Intensity Of Gamma Radiation Research Articles

Comparison of two gamma-ray datasets measured with different methods and assessment of their performance to predict soil properties

ABSTRACT Terrain mobility is directly dependent on soil properties, i.e. stoniness, soil particle size and peat depth. Gamma-ray spectrometry has been widely used in soil mapping as gamma-rays can penetrate up to 50 cm of soil. The method has proven to be effective in gathering information on various soil properties, such as clay and silt content, organic carbon content, soil pH, and soil stoniness. The intensity of gamma radiation decreases with increasing soil moisture content, which is important when assessing the load-bearing capacity of forest terrain, which affects the quality and planning of mechanized wood harvesting. In this study, we compared two gamma-ray datasets that were acquired from the same plots but measured with different methods: airborne gamma-ray spectrometry and a handheld gamma-ray spectrometer. Regression analyses were used to examine whether the gamma-ray datasets have significant similarities. Linear discriminant analysis was then used to study the performance of the two gamma-ray datasets when predicting different soil properties (stoniness index classes (SIC), soil depth, and peat depth). Our correlation analysis produced R2 values of 0.18–0.29 and root mean square error (RMSE%) values of 0.48–0.55. Prediction of SIC was 67.1% accurate with ground gamma and 45.9% accurate with air gamma. For soil depth predictions, the accuracies were 64.7–70.0% for ground gamma and 61.7–63.5% for air gamma. Our findings showed that ground gamma-ray spectrometry is better at predicting soil properties than air gamma-ray spectrometry.

Influence of Nb2O5 additives on SiO2–Pb3O4–ZnO glasses: a physical, structural, elastic, optical, and radiation shielding properties

A series of zinc lead silicate glass having compositions: 60SiO2—35Pb3O4—(5-x) ZnO-xNb2O5 where ( 0≤x≥5 ) mol% were successfully fabricated, by applying the melt-quenching technique. The density of these glasses increased from 5.91, gcm−3 for ZSPNb-0 to 6.782, gcm−3 for ZSPNb-5. Using ultrasonic velocity ( VL ) and ( VT ) data from the ultrasonic technique, elastic moduli and microhardness were computed. Both ( VL ) and ( VT ) increased, going from 4935 to 5215 m s−1 and 2520 to 2845 m s−1, respectively. Because of these results, the glass’s elastic moduli increase, and its structure becomes more rigid. The optical description Eg, n, α o, ε r, χ(3), n2, M, T and further were researched. Totally, the optical considerations are persuaded by alter niobium contents in the present specimens. As the concentration of Nb2O5 in the glass increases, (LAC) is also increased, while (HVL), and (MFP) decreased. This means that ZSPNb glass with higher Nb2O5 content becomes more effective at attenuating or reducing the intensity of gamma radiation. Such enhanced radiation-shielding properties make ZSPNb glass a promising material for potential applications in radiation shielding.

Gamma-ray interaction studies of concrete with waste glass fillers.

In the present work, the efficacy of waste glass as fillers in concrete for gamma-ray shielding has been studied. Glass fillers of 0, 15, 30, 45, and 60% concentrations have been incorporated into the concrete mixture. The attenuation measurements were performed using gamma spectrometer with NaI(Tl) detector at 511, 662, 1173, and 1332keV gamma energies. Gamma-ray shielding parameters, such as the mass attenuation coefficient (μ/ρ), are determined for all filler concentrations. The mass attenuation coefficient of the prepared samples was found to be varied from 0.081 to 0.088, 0.071 to 0.088, 0.05 to 0.058, and 0.05 to 0.055 (cm2 per g) for 511, 662, 1173, and 1332keV gamma energies, respectively. It was observed that experimentally determined (μ/ρ) values were in very good agreement with theoretical values calculated from EDAX data. Furthermore, it was observed that (μ/ρ) showed an increasing trend with an increase in filler concentration, which is attributed to the increase in the shielding property of the material. Therefore, the glass-concrete composite can be accustomed to reduce the intensity of gamma radiation.

Research Results of Municipal Sewage Sludge Applied for Building Material Production

The study presents the experimental results on the use of ash obtained as a result of incineration of municipal sewage sludge from the water utility of Izhevsk, Udmurt Republic, for construction material production. Research methods are given and the results of strength tests of building material samples are given. The impact of the manufactured samples of construction materials on the ecology of the surrounding space and human health is assessed. To achieve the set objectives of the research laboratory experiment and determination of indicators of investigated values of sludge, ash and water extracts with the use of devices and measuring instruments are used. On the basis of the research laboratories of Kalashnikov Izhevsk State Technical University and MUE “IzhVodokanal” of the Udmurt Republic experimental studies on incineration of sewage sludge and the use of the resulting ash as a substituting or modifying component of the construction mixture in the manufacture of experimental samples of ceramics, cement-sand mortar and concrete were carried out. Methodology of manufacturing and algorithm of ceramic (fired) and cement-based (nonfired) testing specimens are presented. Measuring means for determination of gamma-radiation intensity indices of ash, cement and their influence on human health are used. The algorithm of experimental research, applied energy-efficient techniques used in the experiment and analysis of the obtained experimental results are presented. The analysis of experimental research results of ceramic and cement-based products, as well as the analysis of radiation safety, migration of heavy metals is presented. The energy-efficient methodology of sewage sludge utilization and further ways of applying ash as an environmental and resource-saving component used in manufacturing of experimental building materials are considered.

A Novel, Rapid Response Renewable Biopolymer Neutron and Gamma Radiation Solid-State Detector for Dosimetry and Nuclear Reactor Flux-Power Mapping

A novel solid-state neutron and gamma radiation monitor-dosimeter based on biopolymer polylactic acid (PLA) is presented. The resulting detector (PLAD) technology takes advantage of property changes of the renewable PLA resin when subject to ionizing nuclear radiation. A simple yet rapid and accurate (±10%) low-cost (<$0.01/detector) mass loss upon dissolution (MLD) technique was successfully developed; MLD is based on a simple mass balance for discerning neutron and/or gamma doses using small (40 mg, ~4 mm diameter) ultra-low-cost (<$0.01) resin beads via dissolution in acetone. The GammaCellTM Co-60 irradiator, and the PUR-1 12 kW fission nuclear research reactor were utilized, respectively. Irradiation absorbed doses ranged from 1 to 100 kGy. Acetone bath temperature was varied from ~40 °C to ~54 °C. Results revealed a strong dependence of MLD on acetone bath temperature between neutron and gamma photon dose components; this allowed for the unique ability of PLAD to potentially perform as both a neutron-cum-gamma or as a gamma or neutron radiation dosimeter and intensity level detector. A linear trend is found for combined neutron and gamma radiation doses from 0 to 40 kGy when dissolution is conducted above 50 °C. The important potential ability to distinguish neutron from gamma radiation fields was scoped and found to be feasible by determining MLD at 45 °C. The potential was studied for simultaneous use as an in-core neutron and gamma monitor of an operating 3 GWt light-water reactor (LWR). Scoping tests were conducted with the pre-irradiated (@ 20 °C) PLAD resin beads followed by heating to in-core LWR coolant (300 °C) conditions for ~30 s corresponding to the time to reach ~40 kGy total doses in a typical 3 GWt LWR. MLD results were unaffected, indicating the exciting and unique potential for in situ (low-cost, accurate and rapid) simultaneous mapping of neutron and gamma radiation fluxes, related dosimetry, and fission power level monitoring.

DETERMINING GAMMA SOURCE IN URANIUM MOLYBDENUM OF FUEL IN G.A SIWABESSY MULTI PURPOSE REACTOR

Nuclear fission reactions produce a lot of radionuclides that release energy, one of which is in the form of gamma radiation. Gamma radiation is produced by various types of radionuclides, and nuclear reactor fuel will produce different values of gamma intensity. Uranium Molybdenum (U7Mo-Al) is the type of nuclear fuel for future research reactors that possesses many advantages. For the application of molybdenum-based fuel, it is necessary to determine the resulting gamma radiation. The purpose is to determine the gamma radiation produced from molybdenum-based fuel with various densities. This study begins with the determination of the mass composition of the reactor component, calculations with ORIGEN2.1, and data output analysis. The U7Mo-Al density was varied, namely 2.96 gU/cm3, 3.85 gU/cm3, 4.44 gU/cm3, 5.43 gU/cm3, 6.91 gU/cm3, and 8.29 gU/cm3. The gamma radiation yield of U7Mo-Al is lower than that of uranium silicide (U3Si2) with the same density of 2.96 gU/cm3. The result will add to the justification for the superiority of U7Mo-Al compared to U3Si2/Al. For U7Mo-Al with densities of 3.85 gU/cm3, 4.44 gU/cm3, 5.43 gU/cm3, 6.91 gU/cm3, and 8.29 gU/cm3, the one that produced the lowest gamma radiation intensity is 3.85 gU/cm3 while the highest is 8.29 gU/cm3. This explains that the intensity of the gamma radiation produced is directly proportional to the fuel density. The low intensity of gamma radiation in molybdenum-based fuel can be used as a suggestion in shielding design to ensure the operational safety of reactors.

ISOTOPIC IDENTIFICATION OF PHOTOFISSED NUCLEAR MATERIALS IN STAINLESS STEEL CONTAINERS USING DELAYED GAMMA-RAYS

The results of isotope identification of nuclear materials (232Th, 235U, 238U, 239Pu) packed in hermetic stainless steel containers by their stimulated delayed gamma radiation are presented. The ratios of the values of the time dependences of the intensity of gamma radiation of the light and heavy product of their photofission were used for the analysis. Gamma radiation from photofission products 89Rb (1031.9; 1248.1 keV) and 138Cs (1009.8; 1436.8; 2218.0; 2639.6 keV) was used to differentiate nuclear materials. The photofission reaction the samples of nuclear materials was stimulated on an electron accelerator, an M-30 microtron, at maximum bremsstrahlung energy of 12.5 MeV. The possibility of carrying out isotopic identification of nuclear materials using the following sets of ratios of the values of the time dependences of the gamma-line intensity has been demonstrated: X(1031.9)/X(2639.6), X(1248.1)/X(1009.8), X(1248.1)/X(1436.8), X(1248.1)/X(2218.0), X(1248.1)/X(2639.6).

Effects of Radiation on Cross-Linking Reaction, Microstructure, and Microbiological Properties of Whey Protein-Based Tissue Adhesive Development.

Whey proteins are mainly a group of small globular proteins. Their structures can be modified by physical, chemical, and other means to improve their functionality. The objectives of this study are to investigate the effect of radiation on protein–protein interaction, microstructure, and microbiological properties of whey protein–water solutions for a novel biomaterial tissue adhesive. Whey protein isolate solutions (10%, 27%, 30%, 33%, and 36% protein) were treated by different intensities (10–35 kGy) of gamma radiation. The protein solutions were analyzed for viscosity, turbidity, soluble nitrogen, total plate count, and yeast and mold counts. The interactions between whey proteins were also analyzed by sodium dodecyl sulfate polyacrylamide gel electrophoresis and scanning electron microscopy. The viscosity of protein solution (27%, w/w) was increased by the treatment of gamma radiation and by the storage at 23 °C. The 35 kGy intensity irradiated soluble nitrogen (10%, w/w) was reduced to about half of the sample treated by 0 kGy gamma radiation. The effects of gamma radiation and storage time can significantly increase the viscosity of whey protein solutions (p < 0.05). Radiation treatment had significant impact on soluble nitrogen of whey protein solutions (p < 0.05). SDS-PAGE results show that the extent of oligomerization of whey protein isolate solutions are increased by the enhancement in gamma radiation intensity. Photographs of SEM also indicate that protein–protein interactions are induced by gamma radiation in the model system. Consistent with above results, the bonding strength increases by the addition of extent of gamma radiation and the concentration of glutaraldehyde. Our results revealed that the combination of gamma-irradiated whey protein isolate solutions and glutaraldehyde can be used as a novel biomaterial tissue adhesive.

Scattering of gamma radiation by air in the ambient environment using gamma ray spectrometry

The intensity of gamma radiation reduces as it traverses through matter. The gamma radiation from earth’s surface is attenuated by non-radioactive burden between the ground and the detector. The relative intensity of unscattered to scattered gamma radiation by air in ambient atmosphere is measured using in-situ gamma spectrometric method. The air thickness up to 300 cm is used for studying attenuation of terrestrial gamma radiation. No significant attenuation is measured up to 100 cm thickness of air between the detector and the ground. The attenuation by air is found to increase with increasing thickness of air. Also, the attenuation of terrestrial gamma radionuclides (40K) is found higher than 238U and 232Th as 40K has lower energy compared to them.

Застосування методу досліджень кутового розподілу інтенсивності гамма-випромінювання

The paper presents the results of the application and verification results of the effectiveness of the method of studying the angular distribution of gamma radiation intensity using a dosimeter MKS-07 “Poshuk” with a remote detector in the collimator (DC-R). The purpose of this work is to verify the effectiveness of the method using the DС-R device on pre-known sources and to obtain an array of data in one area from different points. Before the start of the study, an analysis of available data on the radiation situation was performed. This allowed determining a sufficient number of measurements of angular distributions to verify the effectiveness of the method and the location of measurement points. As a result of the analysis of the initial data from the radiation state, it was decided to investigate the area of the Shelter object from the west to the east. Known source in the blockages of the central hall of of the Chornobyl Nuclear Power Plant Unit 4 of the Shelter object are located in this zone. The obtained measurements results of the quantitative characteristics of the angular distribution of gamma radiation intensity are presented graphically. As a result of the study of the angular distribution of gamma radiation intensity using the DC-R device, the high efficiency of source recognition was proved even in conditions of high gamma fields. After processing the obtained results and their analysis, the following conclusions were formulated: 1. The effectiveness of this method in the study of the angular distribution of gamma radiation intensity has been confirmed. This is seen when comparing points K1 and K3. 2. A hitherto unrecorded source of ionizing radiation was found, which forms a radiation state at the study site, which corresponds to point K2. 3. It is confirmed that in high fields of ionizing radiation this method is inappropriate in connection with the receipt of personnel of high dose loads during research. 4. Background values were recorded in the directions with no radiation sources, so they are not reflected on the cartograms. This is due to the fixation of gamma rays by the detector passing through the lead walls of the collimator. This proves the effectiveness of shielding the detector from powerful sources and allows it to be used in high fields.

Study of gamma radiation shielding efficiency by 0.5TeO2-(0.5-x)Bi2O3-xWO3 glasses

This article is devoted to the study of determination of gamma radiation shielding efficiency by new radiation-resistant glasses of the 0.5TeO2-(0.5-x)Bi2O3-xWO3 type. As a method of obtaining glasses, the method of solid-phase synthesis combined with thermal annealing and subsequent hardening was used. The amorphous nature of the synthesized samples was confirmed by X-ray phase analysis. Determination of the shielding efficiency, as well as the effect of Bi2O3 and WO3 content in the glass composition on the attenuation efficiency was carried out by evaluation of gamma radiation intensities from the 137Cs source, with a gamma ray energy of 661 keV. The evaluation was performed on parameters such as radiation protection efficiency, linear and mass attenuation coefficients, half-value layer and mean free path. During the studies, it was found that glasses of the following composition 0.5TeO2-0.1Bi2O3-0.4WO3 are most effective, which are 1.3-2 times higher than those of the composition 0.5TeO2-0.4Bi2O3-0.1WO3.

Intensity variation of gamma radiation on ground level interface in São Jose Dos Campos, SP, Brazil

In the period June 22 to September 24, 2012 São José dos Campos region experienced dry climate with low relative humidity. The net rain intensity measured in this period was 60 mm/h and the relative humidity range between 30% to 40% on most days. The intensity of gamma radiation from 0.03 to 10.0 MeV, in the measurement period presents a daily fluctuation well clearly, and some small increases when there is rainfall. These measures were realized at ITA's campus with a scintillator of NaI(Tl), photomultiplier and associated electronics laptop to a Dell 630 PC. A data acquisition interface purchased from (Aware Eletronics, USA) provides a file with measurements versus time, in the range from minute to minute recorded in txt. It was observed that the variation of gamma radiation in the interface soil/air at the region is originating from the local radon gas dynamics and of the presence of wind shear near the ground level.

Synthesis, phase transformations, optical properties and efficiency of gamma radiation shielding by Bi2O3-TeO2-WO3 ceramics

Abstract In the modern world, great attention is paid to methods of protection against the negative effects of ionizing radiation. One of the promising solutions to this problem is the creation of radiation-resistant ceramics or glasses based on Bi2O3–WO3–TeO2, which have a high radiation resistance and absorbency of various types of ionizing radiation, including gamma, X-ray, and electron radiation. This paper presents the results of the study of the synthesis of Bi2O3-TeO2-WO ceramics, phase transformations and changes in optical and structural characteristics as a result of thermal annealing. The synthesis of ceramics was carried out using the methods of mechanochemical synthesis and thermal sintering in the range from 300 to 800 °C. Using the method of X-ray phase analysis, it was found that as a result of an increase in the sintering temperature, the following phase transformations occur: WO3/Bi2Te4O11→ WO3/Bi2Te2W3O16 → Bi2Te2W3O16→ Amorphous glass similar state. The efficiency of gamma radiation shielding with energy of 130 keV by Bi2O3-TeO2-WO3 ceramics is shown. It was found that for ceramics with a thickness of 0.5 mm, the intensity of gamma radiation can be reduced to 30–70%, depending on the phase composition of the ceramics.

Дослідження радіаційного стану промислового майданчика об’єкта «Укриття»

The territory of the industrial site of the New Safe Confinement of the Shelter object (NSC SO) was investigated after the installation of the arch structure in the design position over the destroyed Unit 4 of the Chornobyl NPP. Radiation studies of the industrial site were carried out by the specialists of the Institute for Safety Problems of Nuclear Power Plants of the National Academy of Sciences of Ukraine in 2020–2021. The subject of research was the distribution of the dose rate values and the characteristic of the angular distribution of the intensity of gamma radiation at the NSC SO industrial site. Comprehensive studies of radiation conditions include both dose rate measurements and the angular distribution of gamma radiation intensity. The study of the angular distribution of the intensity of gamma radiation and the determination of the sources forming the dose rate in the research sites was carried out using own developments — the ShD-1 device [7] and the MKS-07 “Poshuk” radiometer-dosimeter with an external collimated detector. This equipment was previously successfully tested and was repeatedly used at the stage of pre-design studies and during the implementation of projects at the site of the Chornobyl NPP. Based on the results of modern research, a comparative analysis was carried out with the results of research before the construction of the arch structure (2004) and during the construction of the NSC (2010). At all points of the study, a decrease in the dose rate from 5 to 15 times was recorded. The decrease is due to the removal during the construction period of all local sources of ionizing radiation from the territory of the industrial site, as well as to the construction of new structures, which are protective barriers for work performed at the NSC SO site. Insignificant changes in the angular distribution of gamma radiation were found, which are associated with the construction of new structures in the middle of the SO and on the industrial site. The research results can be useful for the selection of sites for the construction of new facilities for radioactive waste management in the process of transformation of the SO into an ecologically safe system.

An insight into the quality of internal built environment in Vladivostok. Part 1: Studying background radiation in residential premises

Introduction. The article addresses background gamma radiation in residential premises of apartment buildings in Vladivostok. This study is based on earlier research undertakings focused on the sick building syndrome (SBS), which proves its high relevance. The research is focused on the intensity of background gamma radiation in the residential premises of apartment buildings in Vladivostok. New data obtained in the course of the field experiments, the scale of their analysis, the coverage of substantive issues concerning radiation intensity and its monitoring in residential buildings guarantee the novelty of this research project. These findings also have a practical value that deals with environmental safety. Materials and methods. Onsite examinations were conducted in the form of background gamma radiation measurements taken in versatile apartment buildings, built at different times and made of different materials. Results. This section contains analytical information about the lack of influence of the location of apartment buildings on background radiation inside the apartments examined within the framework of this research project. Measurement results represent a range of values depending on construction materials used. Principal regularities, derived from the measurement results, are based on the time of operation of residential buildings, which is of practical importance. Conclusions. Patterns of influence of building parameters on background radiation inside apartments allow to assess the condition of residential buildings. Background radiation information can be entered into BIM databases and used to formulate the approach to the design of buildings and urban infrastructure so that they were focused on their residents and users. Background radiation research findings, entered into the database and contributed to design algorithms which are customized to the needs of urban residents, will enable designers to project the overall quality of the living environment encompassing the built environment analyzed in this article and other nearby buildings and structures located in Vladivostok.

Selection of low-resistant reservoir rocks in geological cross-section of Helvetian deposits at Letnianske field

The main difficulties that arise in the selection of reservoirs in the geological section of the Helvetian deposits at Bilche-Volytska zone are due to the fact that they are characterized by low values of electrical resistivity. Under such conditions, very often, when interpreting the data of electrical and electromagnetic logging, gas-saturated reservoir rocks are characterized by increasing the penetration of filtrate into the formation and are mistakenly referred to as water-saturated rocks. Based on the analysis results of laboratory studies of the core material and data from geophysical well logging (GWL) in the geological section of Helvetian deposits at Letnianske field, two groups of reservoir rocks were identified. The first group of rocks belongs to the low-resistance, and the second - to the typical quartz sandstones. The formation of groups is due to the difference in electrical, radioactive and neutron attributes of reservoir rocks. According to the results of research it is established that the low resistance of Helvetian reservoir layers is caused by the electronic conductivity of pyrite and chlorite grains, which are part of the cementing material in rocks. Low indications of gamma radiation intensity radiation capture of thermal neutrons for low-resistance rocks are associated with high content of bound water in pyrite and chlorite minerals, and increased radioactivity is due to the content of zircon grains and high adsorption attributes of chlorite and clay masses. In order to increase the reliability of electric and electromagnetic logging data interpretation for the separation of reservoir rocks into typical and low-resistance quartz sandstones, it is proposed to use the comparison of the lateral logging curve (LL) with the normalized neutron gamma-ray logging (NGL) curve. The efficiency of proposed method for dividing reservoir rocks into groups was tested on actual material.

Estimation of the Duration of Cooling Time of the SFA of the VVER-1200 Reactor Depending on the Type of Transport Container

As the burnup increases, the requirements of nuclear and radiation safety for spent nuclear fuel (SNF) at the subsequent stages of operation grow. The analysis and estimation of the required cooling time of the spent fuel assemblies (SFAs) of the VVER-1200 reactor for transportation in various types of transport containers (TUK-13 and TUK-141O) are performed. The estimates are based on the analysis of residual energy release and gamma-radiation intensity of SNF depending on the cooling time for different burnups. The data on the absorbed dose rate of neutron and gamma radiation from SNF after 4 and 5 yr of cooling are presented.

ПРОЕКТУВАННЯ КОМПОЗИТНИХ МАТЕРІАЛІВ НА ОСНОВІ ДРІБНОДИСПЕРСНОЇ ЗАЛІЗОВМІСНОЇ СУБСТАНЦІЇ ДЛЯ ЕКРАНУВАННЯ ІОНІЗУЮЧИХ ВИПРОМІНЮВАНЬ

На основі аналізу механізмів розсіювання іонізуючих електромагнітних випромінювань та залежності ослаблення випромінювання від порядкового номера елемента та його густини зроблено висновок про можливість їх екранування матеріалами з вмістом заліза. Запропоновано засади проектування композиційного металополімерного матеріалу для зниження інтенсивності рентгенівського та гама-випромінювань. Показано, що зміна поглинання іонізуючого випромінювання зі зміною довжини хвилі випромінювання відбувається немонотонно. Тому для проектування матеріалу необхідно з’ясувати переважні довжини хвиль (частоти) випромінювання, яке потребує екранування. Встановлено, що для ефективного екранування випромінювання існує критична концентрація металевих частинок у полімерній матриці. Це відбувається на порозі протікання електричного струму за вмісту екрануючої субстанції 11−12 % (за вагою). Це добре узгоджується зі співвідношеннями електродинаміки суцільних середовищ. При проектуванні матеріалу з використанням залізорудного концентрату слід враховувати його різні властивості у залежності від виробника. Проектуванню захисного матеріалу повинні передувати лабораторні дослідження з визначення переважної фракції залізорудних частинок за розмірами та вмісту заліза і його сполук у вихідній сировині.

Study of Crystal Structure Profile Fitting of CuO for different Intensities of Gamma Radiation using Rietveld Refinement Method

Study of Crystal Structure Profile Fitting of CuO for different Intensities of Gamma Radiation using Rietveld Refinement Method

Model of absorbed gamma radiation in the interaction with rock formation

The article discusses issues of improving the accuracy of operational quality control of iron ore in mountain ranges. There was proposed the use of the absorbed gamma radiation indicator as an improvement of the nuclear physics method for determining the iron content in ore mass are proposed. There were obtained the relationships of the sensitivity of the absorbed gamma radiation intensity on the distance between the detector and the irradiated surface, as well as on the distance between the source and the detector of gamma radiation.