но. 2, стр. 15 – 23, 1995. (K. N. Loganovsky, A. I. Nyagu, “Characteristics of mental disorders in victims of the Chernobyl disaster in the light of ICD-10,” Social and Clinical Psychiatry, vol. 5, no. 2, pp. 15 – 23, 1995.)
3. А. К. Наприенко, К. П. Логановский, “Пограничные нервно-психические расстройства у лиц, подвергшихся воздействию ионизирующего излучения,” Врачебное дело, но. 6, стр. 48 – 52, 1992. (A. K. Naprenenko, K. N. Loganovskiy. “Borderline neuropsychiatric disorders in persons exposed to ionizing radiation,” Medical work, no. 6. pp. 48 – 52, 1992.)
4. А. К. Напреенко, К. Н. Логановский, “Систематика психических расстройств, связанных с последствиями аварии на ЧАЭС,” Врачебное дело, но. 5-6, стр. 25 – 28, 1995. (A. K. Naprenenko, K. N. Loganovskiy, “Systematics of Mental Disorders Associated with the Consequences of the Chernobyl Nuclear power plant accident,” Medical work, no. 5-6, pp. 25 – 29, 1995.)

Occupational exposure to ionizing radiation (IR) involves operations with unsealed or sealed sources. Nuclear medicine staff using unsealed sources is of particular interest for dosimetry research because they are exposed to extremely inhomogeneous fields of ionizing radiation with an increased risk of internal contamination. The findings for two technicians who were unintentionally exposed to IR while operating unsealed sources in the Nuclear Medicine Department are presented here. Exposure evaluation was conducted at the Radiation Protection Center of the Serbian Institute of Occupational Health (SIOH). Values for the personal dose equivalent at a body depth of 10 mm at the point of application of the personal dosimeter [Hp(10)], the dose equivalent at a body depth 0.07 mm at the application point of the personal dosimeter [Hp(0.07)], and the results for chromosomal aberrations (CA) and micronuclei (MN) analysis after the first and control examinations at the Cytogenetic Laboratory (SIOH) are presented. The case report for Technician 1 (T1) is an example of agreement between the findings obtained by physical dosimetry and cytogenetic analysis in detecting unintentional exposure and internal contamination with high doses of radionuclides. The results also show that the cytokinesis block micronucleus (CBMN) test is a more sensitive technique in detecting internal contamination than CA analysis. Multiple MN are an unequivocal indicator of genetic damage. Since radiation is a strong inducer of MN, these genetic changes may be a certain biomarker of internal contamination.

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One of the main factors that differentiate people in terms of the effectiveness of therapeutic procedures or side effects is the variability in DNA repair capabilities. The aim of the study was to investigate the response of DNA damage repair systems in human lymphocytes irradiated with the therapeutic proton beam in the Bronowice Cyclotron Center of Institute of Nuclear Physics, Polish Academy of Sciences (IFJ PAN) in compare to X-rays. Lymphocytes from healthy donors were irradiated in the Spread-Out Bragg Peak of the proton beam or as reference X-rays. For both sources of radiation, the kinetics of the DNA damage repair capabilities were estimated using the comet assay method (0–120 min) and γ-H2AX test (0-24h). Preliminary results from the comet assay show a similar time and repair efficiency of induced DNA damage for both types of radiation. However, in a group involving X-rays, significant inter-individual differences were observed. With the γ-H2AX test, inter-individual differences in the repair capabilities were not noted. These findings indicate that induced DNA damage repair mechanisms after proton irradiation may be different when compared to X-rays.

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In present investigations, the sorption removal of Sr²⁺ and Y³⁺ ions from aqueous solutions by TiO₂ – La sorbent was researched. The dependence of the sorption process on the time of interaction, solution’s acidity, and initial concentrations of the Sr²⁺ and Y³⁺ ions were investigated. Four simplified kinetic models – Lagergren’s pseudo-first and pseudo-second order kinetic models, Intra-particle diffusion and Elovich models – were tested to describe the adsorption process. Equilibrium isotherms data were analyzed using Langmuir and Freundlich isotherm models. The kinetic data indicated that the adsorption of Sr²⁺ and Y³⁺ ions by ТіО₂–La fitted well with the pseudo-second order kinetic model with coefficients of linear approximation (R² = 0.99) for both elements. The application of the Elovich model to the experimental data of the sorption of Sr²⁺ and Y³⁺ ions by ТіО₂–La shows that yttrium is absorbed due to the mechanism of chemisorption. Coefficient of linear approximation R² = 0.98. Strontium is absorbed via physical sorption or ion exchange mechanism. The maximum adsorption capacity of ТіО₂ –La was found to be 0,9 mmol·g^-1 (79 mg g^-1) for Sr²⁺ and 1.6 mmol·g^-1 (134 mg·g^-1) for Y³⁺.

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Radium (Ra) isotopes are important from the viewpoints of radiation protection and environmental protection. Radium is routinely analyzed in drinking water. Radium isotopes can be analyzed by different analytical methods based on gamma spectrometric measurements or alpha spectrometry. Modern gamma spectrometry systems are typically operated via computer software applications. In this study, the LabSOCS (Laboratory Sourceless Calibration Software) mathematical efficiency calibration software is used. An improved method was developed to determine radium isotopes from water using gamma spectrometry after micro-coprecipitation as lead (radium) sulfate method for radiochemical separation (Pb(Ra)(Ba)SO₄). This method was successfully modified to allow direct determination of ²²⁶Ra and ²²⁸Ra by gamma spectrometry. However, large volumes of samples and/or long waiting time (20 days), before radioactive equilibrium is established, are required for accurate ²²⁶Ra activity concentration determination. The amounts of ²²⁶Ra and ²²⁸Ra on the sample were quantified by using gamma spectrometric analysis for its 186 keV gamma emission, 351.9 (²¹⁴Pb), 295.2 (²¹⁴Pb), and 609.3 (²¹⁴Bi), 1764.5 (²¹⁴Bi) and for ²²⁸Ra can be nonetheless achieved via its daughter nuclide ²²⁸Ac in 911.2 and 969 keV gamma emission. The radiochemical recovery was 93% and 100% for ²²⁶Ra and ²²⁸Ra, respectively. The Minimum Detectable Activities (MDAs) for 8L of sample and a measuring time of 2.3 days for ²²⁶Ra and ²²⁸Ra were calculated. The best results were obtained when the herein described method was combined with LabSOCS calculations.

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The X-ray fluorescence method is known as a laboratory method and one of the few atomic spectroscopy methods used in many fields. The process of emission of the characteristic X-rays is called “X-ray fluorescence” (XRF). The objectives of this research study are optimization of the XRF portable system geometry and the use of the fundamental parameters method to calculate the concentrations of elements in environmental samples using portable systems. Since this method is quick in getting results and does not destroy the sample, it is widely used both in research and in the analysis of industrial products for materials in the field of mineralogy, geology, environmental analysis of water, air, etc. Various experiments have led to the optimization of the geometry system, as the distances’ minimization, angles optimization, and the assessment of the beam spot in the position of the sample. Most of the data collected are used as initial data in the ADMCA program that uses fundamental parameters (FP-XRF) for calculating the concentrations of elements in environmental samples. Errors in calculating the concentrations of the sediment and soil samples when we introduce the approximate content of light elements can be eligible for geochemical studies. During the research, several areas that can be used in the future to improve the results are identified.

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The coincidence summing effect plays an important role in HPGe spectrometry, especially at low source-detector distances, due to a large solid angle; therefore, the calculation of correction factors is necessary. The aim of the research described in this paper was to compare values of correction factors for a ²²Na point source obtained using the GESPECOR software package (Monte-Carlo method) and experimentally obtained values. Measurements were performed using a semiconductor HPGe spectrometer and the point source axially positioned at nine different distances from the detector end-cap. For the purpose of determining correction factors, a system of equations was formed, which, besides nuclear data as the input parameters, uses the experimentally obtained values of the total count in the entire spectrum, as well as the counts in the full energy peaks. The system of equations was solved for each particular case and correction factors were determined. By comparing the results obtained using the experimental and Monte-Carlo method, it was found that the correction factors for the ²²Na point source have discrepancies less than 3%. The significance of these discrepancies was also verified from a statistical point of view using a Student's t-test.

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Albedo thermoluminescent and direct-reading electron personal neutron dosimeters were examined. The ratio introduced by the difference between calibration and operational spectra were studied. The ratio of dosimeter reading and personal dose equivalent to a variety of workplace spectra after calibration is in the range from 0.6 up to 106. A new dosimeter for neutron exposure was presented. It is suggested that the dosimeter should be used inside of the body. The difference between its response function and fluence-to-effective dose conversion function is in the factor of 7 and 9 for anteroposterior (AP) and rotation (ROT) exposure geometries respectively. This dosimeter might be used at emergency situations, when neutron spectrum is similar to one of nuclear fuel radionuclides fission reaction.

1. The 2007 Recommendations of the International Commission on Radiological Protection, ICRPPublication 103, ICRP, Vienna, Austria, 2007.
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3. B. M. Frietas, M. M. Martins, W. W. Pereira, A. X. da Silva, C. L. P. Mauricio, “MCNP simulation of the Hp(10) energy response of a brazilian TLD albedo neutron individual dosemeter, from thermal to 20 MeV,” Rad. Prot. Dosim., vol. 170, no. 1-4, pp. 350 – 353, Sep. 2016.
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4. T. Haninger, J. Henniger, “Dosimetric properties of the new TLD albedo neutron dosemeter AWST-TL-GD 04,” Rad. Prot. Dosim., vol. 170, no. 1-4, pp. 150 – 153, Sep. 2016.
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7. R. I. Scherpelz, J. R. Cezeaux, “Performance of the EPD-N2 dosemeter for monitoring aircrew doses,” Rad. Prot. Dosim., vol. 163, no. 4, pp. 415 – 423, Mar. 2015.
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13. Reference neutron radiations, ISO 8529, Feb. 1, 2001.
14. L. G. Beskrovnaya, E. A. Goroshkova, Yu. V. Mokrov, “An Investigation into the Accuracy of the Albedo Dosimeter DVGN-01 in Measuring Personnel Irradiation Doses in the Fields of Neutron Radiation at Nuclear Power Installations of the Joint Institute for Nuclear Research,” Phys. Part. Nuclei Lett., vol. 7, no. 3, pp. 212 – 221, May 2010.
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16. J. M. Bordy et al. “Performance test of dosimetric services in the EU member states and Switzerland for the routine assessment of individual doses (photon, beta and neutron),” Rad. Prot. Dosim., vol. 89, no. 1-2, pp. 107 – 154, Jun. 2000.
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19. G. Fehrenbacher, F. Gutermuth, E. Kozlova, T. Radon, R. Schuetz, “Neutron dose measurements with the GSI ball at high-energy accelerators,” Rad. Prot. Dosim., vol. 125, no. 1-4, pp. 209 – 212, Jul. 2007.
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20. Occupational Radiation Protection, General Safety Guide No. GSG-7, IAEA, Vienna, Austria, 2018, p. 335
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In the Public Company Nuclear Facilities of Serbia, the measurement of the operational dosimetric quantity, ambient dose equivalent H*(10), is continuously carried out at measurement points in the surrounding of the radioactive waste storage facilities (hangars H1, H2 and H3) and old reactor buildings (RA and RB), located at Vinca site in Belgrade. For that purpose, two different types of passive dosimeters are used: thermoluminescent (TL) high sensitivity dosimeters (LiF:Mg,Cu,P) and optically stimulated luminescence (OSL) dosimeters (Al₂O₃). The principle of radiation interaction with both types of material is very similar, and the main difference is reflected in the method of detecting the light which is in relation to the dose in the dosimeter. The measurement of the ambient dose equivalent is performed at 34 measuring points in order to monitor the level of radiation exposure in the vicinity of the mentioned facilities. The paper shows the results of the measurements in the period from January to December of 2016. TL and OSL dosimeters were used and read once a month at the same time under the same measurement conditions. The aim of this paper is to present the comparative results of the ambient dose equivalent measurements using TL and OSL dosimeters and compare them with the measurement results of the reference instrument for measuring dose rate (Atomtex AT6101C spectrometer) at the same measuring points. It was found that the differences among the measurement results using different dosimeter types were satisfactory, with a maximum deviation of 35%. The results also show that there is no significant increase in the level of radiation exposure, which is of particular importance to the environment and the population around nuclear facilities in Serbia.

1. The 2007 Recommendations of the International Commission on Radiological Protection, ICRP Publication 103, ICRP, Vienna, Austria, 2007.
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2. Народна Скупштина Републике Србије. (8.12.2018). Закон о радијационој и нуклеарној сигурности и безбедности. (National Assembly of the Republic of Serbia. (Dec. 8, 2018). Law on radiational and nuclear safety and security.)
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3. Влада Републике Србије. (18.11.2011) Правилник о границама излагања јонизујућим зрачењима и мерењима ради процене нивоа излагања јонизујућим зрачењима. (Government of the Republic of Serbia. (Nov. 18, 2011). Rulebook on Limits of Exposure to Ionizing Radiation and Measurements for Assessment if the Exposure Levels.)
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4. C. M. Sunta, Unraveling Thermoluminescence, Mumbai, India:Springer India, 2015.
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5. L. Botter-Jensen, S. McKeeverm A. G. Wintle, Optically Stimulated Luminescence Dosimetry, Amsterdam, Netherlands: Elsevier Science B.V., 2003.
6. AOMTEX official webpage, ATOMTEX, Minsk, Belarus, 2018.
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7. V. Ramzaev et al., “A backpack γ-spectrometer for measurements of ambient dose equivalent rate, _*H˙ (10), from 137Cs and from naturally occurring radiation: The importance of operator related attenuation,” Rad. Meas., vol. 107, pp. 14 – 22, Dec. 2017.
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8. R. Casanovas, E. Prieto, M. Salvado, “Calculation of the ambient dose equivalent H*(10) from gamma-ray spectra obtained with scintillation detectors,” Appl. Radiat. Isot., vol. 118, pp. 154 – 159, Dec. 2016.
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9. P. Olko et al., “Applicarion od MCP-N (LiF:Mg, Cu, P) TL Detectors in Monitoring Environmental Radiation,” Nucl. Technol. Radiat. Prot.,vol. 19, no. 1, pp. 20 – 25, Jan. 2004.
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10. M. Budzanowski, P. Olko, E. Ryba, U. Woznicka, “A System for Rapid Large-area Monitoring of Gamma-dose Rates in the Environment Based on MCP-N (LiF:Mg, Cu, P) TL Detectors,” Radiat. Prot. Dosim.,vol. 101, no. 1-4, pp. 205 – 209, Aug. 2002.
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11. D. Imatoukene, F. Abdelaziz, M. Mezaguer. Z. Lounis-Mokrani, “Development of new system for environmental monitoring based on Al2O3:C detectors,” Radiat. Meas.,vol. 43, no. 2-6, pp. 668 – 671, Feb-Jun. 2008.
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The specialists of NRC “Kurchatov Institute” have conducted the dismantling of the MR multiloop research reactor and RFT reactor. The technical start-up of the 20 MW capacity experimental graphite water cooling reactor (RFT) started in 1952. The reactor was shut down 10 years after the working period. The fuel was removed and the reactor was partially dismantled. The ventilation system and water cleanup system of the RFT reactor were located in a separate building. The upper part of the reactor vent stack was dismantled in the early 60’s. The water cleanup system, which consists of 6 stainless steel tanks (4 – Ø1.5m, h=5m; 2 – Ø3m, h=5m) located around the base reactor vent stack, was mothballed. To plan the dismantling work, a radiation and video survey of the water cleanup system and the reactor vent stack was carried out. For this purpose, holes were drilled in the upper ceiling of premises with the water cleanup system and at the top of vent stack. Through these holes video recording and measurement of the exposure dose rate distribution were carried out. The measurement of the exposure dose rate distribution along the height of vent stack was also carried out. Based on the result of these surveys, the measurements of distribution of activity from radioactive waste along the height of the tank were carried out. The collimated spectrometric system on the basis of a semiconductor detector CdZnTe (volume of a crystal of 60mm³) was used. The measurements showed that the distribution of activity from radioactive waste along the height of the tank was non uniform. To measure the distribution of the contamination of the inner surface vent stack we used the spectrometric system with semiconductor detector CdZnTe (volume of a crystal of 500mm³) with circular collimator. The results of measurements are presented and discussed. The results of the survey will be used for planning the dismantling work.

1. V. G. Volkov, Yu. A. Zvercov, V. I. Kolyadin et al., “Preparations for decommissioning the MR research reactor at the Russian Science Center Kurchatov institute,” Atomic Energy., vol. 104, no. 5, pp. 335 – 341, May 2008.
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2. V. E. Stepanov, V. N. Potapov, S. V. Smirnov, A. S. Danilovich “Radiological examination of MR reactor rooms using a remote-controlled spectrometric scanning system,” Atomic Energy., vol. 113, no. 2, pp. 125 – 129, Dec. 2012.
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3. A. G. Volkovich, O. P. Ivanov, A. V. Lemus et al, “Particularities of the Dismantling of the Intra-Vessel Structures of the RFT Reactor,” Atomic Energy., vol. 121, no. 5, pp. 377 – 382, Mar. 2017.
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4. I. Simirskii et al., “Particularities of the Dismantling of the Intra-Vessel Structures of the RFT Reactor,” in Proc. 43^rd Annual Waste Management Conference (WM2017), Phoenix (AZ), USA, 2017.
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5. A. Stepanov et al., “CdZnTe Detector Using for Characterization MR Water Cleanup System before Dismantling,” in Proc. 43^rd Annual Waste Management Conference (WM2017 Phoenix (AZ), USA, 2017.
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6. V. E. Stepanov, A. G. Volkovich, V. N. Potapov et al., “The CdZnTe Detector with Slit Collimator for Measure Distribution of the Specific Activity Radionuclide in the Ground,” in Proc. Int. Conf. Advanced Measurement Methods and their Applications (ANIMMA17), Liege, Belgium, 2017.
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7. V. E. Stepanov, V. N. Potapov, O. P. Ivanov, “The development of non destructive remote measurement method of concrete contamination,” in Proc. 15^th Int. Conf. Environmental Remediation and Radioactive Waste Management (ASME 2013), Brussels, Belgium, 2013, p. V002T03A009.
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The paper presents the methodology for determining the area in the vicinity of overhead power lines where the levels of non-ionizing radiation are significant in the context of current regulations referring to the protection of the general public in the Republic of Serbia. A brief review of Serbian legislation on protection of the general public from power frequency electromagnetic fields is given. The zones of influence of 110 kV, 220 kV and 400 kV transmission overhead power lines are determined by calculations. The configurations of power lines which result in the widest zone of influence are analyzed for each voltage level. The influence of phase conductor heights on the width of the zone is also considered. Determining the width of the zone of influence is very important for planning the construction of new power lines near residential areas, as well as for the construction of residential buildings near existing lines. It is also significant when it is necessary to determine the locations in the vicinity of overhead power lines where more detailed testing of non-ionizing radiation should be performed by measurements.

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6. Мере за ограничење електричног и магнетског поља,студија бр. 3414017,Електротехнички институт „Никола Тесла”, Београд, Србија,2014.(Techniques for limiting the levels of electric and magnetic field, study no. 3414017, Nikola Tesla Electrical Engineering Institute, Belgrade, Serbia, 2014.)
7. Electric and magnetic field levels generated by AC power systems – Measurement procedures with regard to public exposure, EN 62110:2009, Aug. 38, 2009.
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11. A. Z. El Dein, “Calculation of the electric field around the tower of the overhead transmission lines,” IEEE T. Power. Deliver., vol. 29, no. 2, pp. 899 – 907, Apr. 2014.
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12. A. Z. El Dein, “Parameters affecting the charge distribution along overhead transmission lines’ conductors and their resulting electric field,” Electric Power Syst. Res., vol. 108, pp. 198 – 210, Mar. 2014.
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13. J. C. Salari, A. Mpalantinos, J. I. Silva, “Comparative analysis of 2- and 3-D methods for computing electric and magnetic fields generated by overhead transmission lines,” IEEE T. Power. Deliver., vol. 24, no. 1, pp. 338 – 344, Jan. 2009.
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14. T. Modrić, S. Vujević, D. Lovrić, “3D computation of the power lines magnetic field,” Prog. Electromagn. Res., vol. 41, pp. 1 – 9, 2015.
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    DOI: 10.1016/j.epsr.2016.03.004
16. Дозвољене струје фазних проводника на далеководима, Техничко упутство ТУ-ДВ-04, верзија 2, ЈП „Електромрежа Србије”, Београд, Србија, 2011. (Allowed current values of phase conductors in transmission lines, Technical Manual ТУ-ДВ-04, version 2, SOE Elektromreža Srbije, Belgrade, Serbia, 2011.)
17. Влада Савезне Републике Југославија. (1992). Правилник о техничким нормативима за изградњу надземних електроенергетских водова називног напона од 1 kV до 400 kV. (Government of the Federal Republic of Yugoslavia. (1992). Rulebook on technical norms for building of overground electric transmission lines of the nominal voltage of 1 kV to 400 kV.)
    Retrieved from: http://www.vladars.net/sr-SP-Cyrl/Vlada/Ministarstva/mper/std/Documents/3.Pravilnik%20o%20%20teh.%20norm.za %20izgrd.%20nadzemnih%20el.%20vodova%20naz.%20napons%201kv%20do%20400kv%20SL.L.%20SFRJ%2065-88.pdf;
    Retrieved on: Jul. 3, 2018

In this paper, the operator proximity effect on the measurement results of the electric field strength in the vicinity of overhead power lines is analyzed. The operator proximity effect depends on the distance between the operator and the probe for measuring the electric field strength, as well as on the height at which the probe is placed. The paper presents the results of the electric field strength measurements performed in the vicinity of a 220 kV overhead power line in order to quantify the influence of the proximity of the operator. The measurements were carried out by using a cube-shaped isotropic probe. During the measurements, the probe was placed on a wooden tripod and connected to the electromagnetic field analyzer by an optical cable. The measurements were performed at the heights of 1 m, 1.5 m and 1.7 m. The distance between the operator and the measuring probe during these measurements was gradually increased from 1 m to 10 m. The obtained results are analyzed in detail in this paper. These results can be used for evaluating the electric field strength measurement uncertainty. The significance of these results also lies in demonstrating the manner in which the operator’s influence on the measured field can be reduced to an acceptable level.

1. J. Di Placido et al., “Analysis of the proximity effects in electric field measurements”, IEEE Trans. Power App. Syst., vol. PAS–97, no. 6, pp. 2167 – 2177, Nov-Dec. 1978.
   DOI: 10.1109/TPAS.1978.354720
2. Technical guide for measurement of low frequency electric and magnetic fields near overhead power lines, WG C4.203, CIGRE, Apr. 2009.
3. Measurement of DC magnetic, AC magnetic and AC electric fields from 1 Hz to 100 kHz with regard to exposure of human beings – Part 1: Requirements for measuring instruments, EN 61786-1:2014, Jul. 31, 2014.
4. Measurement of DC magnetic, AC magnetic and AC electric fields from 1 Hz to 100 kHz with regard to exposure of human beings – Part 2: Basic standard for measurements, IEC 61786-2:2014, Dec. 11, 2014.
5. Electric and magnetic field levels generated by AC power systems – measurement procedures with regard to public exposure, EN 62110:2009, Aug. 31, 2009.
6. IEEE standard procedures for measurement of power frequency electric and magnetic fields from AC power lines, IEEE 644-1994, Dec. 13, 1994.

The concept of CBRN (chemical, biological, radiological, nuclear) defence is a highly complex phenomenon and a scientific discipline within both the social and technical-technological sciences. CBRN defence has multiple meanings. In the most general sense, it refers to absence/elimination or minimization of threats, i.e. pressures that can threaten people, property, and the environment. Effective and efficient CBRN defence activities can be seen from the perspective of civil structures or armed forces. In this sense, the organizational structure of the armed forces of any country represents a dynamic system which, within the wider community, operates and exists under specific conditions and circumstances. Starting from its basic purposes, the regular armed forces of any state do not have unknowns regarding the rules and their core roles. However, the complex structure and the interdependence of different organizational structures within the country and within the armed forces have an impact on the implementation of measures in the field of CBRN defence and management of risk both in war and peacetime. The aim of this paper is to present the structural organization, resources and tasks of the Serbian armed forces (SAF) within the field of CBRN defence.

1. Народна скупштина Републике Србије. (18.11.2011). Сл. гласник 86/2011 Национална стратегија заштите и спасавања у ванредним ситуацијама. (National Assembly of the Republic of Serbia. (Nov. 18, 2011). Official Gazette 86/2011 National strategy for protection and rescue procedures in emergency situations.)
   Retrieved from: http://arhiva.mup.gov.rs/cms_lat/sadrzaj.nsf/Nacionalna_strategija_zastite_i_spasavanja_u_vanrednim_situacijama_l at.pdf;
   Retrieved on: Sep. 15, 2018
2. Народна скупштина Републике Србије. (01.04.2009). Стратегија националне безбедности Републике Србије. (Ministry of Defence of Republic of Serbia. (Apr. 1, 2009). National security strategy of the Republic of Serbia.)
   Retrieved from: http://www.mod.gov.rs/multimedia/file/staticki_sadrzaj/dokumenta/strategije/Strategija%20nacionalne%20bezbednosti %20Republike%20Srbije.pdf;
   Retrieved on: Sep. 30, 2018
3. Народна скупштина Републике Србије. (6.10.2012). Сл. гласник 93/2012 Закон о ванредним ситуацијама. (National Assembly of the Republic of Serbia. (Oct. 6, 2012). Official Gazette 93/2012 Law on emergency situations.)
   Retrieved from: http://prezentacije.mup.gov.rs/svs/html/Zakon%20o%20VS.pdf;
   Retrieved on: Sep. 15, 2018
4. Народна скупштина Републике Србије. (25.9.2012). Закон о ванредним ситуацијама. (National Assembly of the Republic of Serbia. (Sep. 25, 2012) Law on emergency situations.)
   Retrieved from: http://prezentacije.mup.gov.rs/svs/html/Zakon%20o%20VS.pdf;
   Retrieved on: May 12, 2018
5. Народна скупштина Републике Србије. (28.09.2012). Закон о заштити од јонизујућег зрачења и нуклеарној сигурности. (National Assembly of the Republic of Serbia. (Sep. 28. 2012). Law on the ionizing radiation protection and nuclear safety.)
   Retrieved from: https://www.paragraf.rs/propisi/zakon_o_zastiti_od_jonizujucih_zracenja_i_o_nuklearnoj_sigurnosti.html;
   Retrieved on: Sep. 15, 2018
6. Народна скупштина Републике Србије. (10.05.2018). Закон о одбрани. (National Assembly of the Republic of Serbia. (May 10. 2018). Law on defense.)
   Retrieved from: https://www.paragraf.rs/propisi/zakon_o_odbrani.html;
   Retrieved on: Sep. 15, 2018
7. S. Mušicki, V. Nikolić, D. Vasović, “Resource protection - the Serbian Army experience,” in Proc. VI International Symposium Engineering Management and Competitiveness (EMC 2016), Kotor, Montenegro, 2016, pp. 110 – 113.
   Retrieved from: http://www.tfzr.uns.ac.rs/emc/pastEMCs.aspx;
   Retrieved on: May 20, 2018
8. S. Mušicki, V. Nikolić, D. Vasović, “Safety, security, hazard and risk – a conceptual approach,” in Proc. 7th DQM International Conference Life Cycle Engineering and Management (ICDQM-2016), Prijevor, Serbia, 2016, pp. 396 – 401.
9. D. Vasović, J. Malenović Nikolić, G. Janacković, “A quick glance at disaster risk reduction from different perspectives,” in Proc. Int. Conf. Life Cycle Engineering and Management (ICDQM-2016), Prijevor, Serbia, 2016, pp. 193 – 200.
10. S. Mušicki, “Integrative model or resource protection improvement in MoD and SAF,” Ph.D. dissertation, University of Defence, Military Academy, Belgrade, Serbia, 2016.
11. 246. батаљон АБХО, Војска Србије, Београд, Србија, 2018.(246^th CBRN battalion of the Serbian Army, Serbian Armed forces, Belgrade, Serbia, 2018.)
    Retrieved from: http://www.vs.rs/sr_cyr/jedinice/vojska-srbije/kopnena-vojska/246-bataljon-abho;
    Retrieved on: Jun. 10, 2018
12. D. Indjić, “Possibility of the development of Serbian protection system of chemical accident,” Mil. Tech. Cour., vol. 60, no. 4, pp. 133 – 146, 2012.
    Retrieved from: http://www.vtg.mod.gov.rs/archive/2012/military-technical-courier-4-2012.pdf;
    Retrieved on: Jun. 10, 2018
13. D. Baker et al., Guidebook to Decision-Making Methods. Department of Energy, Washington (DC), USA, 2002, pp. 2 – 5.
    Retrieved from: https://www.researchgate.net/publication/255621095_Guidebook_to_Decision-Making_Methods;
    Retrieved on: Jun. 10, 2018
14. Народна скупштина Републике Србије. (10.05.2018). Закон о Војсци Србије. (National Assembly of the Republic of Serbia. (May 10, 2018). Law on Serbian Armed Forces).
    Retrieved from: https://www.paragraf.rs/propisi/zakon_o_vojsci_srbije.html;
    Retrieved on: Sep. 15, 2018

Nuclear and chemical accidents lead to endangering the health of citizens and the environment due to contamination by radiological and chemical contaminants and consequently cause security risks for the population and material goods. Decontamination related to CBRN (chemical, biological, radiological, nuclear) events represents a set of processes and activities aimed at total or partial removal or neutralization of radiological, chemical, and biological contamination caused by an intended or non-intended threat, thereby reducing the risk of exposure to the people or the environment up to the permissible levels. The primary and ultimate goal of decontamination is the complete elimination of radioactive contaminants or the minimization of contamination levels of chemical and biological contaminants. The aim of this paper is to demonstrate the relevance of CBRN decontamination observed from multiple perspectives: the environmental resources protection standpoint, the society wellbeing standpoint, and the operative personnel and experience-knowledge standpoint to engage them in the most effective manner.

1. N. Ivanova, S. Ivanova, “Radiation incident in “Polimeri” Devnya, actions and safety measures: a case study,” Ecology & Safety, vol. 10, pp. 515 – 523, 2016.
   Retrieved from: https://www.scientific-publications.net/get/1000017/1482509635891347.pdf;
   Retrieved on: Jun. 13, 2018
2. Categorization of Radioactive Sources, Safety Guide No. RS-G-1.9, IAEA, Vienna, Austria, 2005.
   Retrieved from: https://www-pub.iaea.org/MTCD/Publications/PDF/Pub1227_web.pdf;
   Retrieved on: Jun. 13, 2018
3. Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards,General Safety Requirements, No. GSR Part 3, IAEA, Vienna, Austria, 2014.
   Retrieved from: https://www-pub.iaea.org/MTCD/publications/PDF/Pub1578_web-57265295.pdf;
   Retrieved on: Jun. 11, 2018
4. Manual for the public health management of chemical incidents, WHO, Geneva, Switzerland, 2009.
   Retrieved from: http://apps.who.int/iris/bitstream/handle/10665/44127/9789241598149_eng.pdf;jsessionid=31019957AADF5FE8CAE88EE 8D7544783?sequence=1;
   Retrieved on: Jun. 11, 2018
5. Public health response to biological and chemical weapons, WHO guidance, WHO, Geneva, Switzerland, 2004.
   Retrieved from: https://www.who.int/csr/delibepidemics/cover.pdf?ua=1;
   Retrieved on: Jun. 11, 2018
6. Д. Васовић, “Хибридни модел управљања капацитетом животне средине,” докторска дисертација, Универзитет у Нишу, Факултет заштите на раду, Ниш, Србија, 2016. (D. Vasovic, “Hybrid model of environmental capacity management,” Ph.D. dissertation, University of Niš, Faculty of Occupational Safety, Niš, Serbia, 2016.)
   Retrieved from: http://www.znrfak.ni.ac.rs/SERBIAN/013-OGLASENI-DOKUMENTI/DOKTORSKE%20DISERTACIJE/Dejan%20Vasovic/Dis_UNI_ Dejan_M_Vasovic_2016%20sa%20napomenom.pdf;
   Retrieved on: Sep. 30, 2018
7. Народна скупштина Републике Србије. (18.11.2011). Национална стратегија заштите и спасавања у ванредним ситуацијама. (National Assembly of the Republic of Serbia. (Nov. 18, 2011). National strategy for protection and rescue procedures in emergency situations.)
   Retrieved from: http://arhiva.mup.gov.rs/cms_lat/sadrzaj.nsf/Nacionalna_strategija_zastite_i_spasavanja_u_vanrednim_situacijama_la t.pdf;
   Retrieved on: Sep. 15, 2018
8. Мистарство одбране Републике Србије. (01.04.2009). Стратегија националне безбедности Републике Србије. (Ministry of Defence of Republic of Serbia. (Apr. 1, 2009). National security strategy of the Republic of Serbia.)
   Retrieved from: http://www.mod.gov.rs/multimedia/file/staticki_sadrzaj/dokumenta/strategije/Strategija%20nacionalne%20bezbednosti %20Republike%20Srbije.pdf;
   Retrieved on: Sep. 30, 2018
9. Народна скупштина Републике Србије. (6.10.2012). Закон о ванредним ситуацијама. (National Assembly of the Republic of Serbia. (Oct. 6, 2012). Law on emergency situations.)
   Retrieved from: http://prezentacije.mup.gov.rs/svs/html/Zakon%20o%20VS.pdf;
   Retrieved on: Sep. 15, 2018
10. Народна скупштина Републике Србије. (28.09.2012). Закон о заштити од јонизујућег зрачења и нуклеарној сигурности. (National Assembly of the Republic of Serbia. (Sep. 28. 2012). Law on the ionizing radiation protection and nuclear safety.)
    Retrieved from: https://www.paragraf.rs/propisi/zakon_o_zastiti_od_jonizujucih_zracenja_i_o_nuklearnoj_sigurnosti.html;
    Retrieved on: Sep. 15, 2018
11. Народна скупштина Републике Србије. (10.05.2018). Закон о одбрани. (National Assembly of the Republic of Serbia. (May 10. 2018). Law on defense.)
    Retrieved from: https://www.paragraf.rs/propisi/zakon_o_odbrani.html;
    Retrieved on: Sep. 15, 2018
12. Народна скупштина Републике Србије. (10.05.2018). Закон о Војсци Србије. (National Assembly of the Republic of Serbia. (May 10. 2018). Law on Serbian Armed Forces.)
    Retrieved from: https://www.paragraf.rs/propisi/zakon_o_vojsci_srbije.html;
    Retrieved on: Sep. 15, 2018
13. BM Országos Katasztrófavédelmi Foigazgatói. (24.1.2017). Intézkedés a Katasztrófavédelmi Muveleti Szolgálat, a Katasztrófavédelmi Mobil Labor, valamint a Katasztrófavédelmi Sugárfelderíto Egység tevékenységének szabályozásáról. (National Directorate General for Disaster Management, Ministry of the Interior. (Jan. 24, 2017). Rule No. 4/2017 on issuing the Operational Regulations and Methodological Guide of the Disaster Management ‘s CBRN Units.)

Nondestructive Testing (NDT) is a non-invasive method based on physical principles used to evaluate the integrity and characteristics of materials. Its measurement methodology covers a wide range of applications of materials and structures that relate to the entire life cycle, from manufacture to use and retirement. Radiography is one of the most important and widely used NDT methods for volumetric examination. In general, Radiography Testing (RT) is a method of inspecting materials for hidden flaws by using the ability of short wavelength electromagnetic radiation (high energy photons) to penetrate various materials. The intensity of radiation that penetrates and passes through the material is captured by a radiation sensitive film. This study presents the evaluation of the dose rate field in and around the radiation beam for MHF 200D X-ray tube model, using a large interval of voltage (20 to 200 kV) and current (0.5 to 8 mA). We controlled the variables that represent the essential characteristics of beam radiation quality, such as voltage (kV), and determined the Half-Value Layer (HVL) for different values of voltage and current.

1. Radiation protection and safety in industrial radiography, Safety Report Series No. 13, IAEA, Vienna, Austria, 1999.
   Retrieved from: https://www-pub.iaea.org/MTCD/Publications/PDF/P066_scr.pdf;
   Retrieved on: Apr. 11, 2018
2. Radiation safety in industrial radiography, Specific Safety Guide No. SSG-11, IAEA, Vienna, Austria.
   Retrieved from: https://www-pub.iaea.org/MTCD/Publications/PDF/Pub1466_web.pdf;
   Retrieved on: Apr. 11, 2018
3. Ministria e Shëndetësisë. (18.6.2014). Nr 404 Prot për miratimin e rregullores ”për rregullat bazë të instalimeve radiologjike në mjekësi”. (Ministra of health. (Jun. 18, 2014). No. 404 on the approval of the regulation “On basic rules of radiological installations in medicine”.)
   Retrieved from: http://www.ishp.gov.al/wp-content/uploads/2017/11/Rr.404-dt-18.06.2014-Per-rregullat-baze-te-instalimeve-radiologjike-ne-mjekesi.docx;
   Retrieved on: Apr. 11, 2018
4. Safety Procedures for the Installation, Use and Control of X-ray Equipment in Large Medical Radiological Facilities, Safety Code 35, Government of Canada, Ottawa, Canada, 2008.
   Retrieved from: https://www.canada.ca/en/health-canada/services/environmental-workplace-health/reports-publications/radiation/ safety-code-35-safety-procedures-installation-use-control-equipment-large-medical-radiological-facilities-safety-code.html#ack;
   Retrieved on: Apr. 11, 2018
5. Criteria for Acceptability of Medical Radiological Equipment used in Diagnostic Radiology, Nuclear Medicine and Radiotherapy, Radiation Protection N° 162, European Commission, Brussels, Belgium, 2012.
   Retrieved from: https://ec.europa.eu/energy/sites/ener/files/documents/162.pdf;
   Retrieved on: Apr. 13, 2018
6. Industrial Radiography, Image forming techniques, General Electric, Boston (MA), USA, 2008.
   Retrieved from: https://www.gemeasurement.com/sites/gemc.dev/files/industrial_radiography_image_forming_techniques_english_4.pdf;
   Retrieved on: Apr. 13, 2018
7. Gilardoni S.p.A. Instruction for Use of MHF Code 05173201&05173202 & 05173211, Z.1666 Rev. 2 07/2004, Gilardoni S.p.A, Milan, Italy, 2004.

Terrestrial gamma radiation levels are significantly affected by the radionuclides that are present in the soil, which in turn can be used for the assessment of the terrestrial gamma dose rate. This study is important because the employees of this institute, in addition to professional exposure, will be familiar with the average annual effective dose equivalents (AEDEs) in soils that come from this area. The main radioactive materials are the long-lived radionuclides, such as ²³⁸U, ²³²Th and ⁴⁰K, known as NORMs (Naturally Occurring Radionuclide Materials). Natural radioactivity analysis has been done for the soil samples collected from the area of the Institute of Applied Nuclear Physics (IANP) in Tirana, Albania. The activity concentration of Radium (²²⁶Ra), Thorium (²³²Th) and Potassium (⁴⁰K) were measured in these samples using HPGe (High Purity Germanium) detector based on low background gamma-ray counting system. From the measured activity concentration of the above three natural radionuclides, the external gamma absorbed dose rate and the annual effective dose were calculated. The obtained mean values of gamma absorbed dose rate and annual effective dose in soil samples were found to be comparable with the worldwide average as reported by United Nations Scientific Committee on the Effects of Atomic Radiation. The natural radioactivity levels in soils of IANP area had never been studied before. This study aims to determine the dose rate in order to assess the health risks from the activity concentration of the natural radionuclides as ²³⁸U, ²³²Th and ⁴⁰K in the soil. Also, the Radium equivalent (Ra_eq) of the samples is calculated and compared with the similar data reported in literature. The values of the outdoor annual effective dose were in the range of 0.02 to 0.11 mSv, showing that the area of IANP was radiologically safe.

1. Sources and Effects of Ionizing Radiation, UNSCEAR Report (A/48/46), UNSCEAR, New York (NY), USA, 1993.
   Retrieved from: http://www.unscear.org/docs/publications/1993/UNSCEAR_1993_Report.pdf;
   Retrieved on: Aug. 17, 2018
2. Beir VII Phase 2: Health risks from exposure to low levels of ionizing radiation Washington, Rep. 11340, National Academy of Sciences, Washington (DC), USA, 2006.
   Retrieved from: http://www.philrutherford.com/Radiation_Risk/BEIR/BEIR_VII.pdf;
   Retrieved on: Aug. 17, 2018
3. Sources and Effects of Ionizing Radiation, UNSCEAR Report (A/55/46), UNSCEAR, New York (NY), USA, 2000.
   Retrieved from: http://www.unscear.org/docs/publications/2000/UNSCEAR_2000_Report_Vol.I.pdf;
   Retrieved on: Aug. 17, 2018
4. Sources, Effects and Risks of Ionizing Radiation, UNSCEAR Report (A/43/45), UNSCEAR, New York (NY), USA, 1988.
   Retrieved from: http://www.unscear.org/docs/publications/1988/UNSCEAR_1988_Report.pdf;
   Retrieved on: Aug. 17, 2018
5. L. A. Currie, “Limits for Qualitative Detection and Quantitative Determination Application to Radiochemistry,” Anal. Chem., vol. 40, no. 3, pp. 586 – 593, Mar. 1986.
   DOI: 10.1021/ac60259a007
6. Ş. Turhan, A. Köse, A. Varinlioğlu, İ. H. Arıkan, F. Oğuz, B. Yücel, T. Özdemir, “Distribution of terrestrial and anthropogenic radionuclides in Turkish surface soil samples,” Geoderma, vol. 187-188, pp. 117 – 124, Oct. 2012.
   DOI: 10.1016/j.geoderma.2012.04.017

Public Company “Nuclear Facilities of Serbia” is the only nuclear operator in Serbia. Under the radiation safety and radiation protection measures of people and environment, Public Company conducts the environmental radiation monitoring around nuclear facilities. Monitoring also includes relevant meteorological measurements at the micro-location. This paper shows the correlation between the change of ambient gamma dose rate equivalent in the air and meteorological parameters: precipitation and the relative humidity in air. All the measurements were taken at the site of a meteorological tower on 114 meters above sea level, in the vicinity of nuclear facilities. Monthly values of relative humidity of the air and intense rainfall were obtained during 2017. The analysis of this relation clearly shows the impact of the intense rain and the relative humidity of the air on the ambient gamma dose rate equivalent. Calculated Pearson's correlation coefficient shows the degree of the above-mentioned dependence.

1. Sources and Effects of Ionizing Radiations, vol. 1, UNSCEAR Report (A/55/46), UNSCEAR, New York (NY), USA, 2000.
   Retrieved from: http://www.unscear.org/docs/publications/2000/UNSCEAR_2000_Report_Vol.I.pdf
   Retrieved on: May 20, 2018
2. C. R Hosler, “Meteorological effects on atmospheric concentrations of radon (Rn222), RaB(Pb214), and RaC(²¹⁴Bi) near the ground,” American Meteorological Society, Feb. 1966.
   DOI: 10.1175/1520-0493(1966)094<0089:MEOACO>2.3.CO;2
3. E. Simion, I. Mihalcea, F. Simion, C. Pacuraru, “Evaluation Model of Atmospheric Natural Radioactivity Considering Meteorological Variables,” Rev. Chim., vol. 63, no. 12, pp. 1251 – 1256, 2012.
   Retrieved from: http://revistadechimie.ro/pdf/SIMION%20E.pdf%2012%2012.pdf;
   Retrieved on: Apr. 29, 2018
4. Vlada Republike Srbije. (28.9.2012). Sl. Glasnik br. 36/09 i br. 93/12. Zakon o zaštiti od jonizujućih zračenja i o nuklearnoj sigurnosti. (Government of the Republic of Serbia. (Sep. 28, 2012). Official Gazette no. 36/06 and no. 93/12. Law on protection from the ionizing radiation and nuclear safety.)
   Retrieved from: http://www.srbatom.gov.rs/srbatom/doc/vazeca_akta/ZAKON_O_ZASTITI_OD_JONIZUJUCIH_ZRACENJA_I_NUKLEARNOJ _SIGURNOSTI-SLGL-36-09-I-93-12-LAT.pdf;
   Retrieved on: May 15, 2018
5. Agencija za zaštitu od jonizujućih zračenja i nuklearnu sigurnost Srbije. (Dec. 21, 2011). Br 97/11. Pravilnik o monitoringu radioaktivnosti. (Serbian Radiation Protection and Nuclear Safety Agency. (Dec. 21, 2011). No. 97/11. Rulebook on Radioactivity Monitoring.
   Retrieved from: http://www.imrs.rs/!uploads/PRAVILNIK%20O%20MONITORINGU%20RADIOAKTIVNOSTI%20(Sl.%20glasnik%20RS,%20br.%2097-2011)%20-%20LAT.pdf
   Retrieved on: May 15, 2018
6. Guide to Meteorological Instruments and Methods of Observations, WMO-No.8, WMO, Geneva, Switzerland, 2008.
   Retrieved from: https://library.wmo.int/pmb_ged/wmo_8_en-2012.pdf
   Retrieved on: May 10, 2018
7. J. F. Mercier et al., “Increased environmental gamma-ray dose rate during precipitation: a strong correlation with contributing air mass,” J. Environ. Radioact., vol. 100, no. 7, pp. 527 – 533, Jul. 2009.
   DOI: 10.1016/j.jenvrad.2009.03.002
   PMiD: 19403214
8. Calibration of Radiation Protection Monitoring Instruments, IAEA SRS No. 16, IAEA, Vienna, 2000.
   Retrieved from: https://www-pub.iaea.org/MTCD/Publications/PDF/P074_scr.pdf;
   Retrieved on: Apr. 29, 2018
9. V. Radumilo, I. Knežević, D. Žarković, D. Arbutina, “Korelacija radijacionih parametara i količine padavina prilikom monitoringa radioaktivnosti u okolini nuklearnih objekata,” у Zbornik radova XXIX Simpozijuma (DZZSCG, 2017), Srebrno jezero, Srbija, pp. 2017, 37-44. (V. Radumilo, I. Knežević, D. Žarković, D. Arbutina, “Correlation of radiation parameters and the level of precipitations during monitoring of radioactivity in the vicinity of nuclear facilities” in Proc 29^th Symposium, Society for Radiation Protection of Serbia and Montenegro (DZZSCG, 2017), Srebrno jezero, Serbia, 2017, pp. 37 – 44.
   Retrieved from: https://mail.ipb.ac.rs/~centar3/radovi171020/2017_CN03-04_Zbornik_XXIX_Simpozijum_DZZ_SCG_2017.pdf;
   Retrieved on: May 10, 2018

The aim of the study is the investigation of the activity concentration of ¹³⁷Cs and ⁴⁰K in blueberry-based products that are available on the market in the Republic of Serbia. Samples were bought in stores during September 2017 and in total, ten packaged juices, two jams, two sweets and a fresh wild blueberry were measured. The activity concentrations of ¹³⁷Cs in blueberry-based juices, jams and sweets varied from <MDA to 4.1 Bq/kg, <MDA to 21 Bq/kg and 0.6 Bq/kg to 28 Bq/kg, respectively. The average activity concentration of ¹³⁷Cs in fresh wild blueberry was 4.1 Bq/kg. In Serbia, the recommended activity concentration of ¹³⁷Cs in juices and sweets is 15 Bq/kg and 150 Bq/kg in fresh blueberries. The tested samples of juices, jams, fresh wild blueberry and one of the sweets meet the set criteria for ¹³⁷Cs while one sweets sample exceeds the limit. The activity concentrations of ⁴⁰K in juices, jams and sweets varied from 3.5 to 55 Bq/kg, 13.9 to 19.2 Bq/kg and 17.2 to 227 Bq/kg, respectively. The average activity concentration of ⁴⁰K in fresh wild blueberry was 32 Bq/kg. With the obtained result the annual effective dose equivalent due to ingestion of blueberry-based products for adults was calculated, and for ¹³⁷Cs in blueberry-based juices, jams, sweets and fresh wild blueberry varied from 0.2 to 2.5 mSv, 2.8 mSv, 0.4 to 17.0 mSv and 2.5 mSv, respectively. The annual effective dose equivalent for ⁴⁰K in blueberry-based juices, jams, sweets and fresh wild blueberry varied from 1.0 to 16.0 mSv, 1.2 mSv, 5.0 to 66.0 mSv, and 9.3 mSv, respectively.

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The radiation exposure for people and all living things is inevitable. Most of these exposures are due to natural sources. Terrestrial and cosmic radiation sources are the most important contribution to these exposures which originated from the fractionation of U-238, Th-232, gamma radiation of K-40 and high-energy cosmic particles incident on the earth’s atmosphere. The main contribution to these exposures comes from terrestrial sources. Terrestrial radionuclides are found in various concentrations in the crust of the earth depending on geological conditions of the region. They also cause exposure risks externally due to their gamma-ray emissions. This study assesses the terrestrial and cosmic radiation dose rates from the naturally occurring radionuclides in the region of Niğde province of Turkey. The measurements were performed on the surface soil using NaI(Tl) scintillation type gamma-ray detector. The external annual effective doses and cancer risk for people living in the region are also calculated from such terrestrial and cosmic gamma radiation dose rates for each individual.

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Bulgaria is a country which developed uranium (U) mining in the past. In the present study U content in different foodstuffs was determined in answer to public concern of possible radiological risk raised by relatively high U concentration measured in drinking waters in the regions of Haskovo and Plovdiv. Around them uranium mining was carried out on a large scale in the past (around Haskovo under the classical mining method and around Plovdiv under the method of geotechnological drilling). Vegetable (alfalfa, carrots, potatoes and tomato paste) and animal (milk and minced meat) samples were studied and radioactivity concentration (Bq.kg^-1) of two natural U isotopes was determined in the following intervals: U-234 –0.004 – 1.00 and U-238 –0.004 – 0.76. Calculated natural U concentration (mg/kg) was 0.0010 – 0.0712. Results were comparable with data cited in literature for U content in foodstuffs from former U mining regions in Europe and considered not radiologically hazardous to the population.

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The naturally occurring radionuclides are the major source of radiation to which humans are exposed to. A total of 21 samples of roe deer (Capreolus capreolus) from different locations in Vojvodina were tested. The samples were prepared for measuring by microwave digestion. The content of potassium in the samples was determined using atomic absorption spectrometry (AAS) The total content of uranium and thorium were determined using inductively coupled plasma mass spectrometry (ICP-MS). The concentration of the activity of the tested radionuclides was calculated based on their specific activities. It can also be concluded that potassium-40 is the predominant natural radionuclide in urine as compared to other radionuclides and it moved in the range of 128-381 Bq/L. The results of urine analysis showed wide ranges in radionuclide activity concentrations: 18.4-231.9 mBq/L for ²³⁸U, 0.94-11.90 mBq/L for ²³⁵U and 1.03-89.02 mBq/L for ²³²Th.

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17. A. H. Mohagheghi, S. T. Shanks, J. A. Zigmond, G. L. Simmons, S. L. A. Ward, “A Survey of Uranium and Thorium Background Levels in Water, Urine, and Hair and Determination of Uranium Enrichments by ICP-MS,” J. Radioanal. Nucl. Chem., vol. 263, no 1, pp, 189 – 195, 2005.
    Retrieved from: http://rmcc.foresite-jo.com/sites/default/files/U-Th-ICPMS-Study.pdf;
    Retrieved on: Jun. 19, 2017

Tritium is produced naturally, mainly through interactions of cosmic rays with nitrogen in the atmosphere. Human activities (including thermonuclear bomb tests, operation of nuclear reactors, manufacture of nuclear weapons, and various industrial and medical applications) are also sources of tritium. Once in the environment, tritium occurs mainly in the form of tritiated water (HTO). International legislations and national regulations are in place to impose tight controls on releases as well as to ensure regular monitoring near anthropogenic sources. Tritium monitoring of surface and well waters that supply populations with drinking water are of particular importance. The monitoring data are used to trace releases and also for the evaluation of tritium doses to nearby residents. According to the European Commission, the upper limit for tritium in water is 100Bql^-1 [1]. This value was not set based on the probability of health effects. It is a monitoring tool (action level) because tritium activity concentration exceeding 100 Bql^-1 could indicate a leakage or a release for which further analysis, to check if other radionuclides are present in water, would be warranted. In this paper, tritium concentrations measured in water samples collected from the Mlaka creek in the vicinity of the “Nuclear Facilities of Serbia” are presented.

1. The European Commission. (Nov. 3, 1998). Council Directive 98/83/EC of 3 Nov. 1998 on the quality of water intended for human consumption.
   Retrieved from: https://eur-lex.europa.eu/legal-content/EN/TXT/PDF/?uri=CELEX:31998L0083&from=EN;
   Retrieved on: May 16, 2018
2. J. Nikolov et al., “Tritium in Water: Hydrology and Health Implications,” in Tritium Advances in Research and Applications, M. Janković, Ed., New York (NY), USA: Nova Science Publishers, 2018, ch. 5, pp. 157 – 213.
3. J. Nikolov et al., “Different methods for tritium determination in surface water by LSC,” Appl. Radiat. Isot., vol. 71, no. 1, pp. 51 – 56, Jan. 2013.
   DOI: 10.1016/j.apradiso.2012.09.015
   PMid: 23085734
4. 1220 Quantulus Ultra Low Level Liquid Scintillation Spectrometer, PerkinElmer Life and Analytical Sciences, Shelton (CT), USA, 2005.
   Retrieved from: https://www.perkinelmer.com.cn/CMSResources/Images/46-73870SPC_1220Quantulus.pdf;
   Retrieved on: May 16, 2018
5. I. Stojković et al., “Methodology of tritium determination in aqueous samples by liquid scintillation counting techniques,” in Tritium Advances in Research and Applications, M. Janković, Ed., New York (NY), USA: Nova Science Publishers, 2018, ch. 4, pp. 99 – 157.
6. Standard Test Method for Tritium in Drinking Water, ASTM D 4107–08, Jun. 15, 2013.
   DOI: 10.1520/D4107-08R13
7. I. Jakonić et al., “Optimization of low-level LS counter Quantulus 1220 for tritium determination in water samples,” Radiat. Phys. Chem., vol. 98, pp. 69 – 76, May 2014.
   DOI: 10.1016/j.radphyschem.2014.01.012

Natural mineral waters used in therapeutic treatments present diverse chemical composition which can include natural radionuclides, such as radon, increasing the risk of exposure to natural radiation for both workers and bathers. The purpose of the present study was to evaluate the radon concentration in natural mineral waters of 17 Portuguese thermal establishments. The evaluation was carried out between 2013 and 2015 in several places of each thermal establishment. An analysis of the compliance between the obtained values and the existing legal requirements for the different parameters concerning radon concentration in water was made. The results showed the presence of anomalous values both higher than the reference level and the action level. Approximately 50% of the obtained results are higher than the reference level recommended by the EU, while 20% of the results exceeded the action level. These results may also imply high concentrations of indoor radon (and hence occupational exposure to radon), since the natural mineral water will be a continuous source of this radionuclide. The high values obtained in some cases are worrying and show the need for a more detailed and extensive study, both in space and time.

1. Radão – um gás radioativo de origem natural, Instituto Tecnológico e Nuclear, Lisboa, Portugal, 2010. (Radon - a radioactive gas of natural origin, Technological and Nuclear Institute, Lisbon, Portugal, 2010.)
   Retrieved from: http://www.itn.pt/docum/relat/radao/itn_gas_radao.pps;
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2. U. A. Tarim et al., “Evaluation of radon concentration in well and tap waters in Bursa, Turkey,” Radiat. Prot. Dosim., vol. 150, no. 2, pp. 207 – 212, Jun. 2012.
   DOI: 10.1093/rpd/ncr394
   PMid: 21990391
3. Radon Toxicity, Agency for Toxic Substances and Disease Registry, Atlanta (GA), USA, 2010.
   Retrieved from: https://www.atsdr.cdc.gov/csem/radon/radon.pdf;
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4. Radiation Protection against Radon in Workplaces other than Mines, Safety Report Series No. 33, IAEA, Vienna, Austria, 2003.
   Retrieved from: https://www-pub.iaea.org/MTCD/Publications/PDF/Pub1168_web.pdf;
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5. Lung Cancer Risk from Radon and Progeny and Statement on Radon, ICRP Publication 115, ICRP, Ottawa, Canada, 2010.
   Retrieved from: http://radon-and-life.narod.ru/pub/ICRP_115.pdf;
   Retrieved on: Aug. 15, 2018
6. K. Schmid, T. Kuwet, H. Drexler, “Radon in Indoor Spaces: An underestimated risk factor for lung cancer in environmental medicine,” Dtsch. Arztebl. Int., vol. 107, no. 11, pp. 181 – 186, Mar. 2010.
   DOI: 10.3238/arztebl.2010.0181
   PMid: 20386676
   PMCid: PMC2853156
7. Radon and cancer, Fact Sheet no. 291, WHO, Geneva, Switzerland, 2007.
   Retrieved from: http://www.who.int/en/news-room/fact-sheets/detail/radon-and-health;
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8. Effects of Ionizing Radiation, vol. 2, UNSCEAR, New York (NY), 2009.
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9. WHO handbook on Indoor Radon: A Public Health Perspective, WHO, Geneva, Switzerland, 2009.
   Retrieved from: http://apps.who.int/iris/bitstream/handle/10665/44149/9789241547673_eng.pdf?sequence=1;
   Retrieved on: Aug. 15, 2018
10. Health Risk of Radon, EPA, Washington (DC), USA, 2018.
    Retrieved from: https://www.epa.gov/radon/health-risk-radon;
    Retrieved on: Aug. 28, 2018
11. A. M. S. Ferreira, “Radioactividade das Águas da Região Subterrâneas do Minho,” Dissertação de Mestrado, Universidade do Minho, Escola de Ciências, Braga, Portugal, 2009. (A. M. S. Ferreira, “Water Radioactivity of Waters of the Subterranean Region of Minho,” M.Sc. dissertation, University of Minho, School of Sciences, Braga, Portugal, 2009.)
12. A. S. Silva, M. L. Dinis, “Measurements of indoor radon and total gamma dose rate in Portuguese thermal spas,” in Occupational Safety and Hygiene IV,P. Arezes, J. S. Baptista, M. Barroso, P. Carneiro, P. Cordeiro, N. Costa, R. Melo, A. S. Miguel, G. Perestrelo, Eds., London, UK: Taylor & Francis Group, 2016. pp. 485 – 489.
13. K. Q. Lao, Controlling indoor radon: measurement, mitigation, and prevention, New York (NY), USA: Van Nostrand Reinhold, 1990.
14. M. Al Zoughool, D. Krewski, “Health effects of radon: a review of the literature,” Int. J. Radiat. Biol., vol. 85, no. 1, pp. 57 – 69, Jan. 2009.
    DOI: 10.1080/09553000802635054
    PMid: 19205985
15. M. Erdogan, F. Ozdemir, N. Eren, “Measurements of radon concentration levels in thermal waters in the region of Konya, Turkey,” Isotopes Environ. Health Stud., vol. 49, no. 4, pp. 567 – 574, 2013.
    DOI: 10.1080/10256016.2013.815182
    PMid: 23937805
16. A. S. Silva, M. L. Dinis, A. J. S. C. Pereira, “Assessment of indoor radon levels in Portuguese thermal spas,” Radioprotection, vol. 51, no. 4 pp. 249 – 254, Oct-Dec. 2016.
    DOI: 10.1051/radiopro/2016077.
17. Case studies in Environmental Medicine, ATSDR, Washington (DC), 2012.
    Retrieved from: https://www.atsdr.cdc.gov/csem/radon/radon.pdf;
    Retrieved on: Aug. 15, 2018
18. Standard Test Method for Radon in Drinking Water, ASTM D5072 – 09, 2009.
    DOI: 10.1520/D5072-09
19. C. V. M. Gonçalves, A. J. S. C. Pereira, “Radionuclides in groundwater of the Serra do Buçaco region (Central Portugal),” in Proc. XXXV Congress of the International Association of Hydrogeologists, Lisbon, Portuga, 2007, p. 6.
20. Consumer`s Guide to Radon Reduction: How to Fix Your Home, EPA 402/K-10/005, EPA, Washington (DC), USA, 2013.
    Retrieved from: https://www.epa.gov/sites/production/files/2016-02/documents/2013_consumers_guide_to_radon_reduction.pdf;
    Retrieved on: Aug. 18, 2018
21. The Council of the European Union. (Oct. 22, 2013). Directive 2013/51/EURATOM laying down requirements for the protection of the health of the general public with regard to radioactive substances in water intended for human consumption.
    Retrieved from: https://eur-lex.europa.eu/legal-content/EN/TXT/PDF/?uri=CELEX:32013L0051&from=EN;
    Retrieved on: Aug. 18, 2018
22. J. A. S. Cortez et al., Águas Minerais Naturais e de Nascente da Região Centro, Aveiro, Portugal: Mare Liberum, 2012. (J. A. S. Cortez et al., “Natural and Spring Mineral Waters of the Central Region,” Aveiro, Portugal: Mare Liberum, 2012.)
23. P. Diegues, V. Martins, Águas termais riscos e benefícios para a saúde, Lisboa, Portugal: Auditório IPQ, 2010. (P. Diegues, V. Martins, Thermal waters risks and benefits for health, Lisbon, Portugal: Auditório IPQ, 2010.)
    Retrieved from: https://www.dgs.pt/ficheiros-de-upload-2/sa-aguas-termais-riscos-e-beneficios-para-a-saude_final_a.aspx;
    Retrieved on: Aug. 18, 2018
24. U. A. Tarim et al., “Evaluation of radon concentration in well and tap waters in Bursa, Turkey,” Radiat. Prot. Dosim., vol.150, no. 2, pp. 207 – 212, Jun. 2012.
    DOI: 10.1093/rpd/ncr394
    PMid: 21990391
25. V. Radolić, B. Vuković, G. Smit, D. Stanić, J. Planinić, “Radon in the spas of Croatia,” J. Environ. Radioact., vol. 83, no. 2, pp. 191 – 198, 2005.
    DOI: 10.1016/j.jenvrad.2005.02.016
    PMid: 15925434
26. A. Pereira, L. Neves, C. Gomes. J. Figueiredo, A. Vicente, “Concentração do gás radão em habitações da região de Castelo Branco (Portugal Central) e factores geológicos condicionantes,” em Proc. VI Congresso Ibérico de Geoquímica e XV Semana de Geoquímica, Vila Real, Portugal, 2007. (A. Pereira, L. Neves, C. Gomes, J. Figueiredo, A. Vicente, “Gas concentration in the habitation region of Castelo Branco (Central Portugal) and geological conditioning factors,” in Proc. VI Iberian Congress of Geochemistry and XV Geochemistry Week, Vila Real, Portugal, 2007.)
    Retrieved form: https://dadospdf.com/queue/concentraoes-do-gas-radao-em-habitaoes-da-regiao-de-castelo-branco-portugal-central-e-factores-geologicos-condicionantes-_5a44ce58b7d7bc891f84fb71_pdf?queue_id=-1;
    Retrieved on: Aug. 18, 2018

Radon exposure in the workplace is one of the main exposures to the population after that in dwellings. These workplaces are generally at the ground and/or first floor, where radon concentration is generally higher than at upper ones. This study deals with the measurements of indoor radon concentration in several workplaces located in different geological conditions. Measurements of indoor radon concentration have been carried out using passive bare detectors based on CR -39 in 50 workplaces, including one site at the Centre of Applied Nuclear Physics, Tirana. According to the principles of the methodology, the radon passive detectors have been located inside the workplaces for three months exposure, allowing the calculation of average values, which represent much better the true values of the radon concentration inside of a closed environment. The exposure time of detectors was performed during period January–April 2014. According to the assessment made by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR), radon in the natural environment constitutes about 50% of the human exposure to natural radiation or 1.2 mSv/year. The measurements were used to calculate the effective dose due to the radon contribution (mSv/y). Based on the results of the measurements, the minimum value of the radon concentration found is 53 Bq/m³ to 400 Bq/m³ in workplaces, while the reference levels are 300 Bq/m³. Around 90% of the radon concentration values are within reference levels. The results of this study represent a variation of radon concentration related to geological composition. More detailed studies are needed in areas with different geology and construction materials for a better spatial distribution of radon concentration, particularly in public places.

1. Radiation Protection and Safety of Radiation Sources, No. GSR Part 3, IAEA, Vienna, Austria, 2014.
   Retrieved from: https://www-pub.iaea.org/MTCD/publications/PDF/Pub1578_web-57265295.pdf;
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2. WHO Handbook on Indoor Radon: A Public Health Perspective, WN 615, WHO, Geneva, Switzerland, 2009.
   Retrieved from: http://whqlibdoc.who.int/publications/2009/9789241547673_eng.pdf;
   Retrieved on: Jan. 15, 2018
3. The Council of European Union. (Dec. 5, 2013). Council Directive 96/29/ EURATOM Laying down basic safety standards for protection against the dangers arising from exposure to ionizing radiation.
   Retrieved from: https://eur-lex.europa.eu/legal-content/EN/TXT/?uri=CELEX%3A32013L0059;
   Retrieved on: Jan. 12, 2018
4. K. Bode Tushe et al., “First step toward the geographical distribution of indoor radon in dwellings in Albania,” Radiat. Prot. Dosimetry, vol. 172, no. 4, pp. 488 – 495, Dec. 2016.
   DOI: 10.1093/rpd/ncv494
   PMid: 26656073
5. Këshilli i ministrave. (25.11.2015). No. 957 date 25.11.2015. Për miratimin e rregullores "për nivelet e lejuara të përqendrimit të radonit në ndërtesa dhe ujë, nivelet udhëzuese të radiobërthamave në materialet e ndërtimit, si dhe nivelet e lejuara të radiobërthamave në ushqime dhe produkte kozmetike". (Decision of the Council of Ministers. (Nov. 25, 2015). No. 957, dated 25.11.2015, Improving regulatory standards and concentration of indoor radon and radioactive concentration in goods, in order to protect the public.)
   Retrieved from: http://www.ishp.gov.al/wp-content/uploads/2015/materiale/R.%20Nr.591%20date%2018.08.2011%20Per%20nivelet% 20e%20lejuara%20te%20perqendrimit%20te%20radonit.pdf
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6. M. A. Lopez et al., “Workplace monitoring for exposures to radon and to other natural sources in Europe integration of monitoring for internal and external exposures,” Radiat. Prot. Dosimetry, vol. 112, no. 1, pp. 121 – 139, Nov. 2004.
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   PMid: 15574988
7. National and regional surveys of radon concentration in dwellings, IAEA/AQ/33, IAEA, Vienna, Austria, 2013.
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8. G. M. Kendall, T. J. Smith, “Doses to organs and tissues from radon and its decay products,” J. Radiol. Prot., vol. 22, no. 4, pp. 389 – 406, Dec. 2002.
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10. H. Reci, S. Dogjani, I. Jata, I. Milushi, “Estimation of radon risk in Shkodra Region,” presented at the Second East European Radon Symposium (Rn SEERAS 2014), Nis, Serbia, 2014.

In this paper, SRIM (The Stopping and Range of Ions in Matter) software package is used to simulate the interaction of alpha particles into the material of radiometric analytical filters. The effect of alpha particle self-absorption in alpha radiometric filters measurements is estimated, especially in the range of natural alpha energy (5-9 MeV, Radon and Thoron alpha energy). Software package SRIM allows to calculate the parameters of the ions interaction with target material using a Monte Carlo simulation method based on a quantum mechanical treatment of ion-atom collisions. The effect of the radiometric analytical filter material on the transmitted efficiency of alpha energy is discussed. As the energy increases the self-absorption in analytical filter material is decreased but still has a clear effect. In this case, the filter material and the space distance between the filter and the detector window decrease the number of alpha particles which reach to the detector window.

1. R. Whitcher, “Calculation of the average solid angle subtended by a detector to source in a parallel plane by a Monte Carlo method,” Radiat. Prot. Dosim., vol. 102, no. 4, pp. 365 – 369, 2002.
   DOI: 10.1093/oxfordjournals.rpd.a006107
   PMid: 12474948
2. S. Pickering, “The interpretation of alpha energy spectra from particulate sources,” J. Aerosol Sci., vol. 15, no. 5, pp. 533 – 543, 1984.
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3. R. J. Krupa, K. Kurzak, “Simulation and evaluation of aspectra obtained with semiconductor detectors,” Nucl. Instrum. Methods A, vol. 307, no. 2-3, pp. 469 – 483, Oct. 1991.
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   DOI: 10.1016/0168-9002(94)91334-X
5. F. A. Seiler, G. J. Newton, R. A. Guilmette, “Continuous monitoring for airborne alpha emitters in a dusty environment,” Health Phys., vol. 54, no. 5, pp. 503 – 515, May 1988.
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6. T. Geryes, C. Monsanglant-Louvet, E. Gehin, “Experimental and simulation methods to evaluate the alpha self-absorption factors for radioactive aerosol fiber filters,” Radiat. Meas., vol. 44, no. 9-10, pp. 763 – 765, Oct-Nov. 2009.
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7. D. P. Higby, Effects of Particle Size and Velocity on Burial Depth of Airborne Particles in Fiber Filters, Rep. PNL-5278, National Technical Information Service., Springfield (VA), USA, 1984.
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8. J. W. Luetzelschwab, Ch. Storey, K. Zraly, D. Dussinger, “Self-absorption of alpha and beta particles in a fiberglass filter,” Health Phys., vol. 79, no. 4, pp. 425 – 430, Oct. 2000.
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   PMid: 11007466
9. J. F. Ziegler, M. D. Ziegler, J. P. Biersack, “SRIM The Stopping and Range of Ions in Matter,” Nucl. Instrum. Methods Phys. Res. B, vol. 268, no. 11-12, pp. 1818 – 1823, Jun. 2010.
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10. Y. A. M. Mostafa, M. Vasyanovich, M. Zhukovsky, N. Zaitceva, “Calibration system for radon EEC measurements,” Radiat. Prot. Dosimetry, vol. 164, no. 4, pp. 587 – 590, Jun. 2015.
    DOI: 10.1093/rpd/ncv316
    PMid: 25979737

It is well-known that radon is the second important human carcinogen for lung cancer, after smoking. The major sources of indoor radon concentrations are soil and building material. Under certain conditions, a dose received from the inhalation of radon and its progenies can be higher than a dose received from the external exposure due to radium concentration in building materials. In this contribution, the results of the radon and thoron exhalation rate measurement from 9 commonly used building materials are reported. Exhalation rate measurements were performed with accumulation chamber method using active device for measurement of radon concentration.

1. Sources and Effects of Ionizing Radiation, vol. 1, Annex B, UNSCEAR 2000 Report to the General Assembly with Scientific Annexes, UNSCEAR, New York (NY), USA, 2000.
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   Retrieved on: Nov. 20, 2018
2. Handbook on Indoor Radon: A public health perspective, WHO, Geneva, Switzerland, 2009.
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   Retrieved on: Nov. 20, 2018
3. Who guidelines for indoor air quality: selected pollutants, WHO Regional Office for Europe, Copenhagen, Denmark, 2010.
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4. I. Yarmoshenko, A. Vasilyev, A. Onishchenko, S. Kiselev, M. Zhukovsky, “Indoor radon problem in energy efficient multi-storey buildings,” Radiat. Prot. Dosim. vol. 160, no. 1-3, pp. 53 – 56, Jul. 2014.
   DOI: 10.1093/rpd/ncu110
   PMid: 24723188
5. P. Ujić et al., “Internal exposure from building materials exhaling 222 Rn and 220 Rn as compared to external exposure due to their natural radioactivity content,” Appl. Radiat. Isot., vol. 68, no. 1, pp. 201 – 206, Jan. 2010.
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6. P. Ujić, I. Čeliković, A. Kandić, Z. Žunić, “Standardization and difficulties of the thoron exhalation rate measurements using an accumulation chamber,” Radiat. Meas., vol. 43, no. 8, pp. 1396 – 1401, Sep. 2008.
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7. A. Awhida et al., “Novel method of measurement of radon exhalation from building materials,” J. Environ. Radiat. vol. 164, pp. 337 – 343, Nov. 2016.
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The IEA-R1 research reactor works 40h weekly, with 4.5 Mw power. The storage rack for spent fuel elements has less than half of its initial capacity. Under these conditions, the reactor operating for 32h/week will have 3 spent fuel by year, approximately 3 utilization rate Positions/year; thus, we will have only about six years of capacity for storage. Since the desired service life of the IEA-R1 is at least another 20 years, it will be necessary to increase the storage capacity of spent fuel by doubling the wet storage in the reactor’s pool. 3M’s neutron absorber Boralcan^TM was chosen after reviewing the literature about available materials for the construction of a new storage rack. This work presents studies for the construction of new storage racks with double of capacity using the same place of the current ones. Criticality safety analysis was performed with MCNP-5 Monte Carlo code, using two Evaluated Nuclear Data Files (ENDF/B-VI and ENDF/B-VII) in calculations, and subsequently, the results were compared. The full charge of the storage rack with only new fuel elements (maximum reactivity) was considered to calculate the keff. The results obtained in the simulations show that it is possible doubling the storage capacity of the spent fuel elements. Additionally, it complies with safety limits established by International Atomic Energy Agency (IAEA) and Brazilian Commission of Nuclear Energy (CNEN) standards to the criticality criteria (keff <0.95). This is only possible with the use of neutron absorber material.

1. R. N. Saxena, “The IEA-R1 research reactor 50 years of operating experience and utilization” in Proc. IAEA International Conference on Safe Management and Utilization of Research Reactors, Sydney, Australia, 2007.
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   Retrieved on: Feb. 24, 2018
2. A. C. I. Rodrigues, T. Madi Filho, W. And Ricci Filho, “Borated stainless steel storage project to the spent fuel of the IEA-R1 reactor,” in Proc. International Nuclear Atlantic Conference (INAC 2013), Recife, Brazil, 2013.
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3. A. C. I. Rodrigues, T. Madi Filho, P. T. D. Siqueira, W. Ricci Filho, “Design of a new wet storage rack for spent fuels from IEA-R1 reactor,” in Proc. International Nuclear Atlantic Conference (INAC 2015), São Paulo, Brazil, 2015.
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ZnO polycrystalline thin films and ZnO nanorod arrays were obtained by the spray pyrolysis method at a substrate temperature of 450 °C. By analyzing the XRD diffractograms, the hexagonal crystal structure of the ZnO films and ZnO nanorods was determined. On the other hand, the grain size of the films and nanorods was determined using the Debye-Scherrer equation. The optical properties of the films and nanorods were determined by measuring the dependence of the transmission on the wavelength of the light. Also, the optical band gap of 3.28 eV for the ZnO films and 3.21 eV for the ZnO nanorods was estimated. The photoconductivity spectrum of thin films and nanorods was recorded in the visible light range and their photoconductivity was studied when they were illuminated by X-rays, where the incident X-rays increase the conductivity of thin films of nanorods. The surface morphologies of the ZnO films and the ZnO nanorods, as well as the grain size of the film and the dimensions of the nanorods, were studied by a scanning electron microscope.

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A new series of dosimetric devices, based on the optically stimulated luminescence (OSL) of BeO, is presented. The dosimetric properties of BeO and the use of OSL are favorable with a linear range at least up to 10 Sv, near tissue energy response, and because of the use of OSL as a measurement technique, the dose information can be re-read. The myOSLraser device combines measurement and zeroing equipment in a single unit and is thus cost and time efficient. The manual reader for single myOSLdosimeters, consisting of two BeO-elements for Hp(0.07) and Hp(10), can be expanded by myOSLautomation, which allows a fully automated analysis of 200 dosimeters. The system exceeds the requirements of EN/IEC 62387. A truly portable handheld device (myOSLchip) allows the manual operation of single element dosimeters, e.g. in phantoms. A simple method is proposed to use the OSL decay signal for the normalization of equipment and bringing into line the sensitivity between instruments.

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The aim of this research is to study the use of polycarbonate as a reusable radiochromic integrating dosimeter for the determination of high doses of ionizing radiation in the (range of 0.1 to 10 kGy). The region of the linear dependence of the optical density of polycarbonate samples on gamma radiation dose, as well as the fading of the radiation effect and the possibility of accelerating this fading by annealing have been explored. To determine the effect of oxygen concentration on changes in optical density and the rate of oxygen diffusion into the polycarbonate, some samples were stored in a pure oxygen atmosphere, produced by electrolytic dissociation of distilled water using a fuel cell.

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Chronic lymphatic leukemia (CLL) was formerly considered to be a non-radiogenic form of cancer. Non-Hodgkin Lymphomas (NHL) were supposed to be very rare after radiation exposure. These historical estimations were based on the early observations of the Japanese A-bomb survivors. In contrast to these conclusions, increasing rates of CLL and NHL were found in the last decades in nuclear workers and liquidators of Chernobyl, i.e. in cases of low dose chronic exposure. Estimating the dose response, the authors generally refer to the bone marrow as the corresponding target organ which often leads to surprisingly high-risk figures for the radiation effect. We recently investigated three cases of people suffering from B-lymphocyte proliferation (two CLLs and one lymphoma) who were involved in the decontamination of nuclear establishments, because Germany decided to go out of nuclear energy, and they started tearing down the plants. The men worked in the same enterprise, were exposed to external doses of 46, 108 and 116 mSv, and had certainly inhaled alpha emitters such as uranium and plutonium isotopes. In the 1980s, radiation hematologists stated that the bone marrow should not be considered as the relevant target of B-cell lymphomas and CLL of B-cell type because the effect results in a proliferation of mature B lymphocytes which mainly occur outside the bone marrow. Therefore, the diseases may be induced in the whole pool of B lymphocytes including all peripheral locations also comprising lymph nodes and lymphatic organs. Our impression is that CLL and NHL are initiated predominantly at workplaces where the possibility of open radioactivity exists: in uranium mines, uranium and radium processing facilities, nuclear facilities, and consequently in liquidators. Several studies involving animals and humans have shown that incorporated radionuclides such as uranium, thorium, and plutonium concentrate in the lymph nodes leading to higher radiation doses to the lymphocytes than are provided in other tissues. This effect is explained by the immunological reaction of macrophages functioning as scavengers of particles such as materials emitting alpha-radiation. These cells circulating via the lymph vessels are stored in the stationary lymph nodes. If the target organ for dosimetry must be seen in all mature B lymphocytes in the body, this will be valid for all kinds of external and internal exposures. Except in cases of homogeneous whole-body exposure, any dose estimation will be extremely unsafe or – as in our examples – not possible. These limitations must be considered when planning the radiation protection strategies for nuclear workers and adequate evaluation in compensation cases.

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36. A. T. Keane, A. P. Polednak, “Retention of uranium in the chest: implications of findings in vivo and post-mortem,” Health Phys.,vol. 44, suppl. 1, pp. 391 – 402, Jan. 1983.
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37. N. P. Singh, D. D. Bennett, M. E. Wrenn, G. Saccomanno, “Concentrations of α-emitting isotopes of U and Th in uranium miners’ and millers’ tissues,” Health Phys., vol. 53, no. 3, pp. 261 – 265, Sep. 1987.
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Charged particle therapy is a precise radiotherapy method for the treatment of solid tumors. This method can deliver conformal dose distributions minimizing damage to healthy tissues thanks to its characteristic dose profile. However, the steep dose profile of charged particle beams (due to the Bragg peak) can result in over- or under-dosage in critical regions. Monitoring the range of the charged particles is therefore highly desirable. In this study, we use a planar in-beam PET system for the range verification of pencil beams in proton therapy. The planar geometry of the DoPET system is advantageous because it can be used online, i.e., during treatment. In the particle therapy community, the Monte Carlo (MC) codes are widely used to evaluate the radiation transport and interaction with matter. For this reason, the FLUKA MC code was used to simulate the experimental conditions of irradiations performed at the Cyclotron Centre Bronowice (CCB) proton therapy center in Krakow (PL). 130MeV pencil beams were delivered on phantoms mimicking human tissues. Different acquisitions are analyzed and compared with the MC predictions. The image reconstruction for experimental data and simulation is based on the Maximum Likelihood Estimation Method (MLEM) algorithm. A special focus in the paper will be on the validation of the PET detector response for activity range verification.

1. D. Schulz-Ertner, H. Tsuji, “Particle radiation therapy using proton and heavier ion beams,” J. Clin. Oncol., no. 25, no. 8, pp. 953 – 964, Mar. 2007.
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2. A. Knopf, A. Lomax, “In vivo proton range monitoring: a review,” Phys. Med. Biol., vol. 58, no. 15, pp. R131 – R160, Aug. 2013.
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3. X. Zhu, G. El Fahkri, “Proton therapy verification with PET imaging,” Theranostics, no. 3, no. 10, pp. 731 – 740, Sep. 2013.
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4. A. Del Guerra et al., “Positron emission tomography: its 65 years,” Riv. Nuovo Cim., no. 39, no. 4, pp. 155 – 223, Apr. 2016.
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5. K. Parodi et al., “In-beam PET measurements of b+ radioactivity induced by proton beams,” Phys. Med. Biol., vol. 47, no. 1, pp. 21 – 36, Jan. 2002.
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6. G. Sportelli et al., “First full-beam PET acquisitions in proton therapy with a modular dual-head dedicated system,” Phys. Med. Biol., no. 59, vol. 1, pp. 43 – 60, Jan. 2013.
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7. N. Camarlinghi et al., “An in-beam PET system for monitoring ion-beam therapy: test on phantoms using clinical 62 MeV protons,” J. Instrum., vol. 9, no. 4, C04005, Apr. 2014.
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8. L. Brombal et al., “Proton therapy treatment monitoring with in-beam PET: Investigating space and time activity distributions,” Nucl. Instrum. Methods Phys. Res. A, vol. 861, pp. 71 - 76, 2017.
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9. S. Helmbrecht et al., “In-beam PET at clinical proton beams with pile-up rejection”, Zeitscrift für Medicinische Physik, vol. 27, pp. 202-217, 2017
10. S. Moehrs et al., “Multi-ray-based system matrix generation for 3D PET reconstruction,” Phys. Med. Biol., vol. 53, no. 23, pp. 6925 – 6945, Dec. 2008.
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11. S. Muraro et al., “Proton therapy treatment monitoring with the DoPET system: Activity range, positron emitters evaluation and comparison with Monte Carlo predictions,” J. Instrum., vol. 12, C12026, Dec. 2017.
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12. A. Ferrari, P. Sala, A. Fassò, J. Ranft, FLUKA: A Multi-Particle Transport Code, Rep. CERN-2005-10, INFN/TC_05/11, SLAC-R-773, CERN, INFN, SLAC, Geneva, Switzerland, 2005.
    Retrieved from: https://www.slac.stanford.edu/pubs/slacreports/reports16/slac-r-773.pdf;
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13. T. T. Boehlen et al., “The FLUKA code: developments and challenges for high energy and medicalapplications,” Nucl. Data Sheets, vol. 120, pp. 211 – 214, Jun. 2014.
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14. G. Battistoni et al., “The FLUKA code: an accurate simulation Tool for Particle Therapy,” Front. Oncol.,vol. 6, no. 116, May 2016.
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15. V. Rosso et al., “A new PET prototype for proton therapy: Comparison of data and Monte Carlo simulation,” J. Intrsum.,vol. 8, C03021, Mar. 2013.
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16. A. Kraan et al., “Online monitoring for proton therapy: A real-time procedure using a planar PET system,” Nucl. Instrum. Methods Phys. Res. A, vol. 786, pp. 120 – 126, Jun. 2015.
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The Techa River (the Urals, Russia) was heavily contaminated due to the release of radionuclides from the Mayak Production Association. The radioactive releases included bone-seeking beta-emitters such as 90Sr and 89Sr that contribute to doses to bone marrow. Moreover, 90Sr is a long-lived isotope, the uptake of which leads to a chronic bone marrow exposure known to result in an increased risk of leukemias. Ongoing epidemiological studies of the long-term effects of chronic radiation exposure are being performed for the Techa River Cohort members. Radiation dosimetry is a part of this study, of which, the internal dose estimates for active bone marrow exposed to beta emission of Sr isotopes incorporated in calcified tissue is an important component. Internal dose calculations, which are based on electron-photon transport simulations, require geometrical descriptions of bone shapes and bone microstructures of the main hematopoietic sites of the human skeleton (ribs, vertebrae, pelvic bones, femur, humeri, bones of the skull, sternum, clavicle and scapula). For this purpose, the parametric approach for modeling bone geometry was elaborated. The proposed approach can be used to segment and define each of the bone sites as simple geometric shapes for which parameters can be derived. The aim of the paper is to present the principles of bone segmentation. Dose factors that convert the activity concentration of bone-seeking radionuclides into a corresponding bone marrow dose rate were calculated for each segment. The calculations were done with MCNP6. The bone segmentation allows optimizing the size of the computational phantom (in terms of voxel number), substituting the complex–shaped bone model with a set of simple stylized phantoms and taking into account the heterogeneity of bone microstructure.

1. M. O. Degteva, N. B. Shagina, M. I. Vorobiova, L. R. Anspaugh, B. A. Napier, “ Reevaluation of waterborne releases of radioactive materials from the Mayak Production Association into the Techa River in 1949-1951,” Health Phys., vol. 102, no. 1, pp. 25 – 38, Jan. 2012.
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2. L. Yu. Krestinina et al., “Leukaemia incidence in the Techa River Cohort: 1953-2007,” Brit. J. Cancer, vol. 109, no. 11, pp. 2886 – 2893, Nov. 2013.
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3. M. Hough et al., “An image-based skeletal dosimetry model for the ICRP reference adult male – internal electron sources,” Phys. Med. Biol.,vol. 56, no. 8, pp. 2309 – 2346, Apr. 2011.
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4. F. W. Spiers et al., “Mean skeletal dose factors for beta-particle emitters in human bone: Part I: Volume-seeking radionuclides,” Brit. J. Radiol., vol. 51, no. 608, pp. 622 – 627, Aug. 1978.
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5. V. I. Zalyapin et al., “A parametric stochastic model of bone geometry,” Bull. South Ural State University, Ser. Mathematical Modelling, Programming & Computer Software (SUSU MMCS), vol. 11, no. 2, Chelyabinsk, Russia, Jun. 2018.
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6. A. Yu. Volchkova et. al., Effect of the Shape of the Bone on the Power of the Doses in the Bone Marrow of a Person. Materials of the VI International Scientifc and Practical Conference, Chelyabinsk, Russia, 2016, pp 36 -41. (in Russian).
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7. The ICRP computational framework for internal dose assessment for reference adults: specific absorbed fractions. ICRP Publication 133. Ann. ICRP 45(2), pp 1–74; 2016.
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8. B. A. Campbell et al., “Distribution Atlas of Proliferating Bone Marrow in Non-Small Cell Lung Cancer Patients Measured by FLT-PET/CT Imaging. With Potential Applicability in Radiation Therapy Planning,” Int. J. Radiat. Oncol. Biol. Phys., vol. 92, no. 5, pp. 1035 – 1043, Aug. 2015.
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9. E. A. Shishkina et al., “Parametric stochastic model of bone structures to be used in computational dosimetric phantoms of human skeleton,” in Proc. 6th Int. Conf. Radiation and Applications in Various Fields of Research (RAD 2018), Ohrid, Macedonia, 2018, accepted for publication.
10. N. B. Shagina et al., “Age and gender specific biokinetic model for strontium in humans”. Radiol Prot., vol. 35; no 1, pp. 87-127, Jan 2015.
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The objective was to compare the contrast enhanced computed tomography (CT) “LOW DOSE” protocol for thoraco-abdominal scans, with the standard CT protocol for oncologic follow up. We analyzed these two different imaging techniques and the overall radiation dose in order to determine benefits in terms of diagnosis. We included 50 patients where oncologic follow up included a triphasic thoraco-abdominal CT for staging of liver disease. Eligibility criteria were the medical indication for a contrast-enhanced thoraco-abdominal CT as part of an oncologic follow up (breast cancer, hepatocarcinoma, neuroendocrine tumors, kidney cancer and prostatic cancer) and the availability of previous enhanced CT scans performed over the past year of follow up. The LOW DOSE protocol for triphasic CT in oncologic follow up permits saving of effective dose up to 50% (27% on average) for each scan and an overall saving of up to 40% (15% on average) for complete procedure in the normal BMI group. The LOW DOSE protocol was also effective in the diagnosis of thromboembolic disease. All the scans from the LOW DOSE CT protocol were analyzed by radiologists, all with at least 10 years of experience, unaware of the introduction of the protocol – there were no reported differences or difficulties in diagnosis compared to the standard CT protocol.

1. Recommendations of the International Commission on Radiological Protection, ICRP Publication 103, Ottawa, Canada, 2007.
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2. European Commission. (Feb. 18, 2000). European guidelines of quality criteria for computed tomography.
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3. Basic anatomical and physiological data for use in radiological protection, ICRP Publication 89, ICRP, Ottawa, Canada, 2002.
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4. Relative biological effectiveness (RBE), quality factor (Q), and radiation weighting factor (wR), ICRP Publication 92, ICRP, Ottawa, Canada, 2002.
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5. Low dose extrapolation of radiation-related cancer risk, ICRP Publication 99, ICRP, Ottawa, Canada, 2005.
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6. Assessing dose of the representative person for the purpose of radiation protection of the public and the optimisation of radiological protection: Broadening the process,ICRP Publication 101, ICRP, Ottawa, Canada, 2006.
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7. G. Starck, L. Lonn, et al., “A method to obtain the same levels of CT image noise for patients of various size, to minimize radiation dose,” Br. J. Radiol., vol. 75, no. 890, pp. 140 – 150, Feb. 2002.
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8. C. S. Alvin, J. L. Holly et al., “Innovation in CT Dose Reduction Strategy: Application of the Adaptive Statistical Iterative Reconstruction Algorithm,” Am. J. Roentgenol., vol. 194, no. 1, pp. 191 – 199, Jan. 2010.
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The aim of the study was to present the epidemiological characteristics, new diagnostics trends and prevention of the pulmonary diseases related to dust (PDD) in Bulgaria. Retrospective epidemiological study during the period 1980-2003 y. was done. A new cross sectional case control study of workers exposed to high concentration mineral dust and non-exposed control group in 2003 year were performed. Non patrametric, correlation analysis and linear statidstical analysis were performed. An SPSS statistical package was used. Epidemiological trends of different types of pneumoconiosis, and 11 years study of tendencies in malignant mesothelioma in the country were analyzed. A prognosis of the appearance of PDD during the future 10 – 30 years was done. A comparison between chest radiographic images and HRCT amongst pneumoconiotic patients was done. Image/functional constellations for diagnostic purposes were created. The following conclusions can be made: 1. PDD play a leading epidemiological role amongst occupational diseases in Bulgaria. 2. An appearance of pneumoconiosis and asbestos-related malignant mesothelioma in the next 10 – 20 years was expected. 3. HRCT, as well as constellation HRCT/VC, FVC and FEF50% could be more correct diagnostic methods in pneumoconioses.

1. Е. Петрова, “Късни форми на силикоза и силикотуберкулоза,” Канд. дисертация, Медицински Университет, София, 1988. (E. Petrova, “Late forms of silicosis and silicotuberculosis,” Ph.D. dissertation, Medical University, Sofia, 1988.)
2. A. d’ Mannetje et al., “Exposure-response analysis and risk assessment for silica and silicosis mortality in a pooled analysis of six cohorts,” Occup. Environ. Med., vol. 59, no. 11, pp. 723 – 728, Nov. 2002.
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3. Еarly Detection of Occupational Diseases, Id. 924154211X, WHO, Geneva, Switzerland, 1986.
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6. L. Olivetti et al., “Anatomo-radiologic definition of minimal interstitial silicosis and diagnostic contribution of high-resolution computerized tomography,” Radiol. Med., vol. 85, no. 5, pp. 600 – 605, Jun. 1993.
7. D. Sherson, “Silicosis in the twenty first century,” Occup. Environ. Med., vol. 59, no. 11, pp. 721 – 722, Nov. 2002.
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Radioactive sources used for therapy can cause very serious exposures if they are mislaid or misused. The aim of this paper is to present the measures taken in order to ensure the radiation protection in the handling of a deceased person containing I-131. The prominent pathways of exposure for occupational exposed personnel, medical exposure (family, friends) and public exposure (third person e.q. (the mortuary car driver, priest) were assessed. According to these specific conditions, the time after which the body can be taken over by the family was calculated and the doses in the handling of the deceased person, embalming, transport and burial ceremony were evaluated for each category of people. Also, the compliance with national legislation and European recommendations is discussed.

1. The 2007 Recommendations of the International Commission on Radiological Protection, ICRP Publication 103, ICRP, Ottawa, Canada, 2007.
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2. Radiological Protection in Medicine, ICRP Publication 105, ICRP, Ottawa, Canada, 2007.
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3. Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, General Safety Requirements Part 3, IAEA, Vienna, Austria, 2014, p. 24.
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6. Comisia Nationalã Pentru Controlul Activitãtilor Nucleare. (Feb. 15, 2005). 358/2004 ordin privind aprobarea normelor de securitate radiologicã pentru practica de medicinã nuclearã. (National Commission for the Control of Nuclear Activities. (Feb. 15, 2005). No. 358 Regulation on radiation safety in nuclear medicine.)
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The aim of the study is to evaluate the point doses measured by different parameters at various depths with MVCT in the Tomotherapy Hi- Art (HT) treatment unit. HT works in two modes: visual modes and therapy modes. The MVCT images are taken in the visual mode. The user can choose the scan length and image pitch value in the visual mode. The system has pitch values called fine, normal and coarse. When the same volume is scanned during the gentry rotation, the scan times of fine, normal, and coarse modes are different from one another. Cheese Phantom is used to evaluate the point doses. The measured values ranged from 0.64 to 2.67 cGy with an average dose of 1.40cGy. The lowest MVCT dose is found when 7 slices are scanned with a depth of 20 cm for 51 seconds. The highest MVCT dose is found when 17 slices are scanned with a depth of 15 cm for 101 seconds. The measured values are the highest when the fine mode is selected with low depth and high slice. The IGRT method is used before each treatment and can be used more than once if necessary. Therefore, the right mode selection can prevent taking unnecessary doses during MVCT.

1. P. Yadav, R.Tolakanahalli, Y.Rong, B. R. Paliwal, “The effect and stability ofMVCT images on adaptive TomoTherapy,” J. Appl. Clin. Med. Phys., vol. 11, no. 4, pp. 4 – 14, Jul. 2010.
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5. S. M. Goddu et al., “Enhanced efficiency in helical tomotherapy quality assurance using a custom-designed water-equivalent phantom,” Med. Bio., vol. 54, no. 19, pp. 5663 – 5674, Oct. 2009.
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6. F. Crop, A. Bernard, N.Reynaert, “Improving dose calculations on tomotherapy MVCT images,” J. Appl. Clin. Med. Phys., vol. 13, no. 6, pp. 241 – 253, Sep. 2012.
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8. R. Jeraj, T. R. Mackie, J. Balog et al., “Radiation characteristics of helical tomotherapy,” Med. Phys., vol. 31, no. 2, pp. 396 – 404, Feb. 2004.
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11. J. S. Kim et al., “Development of Video Image-Guided Setup (VIGS) System for Tomotherapy: Preliminary Study,” Prog. Med. Phys., vol. 24, no. 2, pp. 85 – 91, Jun. 2013.
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12. J. P. Mege et al., “Evaluation of MVCT imaging dose levels during helical IGRT: comparison between ion chamber, TLD, and EBT3 films,” J. Appl. Clin. Med. Phys., vol. 17, no. 1, pp. 143 – 157, Jan. 2016.
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15. K. Son et al., “Evaluation of radiation dose to organs during kilovoltage cone-beam computed tomography using Monte Carlo simulation,” J. Appl. Clin. Med. Phys., vol. 15, pp. 295 – 302, Mar. 2014.
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18. A. P. Shah et al., “Patient dose from megavoltage computed tomography imaging,” Int. J. Radiat. Oncol. Biol. Phys., vol. 70, no. 5, pp. 1579 – 1587, Apr. 2008.
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24. M. Chen, E. Chao, W. Lu, “Quantitative characterization of tomotherapy MVCT dosimetry,” Med. Dosim., vol. 38, no. 3 pp. 280 – 286, 2013.
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    PMid: 18212190

Tobacco addiction has been mentioned as a leading cause of preventable illnesses and premature disability since tobacco smoking is the main cause of lung cancer and one of the factors that most contribute to the occurrence of heart diseases, among others. The herbaceous species Nicotiana tabacum is a plant of the solanaceae family used for tobacco production. Some authors have conducted research about heavy metals and the toxicity of tobacco. It is, frequently, found in low concentrations in the ground, superficial and underground waters, even though they do not have environmental anthropogenic contributions. However, with the increase of industrial activities and mining together with the agrochemical use of contaminated organic and inorganic fertilizers, an alteration of the geochemical cycle occurs. As a consequence, the natural flow of that materials increases and release into the biosphere, where they are often accumulated in the superior layer of the ground, accessible to the roots of the plants. During planting and plant development, fertilizers and insecticides, including organochlorines and organophosphates, are used; consequently, the smoke from cigarette smoking presents various toxic substances, including heavy metals, such as Chromium (Cr), Manganese (Mn) and Antimony (Sb). Elements studied in this work. The procedures for the preparation of the samples were carried out in our laboratories and submitted to irradiation with thermal neutrons at IPEN/CNEN-SP, in the IEA-R1 research reactor. The irradiated material was, then, analyzed by gamma spectrometry, using a high purity germanium detector (HPGe).

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Incompatible elements (IE) from the bottom sediments of the Acaray Reservoir in the Alto Paraná region of Eastern Paraguay were investigated by the EDXRF technique. Most of them are refractory, that is, they maintain their primary relationships and are transferred almost directly into sediments and thus, they are considered as geoindicators. In this regard, IE are of utmost interest in sediments studies. The refractory trace elements analyzed were Y-Rb-Sr-Zr-Nb-Ba-La-Ce-Nd, and the minor elements Ti-Mn-Fe. The analyses were performed with an Am-241 source and an X-ray tube. Samples were taken from six different stations. Like the sediments of the Itaipu Dam, spidergram results show an enrichment of IE and contributions of sedimentary material to the bottom sediments of the Acaray Reservoir.

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The exposure to radiofrequency electromagnetic fields (RF EMF) in the living environment is due to variety of sources, predominantly for telecommunications – radio and TV stations and base stations for mobile communication emitting in the frequency range from 100 kHz to several GHz. In recent years research has shown that such systems have significantly increased RF EMF levels in urban areas compared to those measured in the 1980s, when the major sources in the environment were analogue radio and television stations. The aim of the report is to present the assessment of electromagnetic field exposure to the general public from telecommunication sources on the territory of the country. Separate data from measurement and exposure assessment of RF EMF levels around base stations for mobile communication and Radio and TV stations are considered. The data contain results of spot measurements of RF EMF levels emitted by separate base stations for mobile communication and radio and TV stations and spot measurements in areas with a high density of RF EMF sources – 105 regions in the country. It covers 1376 base stations and 280 radio and TV stations. The received results show that RF EMF levels are below the permissible levels according to the national legislation. Higher values, within the exposure limits, are found in areas with large number of sources or when the emitters are mounted on small height, but in such cases the values are less than 30% of those in national legislation. Compared to the European legislation the registered RF EMF levels are below 1 % of exposure limits. The measured values of the electric field strengths and power densities around the radio and television stations are within the exposure limits according to the national legislation. Values above exposure limits have been found in 1-2% of cases, but they were measured outside the urban areas where only incidental stay of the general public is possible. In comparison to the European legislation (Council Recommendation 1999/519/ЕС) measured values of the electric field strength and power density around radio and TV stations are well below the limit values.

1. The Council of the European Union. (Jul. 12, 1999). 1999/519/EC Council Recommendation of 12 July 1999 on the limitation of exposure of the general public to electromagnetic fields (0 Hz to 300 GHz)
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3. Basic standard on measurement and calculation procedures for human exposure to electric, magnetic and electromagnetic fields (0 Hz – 300 GHz), EN ISO 50413:2008, Jan. 1, 2008.
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4. Basic standard to demonstrate the compliance of fixed equipment for radio transmission (110 MHz – 40 GHz) intended for use in wireless telecommunication networks with the basic restrictions or the reference levels related to general public exposure to radio frequency electromagnetic fields, when put into service, EN ISO 50400:2006, Jun. 26, 2006.
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5. The European Parliament. (Apr. 2, 2009). 2008/2211(INI) Resolution of 2 April 2009 on health concerns associated with electromagnetic fields.
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6. M. Ivanova, Ts. Shalamanova, “Measurements of RF radiation around base stations for mobile communication in Bulgaria,” J. Environ. Prot. Ecol, vol. 6, no. 2, pp. 328 – 336, Jan. 2005.
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7. W. Joseph, L. Verloock, F. Goeminne, G. Vermeeren, L. Martens, “Assessment of general public exposure to LTE and RF sources present in an urban environment,” Bioelectromagnetics, vol. 31, no. 7, pp. 576 – 579, Oct. 2010.
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8. Министерство на здравеопазването. (14.03.1991). Наредба № 9 от 14.03.1991 г. за пределно допустими нива на електромагнитни полета в населени територии и определяне на хигиенно-защитни зони около излъчващи обекти. (Ministry of Health. (Mar. 14, 1991). Ordinance No. 9 from 14.03.1991 on the limit values of electromagnetic fields in populated areas and the determination of hygienic-protective zones around radiating objects.)
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The health policy connected with electromagnetic fields’ exposure of workers in Europe was developed on the basis of the ICNIRP Guidelines through the implementation of the Directive 2013/35/EC. The transposition of the EU Directive into the national legislation is a large process including the implementation of an ordinance, training of employers and workers, occupational health services, specialists performing measurements. An additional activity is the development of standard methods of risk assessment for practical implementation valid for concrete occupations and workplaces. Special attention should be paid to the workplaces with magnetic resonance imaging.

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4. Министерство на труда и социалната политика. (15.11.2016). Наредба № рд-07-5 от 15 ноември 2016 г. за минималните изисквания за осигуряване на здравето и безопасността на работещите при рискове, свързани с експозиция на електромагнитни полета. (Ministry of the Labor and Social Policy. (Nov. 15, 2016). Наредба Ordinance RD-07-5 on the minimal requirements for providing health and safety at work at risks by exposure to electromagnetic fields)
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5. Non-binding guide to good practice for implementing Directive 2013/35/EU: Electromagnetic fields, vol. 1, European Commission, Luxembourg, 2015.
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A unique 3D tomography apparatus was built and successfully tested in Research Centre Rez. The apparatus allows a three-dimensional view into the interior of low-dimension radioactive samples with a diameter up to several tens of millimeters giving a better resolution than one cubic millimeter and it is designed to detect domains with different levels of radioactivity. Structural inhomogeneities such as cavities, cracks or regions with different chemical composition can be detected by using this equipment. The SPECT scanner has been successfully tested on several samples composed of a 3mm radionuclide source located eccentrically within homogeneous steel bushings. To detect fine cracks inside small samples an ultrafine scan of the sample was carried out in the course of 24 hours with a 0.5 mm longitudinal and transverse step and 18° angular step. The exact location and orientation of a fine crack artificially formed inside a sample has been detected.

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The use of herbal supplements and medicines is increasing rapidly as most people consider them to be of natural origin and therefore safe. Many herbal medications are used to treat diseases but while they are often efficacious, their safety has not sufficiently been considered by physicians or users. One particular safety concern is the risk of interactions with drugs, which often leads to toxicity or loss of therapeutic efficacy. A significant number of patients combine herbal remedies with prescription medications and there is growing evidence for interactions of drugs with herbal remedies or single compound originating from plants. The aim of this paper is to evaluate the possible interactions between chronic patient therapy and herbal substances. The research is presented as a descriptive study which included patients of 30 to 80 years of age, who were randomly selected in Niš from September to December 2017 and agreed to be interviewed as well as completed the questionnaires. We surveyed 157 patients, 115 respondents (73.24%) reported use of dietary supplements. In total, 105 (66.87%) interactions with potential clinical significance were identified. The 5 most common natural products with a potential for interaction (garlic, valerian, ginkgo, and St John’s wort) accounted for 68% of the potential clinically significant interactions. The 4 most common classes of prescription medications with a potential for interaction (antithrombotic medications, sedatives, antidepressant agents, and antidiabetic agents) accounted for 94% of the potential clinically significant interactions. No patient was harmed seriously from any interaction. It is an imperative that pharmacists and doctors ask patients what they are using within their chronic illness treatment and estimate the possible use of a dietary supplement based on the data obtained.

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The aim of the present study was to consider bilirubin (BRB) and riboflavin (RFL) mutual interaction in methanol solution under continuous UV-A and UV-B irradiation regime. Continuous irradiations of samples were performed in a cylindrical photochemical reactor “Rayonet”, with 10 symmetrically placed lamps having the emission maximum at 300 nm (UV-B) and 350 nm (UV-A). The rate of BRB and RFL photodegradation along with simultaneous products formation, as a function of UV exposure time, was followed by combining UV-VIS absorption measurements with RP-HPLC analysis. The compounds were separated by gradient elution with mobile phase A (formic acid, 0.1% water solution) and B (formic acid, 0.1% methanol solution). According to the results obtained, BRB degradation in the absence of RFL was almost 22 times and 9 times slower in comparison to its degradation observed in BRB-RFL mixture under continuous UV-A and UV-B irradiation, respectively. Moreover, BRB degradation in BRB-RFL mixture under anaerobic conditions was almost 24 times and 16 times slower in comparison to the degradation in aerobic conditions under UV-A and UV-B light, respectively. The latter observation suggests that presence of ROS species contributes to UV-induced BRB degradation. These experiments provide the indirect proof of BRB acting as Type II sensitizer because of the fact that 1O2 produced by RFL mediates BRB irreversible degradation giving rise to dipyrrole methanol adducts as typical products obtained via Type II mechanism.

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Radioactivity is perceived as the most terrible danger by regular people. Radioactivity has always been studied in such aspect. Therefore, the occurrence of messages about the useful effects of a weak influence of radioactivity has caused counteraction and has generated the debate lasting till this moment. Thermodynamics is capable of bringing clarity to this problem. Else, in the 19th century, thermodynamics discovered two types of interactions of the system with the environment. In one case, the volume and entropy are constant in a system, and in the second one, the volume and temperature remain constant. The process in the second case is called an isothermal one and in the first case - a thermal one. Quantum thermodynamics was developed in the second half of the 20th century for electromagnetic radiation. It was shown that isothermal processes take place at weak influence on the system, and the thermal ones - at strong influences. Let us pay attention to the fact that the logarithmic scale for the absorbed energy is used for isothermal processes, and the linear scale is used for thermal processes. The logarithmic scale allows to uncover what is hidden in the zero point of thermal processes. In the previous reports of the author at RAD 2012, 2014, 2017 conferences, it was shown that quantum thermodynamics is valid for all three parts of radiation (α-, β- ,γ--radiation) and not only for γ-radiation. The application of the thermodynamic theory to hormesis effects allows us to provide a fresh insight on the essence of proceeding processes. For the experimenters who recorded a U-curve of a dose-effect dependence, it is useful to understand and remember that they study the identical answer of an organism which is a result of two fundamentally different processes: the left branch of the U-curve shows the end of the processes of a weak influence on an organism, and the right branch is the beginning of the effect of strong influences. Strong influences give a linear (or close to it) dose-effect dependence. They have been studied comprehensively and for a long time, and they are object of a hygienic standardization. Among the investigators studying strong influences, there is a different view on the threshold for a dangerous action: some consider dangerous even the smallest doses, and others reject any effects of doses below the threshold. Maybe they are excused by their ignorance of thermodynamics, especially if one is to consider that in thermodynamics there is no concept of harm. But if experimenters wish to deeply understand the essence of the processes they study, they should get acquainted with the general laws of quantum thermodynamics. Then, it would become clear to them why hormesis was found not only in radiobiology, but also in many other sciences. Hormesis is fixed by any experimenter working in a certain range of influences where the system changes the type of its answer to environmental influences (boundary of isothermal and thermal processes).

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The aim of this work is to study how different oscillatory behavior of centrosomes and their mass arrangement affect the kinetic energy of pairs of dyads of sister chromatids in the system of a mitotic spindle during metaphase. The analyses are done through a biomechanical oscillatory model of the mitotic spindle. Analytical expressions for the kinetic energy of the oscillating dyads of sister chromatids are given for the case when the biomechanical system of the mitotic spindle is conservative, linear, and when it oscillates under external single frequency oscillation. Numerical analyses with some approximation for mouse chromosomes are done. Our numerical experiment reveals that the kinetic energy of the oscillating dyads of sister chromatids has an oscillatory character and is affected by the chromosomes’ mass distribution and the frequency of centrosome excitation. The difference in energy distribution regarding different centrosome oscillatory frequencies in the same cell and the mass chromosome distribution may carry additional epigenetic information and could be important for the process of cell differentiation.

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The molecular conformations and electronic properties of a set of five N¹-(o/p-substituted phenyl)aminomethyl-1,2,4-triazole derivatives (PhAMT) were investigated by two semiempirical methods: AM1 and PM3. Characteristic bond lengths (N₁-C₂, C₂-H₆, C₂-N₃, N₃-N₄, N₄-C₅, C₅-H₇ and N₁ - C₅), angles (N₁-C₂-N₃, C₂-N₃-N₄, N₃-N₄-C₅, N₄-C₅-N₁ and C₅-N₁-C₂) and atomic charges (N₁, C₂, N₃, N₄, C₅, H₆ and H₇) for 1,2,4-triazole core were calculated and discussed in accordance with literature data for similar 1,2,4-triazole compounds. The E_HOMO and E_LUMO values, total energies, the heats of formation and dipole moments values were calculated, as well. The discussion was performed in accordance with the type and position of a substituent present in the aromatic core.

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In this study, the influence of additives used during the recycling process, to the crystallinity of LDPE was analyzed. The usage of LDPE recycled is growing, as well as other types of recycled plastics, due to its flexibility and other properties. The spectroscopic method of infrared vibration is used for microstructure analysis of the samples. The presence of low-intensity peaks to infrared spectrum at 1300-800 cm^-1 for all samples indicates the presence of additives. The additives used in the recycled polymers influence their degree of crystallinity that is closely linked with their physical and mechanical properties. Due to the different rates of crystallinity the samples show different intensities of peak at 726 cm^-1. XRD techniques are used to calculate the degree of crystallinity and to study the phase compound of recycled LDPE. Rutile’s and calcite’s peak were identified by diffractgrams analyses as the additives added in the recycled LDPE.

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