H. Oğul

Advanced radiation applications have been widely used and extended to many fields. As a result of this fact, choosing an appropriate shielding material based on the radiation application has become vital. In this regard, the integration of elements into polymer composites has been investigated and contributed to the quantity and quality of radiation shielding materials. This study reports photon attenuation parameters and electromagnetic shielding effectiveness of a novel polymer composite prepared with a matrix reinforced with three different proportions (5, 10, and 15 wt%) of niobium content. Addition of Nb dopant improves both photon attenuation and electromagnetic shielding effectiveness for the investigated composites. Therefore, Nb(15%) polymer composite with highest concentration has been found to be the best absorber for ionizing and non-ionizing radiations. Consequently, the performed analyzes provide evidences that the prepared Nb-reinforced polymer composite could be effectively used as photon radiation attenuator and electromagnetic shielding material.

The photon shielding performances of five different borosilicate-based glasses were investigated in this study using the FLUKA, GEANT4 and MATLAB codes, as well as the XCOM program, at photon energies ranging from 0.03 to 15 MeV. In this context, dependencies of the photon attenuation features with the variation of the photon energy and the chemical compositions have been carefully evaluated with Monte Carlo simulation and theoretical evaluation tools. The mass attenuation coefficient values and effective atomic numbers obtained for BaO-doped G5 glasses are found to be higher than those derived for G1-G4 samples. In other words, the Zeff results showed that high Z-elements such as Ba in a suitable amount should be inserted into the glass composition in order to improve the photon attenuation capability of the borosilicate glasses. The HVLs, TVLs, and MFPs of the studied borosilicate glasses are determined further, and the gamma shielding characteristics of the analyzed samples are found to be associated to the density of the glass, implying that high-density glass can be used for high-level attenuation performance. The exposure buildup factor (EBF) values have been further estimated via the G-P fitting approach. The results of such investigations, according to the work given, may be valuable in designing and fabricating new borosilicate-based glasses, which can then shield against potential radiation damage to environmental health.

Researches on advanced composites to protect environment health towards radioactive pollution have drawn attention with the rising use of radioactive elements. From this point, polymer micro composites are quite encouraging in terms of multifunctional properties in mechanical, electrical, thermal, as well as nuclear shielding. The present study has explored the efficacy of micro lead (Pb) loaded polymer composites for radio protective applications such as a fabrication of protective enclosures. High energetic photon shielding experiments have been applied through gamma spectrometer equipped with HPGe detector and various radioactive point sources namely 137Cs, 22Na, 152Eu, 133Ba, 241Am and 57,60Co which are widely used in several medical and industrial applications. The results demonstrated that mass attenuation coefficients of the composites at different photon energies are proportional to the filler loading. The validation of FLUKA and GEANT4 Monte Carlo software has been performed in the simulation of transmission experiments as well as WinXCOM software. The tests of the Pb (20%) micro composite for the nuclear radiation shielding reveal that it has high attenuation coefficients for photon radiation.

Different types of photon shielding parameters such as total mass attenuation coefficient (μ/ρ), linear attenuation coefficients (μ), half value layers (HVL), mean free paths (MFP), effective atomic numbers (ZEff), energy absorption build-up factors (EABF), exposure build-up factors (EBF) and kerma relative to air were investigated for the fabricated Cu–Ag based alloys. The considered parameters were measured through gamma spectrometer equipped with HPGe detector in order to obtain the experimental attenuation coefficients and other related parameters at various photon energy in the energy range 59.5–1332.5 keV. The measured μ/ρ values were confirmed with WinXCOM database results. FLUKA and GEANT4 simulation codes were used to examine the compatibility of the experimental and WinXCOM database results with these simulation codes. The exposure buildup factors of the alloy samples were estimated with help of Geometric Progression fitting formula over photon energy 0.015–15 MeV up to 40 mfp penetration depth. The results revealed that the exhibited effectiveness of Cu0.2Ag0.8 alloys against high energetic photon radiations had a good performance than that of alternative absorbers such conventional concretes, glasses and some alloys. The results of the present survey can be quite useful for possible applications of such materials, especially in nuclear laboratory and reactor core design for preference of effective photon shielding materials.

This work presents a detailed radiation shielding study for polymer composites filled with Boron and Molybdenum additives. The chosen novel polymer composites were produced at different percentages of the additive materials to provide a proper evaluation of their neutron and gamma-ray attenuation abilities. The effect of additive particle size on the shielding characteristics was further investigated. On the gamma-ray side, simulation, theoretical and experimental evaluations were performed in a wide range of photon energies varying from 59.5 keV to 1332.5 keV with help of MC simulations (GEANT4 and FLUKA), WinXCOM code, a High Purity Germanium Detector, respectively. A remarkable consistency was reported between them. On the neutron shielding side, the prepared samples produced with nano and micron particle size additives were additionally examined by providing fast neutron removal cross-section (ΣR) and the simulated neutron transmissions through the prepared samples. The samples filled with nano sized particles show better shielding capability than the one filled with micron sized particles. In other words, a new polymer shielding material that does not contain toxic content is introduced: the sample codded N–B0Mo50 exhibits superior radiation attenuation.

The usage of composites as the shielding materials are highly recommended since they could be used in order to attenuate the undesired radiation with unique properties and advantages in the areas where the radiation is prevalent. In this context, not only are their radiation shielding properties important but also their flexibility, durability and low cost. Due to the mentioned superior characteristics, the polyester based composites are among the most preferred materials. With the aim of creating unique and novel radiation shielding materials, this study investigates gamma and neutron shielding capabilities of the polyester composites reinforced with Boron and Tin nanopowders at different proportions (0–50%, 10–40%, 20–30%, 30-20% and 40-10%, 50-0%). The gamma shielding abilities of the prepared polyester composite materials were evaluated using an HPGe detector system, WinXCOM computer program and different simulation tools (FLUKA and GEANT4) at the energies varying from 59.5 to 1332.5 keV. The experimental, theoretical and simulation results showed remarkable agreement between each other, and the addition of Sn enhances the gamma attenuation performance of the chosen polyester composite materials. In addition to gamma analysis results, neutron shielding properties of the proposed composites are further determined. On this purpose, the transmitted neutron numbers through the samples (as functions of neutron energy and the sample thickness) and effective neutron removal cross sections were evaluated. The neutron shielding performance of the samples showed that the prepared composites could be alternative materials to the existing neutron shields in the literature.

Recently, polymer materials are preferable in radiation shielding applications due to their unique properties: flexibility, durability and low-cost production. These properties enthuse the researchers and, lately, elements or compounds have been mixed into polymer matrixes to create novel radiation shielding materials having the distinctive advantages of polymers. In this context, polyester resins and 3D printing materials, such as Acrylonitrile Butadiene Styrene (ABS) and Polylactic Acid (PLA), have been used to block/attenuate different radiation types. In this work, Tantalum Carbide was chosen as additive material, while polyester, PLA and ABS were considered as the base polymer samples. GEANT4 and FLUKA codes were utilized in the evaluation of transmitted radiation through the materials. Significant advantages of 3D technology and remarkable enhancements in neutron and gamma shielding were reported.

The shielding efficiencies of gamma and neutron radiations for ternary composites containing polyester resin, polyacrylonitrile and gadolinium (III) sulfate at different ratios were investigated in the present study. In order to investigate the gamma radiation shielding capacity of the produced ternary composites, linear and mass attenuation coefficients, half value layer, effective atomic number and radiation protection efficiency parameters were determined experimentally, theoretically and using the GEANT4 simulation code. The gamma shielding capabilities of the composites were studied in the photon energy range of 59.5-1332.5 keV. In order to investigate the neutron shielding abilities of composites, inelastic, elastic, capture and transport numbers, total macroscopic cross section and mean free path parameters were determined with the help of GEANT4 simulation code. In addition, the number of transmitted neutrons at different sample thicknesses and neutron energies were also determined. It was observed that gamma radiation shielding properties were improved due to the increasing amount of gadolinium (III) sulfate and neutron shielding properties were improved due to the increasing amount of polyacrylonitrile. While the composite coded P0Gd50 exhibits a better gamma radiation shielding ability than the others, the neutron shielding of the sample coded P50Gd0 is also more favorable than the others.

The presented work investigates the photon, charged particle and neutron radiation shielding performances of polyester-based composites filled with barite and/or tungsten boride by using experimental, theoretical, and Monte Carlo simulation techniques. The amount of barite/tungsten boride varying from 0 wt% to 50 wt% in the material and polyester resin were exploited as filler and base materials, respectively. Experimental evaluation of BaWB composites has been performed with help of an HPGe detector based gamma spectrometer as well as 22Na, 133Ba, 137Cs and 60Co radioactive point sources with energies in the range of 276.4–1332.5 keV. The experimental data were compared to those theoretically calculated in WinXCOM as well as Monte Carlo (MC) simulations, i.e., MCNP6, GEANT4 and FLUKA codes. The obtained mass attenuation coefficients for the produced composites were in good agreement with the results of MC simulations and WinXCOM software. Comparing to the other polymer composite samples, the sample with the maximum tungsten boride weight percentage has the best radiation shielding property because of having the highest attenuation coefficients and lowest absorption thicknesses.

Ferrites are ceramic oxide materials consisting of mainly iron oxide and they have become massively important materials commercially and technologically, having a multitude of uses and applications. The protection against neutron-gamma mixed radiation is crucial in several nuclear applications. From this standpoint, mass attenuation coefficient, radiation protection efficiency and transmission factor of some ferrites namely barium, strontium, manganese, copper and cadmium ferrite has been computed using Geant4 and FLUKA simulations. Based on the simulated mass attenuation coefficient, other significant parameters such as linear attenuation coefficient, effective atomic and electron number, conductivity, half value layer, and mean free path were calculated for the selected ferrite materials. The validation of Monte Carlo geometry has been provided by comparing the mass attenuation coefficient results with standard WinXCom data. Gamma ray exposure buildup factors were computed using geometric progression fitting formula for the chosen ferrites in the energy range 0.015-15 MeV at penetration depths up to 40 mfp. The findings of the present work reveal that among the studied ferrites, barium ferrite and copper ferrite possess superior gamma ray and fast neutron attenuation capability, respectively. The present work provides a comprehensive investigation of the selected iron oxides in the field of neutron and gamma ray.

Polyester is strong and durable material and tends to retain its shape, thus polyester composites have become highly preferred option in high-tech applications. This motivates the usage of polyester composites in the production of radiation shielding materials as well. In present study, gamma ray shielding properties of polyester composite reinforced with different proportions of Cadmium Telluride (5%, 10%, 15% and 20%) have been investigated theoretically and experimentally. The experiments were performed with the use of HPGe detector in a wide range of photon energies varying from 59.5 to 1408.0 keV while XCOM computer program was computed in the same photon energy range to obtain theoretical results and to verify the experimental outcomes. Remarkable radiation protection efficiency was obtained with additive material of Cadmium Telluride, and the radiation protection efficiency was found to be increased with the increase of additive material amount. Negligible discrepancies between experimental and theoretical results were also observed.

In this study, CdS doped polyester composites were produced at different weight ratios, and the impact of dopant amount on gamma and neutron shielding characteristics of a new composite material were further evaluated: the composite matrix was doped at 5%, 10%, 15% and 20% CdS weight ratios of the prepared composite. Then, the produced polyester materials have been characterized using a scanning electron microscope (SEM) and X-ray diffraction (XRD) patterns. Following the structure characterization, the prepared composites were tested using one gamma spectrometer system based HPGe detector with help of 22Na, 54Mn, 57Co, 60Co, 133Ba, 137Cs, 152Eu and 241Am radioactive point-isotropic sources in order to perform the evaluation in a wide energy range of gamma. The obtained results were compared to the results of Geant4 and WinXCOM simulation codes. On the last step of the presented work, the neutron removal cross sections of produced polyester composites were calculated using partial density of elements and their cross sections, and then, neutron shielding characteristics of the prepared samples were determined with help of Geant4 simulation toolkit. Both tested and simulated results of gamma shielding evaluation showed good agreement, and, for all considered photon energies, mass attenuation coefficient (μ/ρ) values of CdS (20%) were always found to be greater than the μ/ρ values of other samples (5%, 10%, 15%). The results for neutron shielding showed that neutron transmission was decreasing with the increase of CdS in the material. In short, having higher μ/ρ values and lower neutron transmission shows that increasing the amount of CdS in the sample causes the higher radiation shielding property for both gamma and neutron.

Abstract 3D printer technology has recently become easily reachable technology and are used to create simple or complex structures with high-quality. Its superior advantages could also be useful on the production of effective radiation shielding materials. On this purpose, the presented work studies the gamma and neutron shielding effectiveness of Acrylonitrile Butadiene Styrene (ABS) sample, a 3D printing material, reinforced with Bi and TiO 2 nanopowders at various gamma and neutron energies. The gamma shielding properties were evaluated using experimental (High Purity Germanium detector system), theoretical (WinXCOM computer program) and simulation techniques (GEANT4 and FLUKA) in a wide gamma energy region ranging from 59.5 to 1332.5 keV. The investigation on neutron attenuation capabilities of the printed composites were performed with help of simulation and theoretical approaches for various sample thickness and neutron energies. The half value layer of ABS-Bi10 sample is found to be as 4.9565 cm, which is much smaller than some commercial polymers: polyvinylidenechloride, polyamide, polyacrylonitrile, polyphenylenesulfide, and unsaturated polyester. With the usage of 3D printing technology, significant enhancements in neutron and gamma shielding were reported.

Radiation is the main safety issue for almost all nuclear applications, which must be controlled to protect living organisms and the surrounding materials. In this context, radiation shielding materials have been investigated and used in nuclear technologies. The choice of materials depends on the radiation usage area, type, and energy. Polymer materials are preferred in radiation shielding applications due to their superior characteristics such as chemical inertness, resistivity, low weight, flexibility, strength, and low cost. In the presented work, ABS polymer material, which is possibly the most commonly used material in 3D printers, is mixed with Gd2O3 and Er2O3 nanoparticles. ABS filaments containing these rare-earth elements are then produced using a filament extruder. These produced filaments are used in a 3D printer to create shielding samples. Following the production of shielding samples, SEM, EDS, and gamma-ray shielding analyses (including experiments, WinXCOM, GEANT4, and FLUKA) are performed. The results show that 3D printing technology offers significant enhancements in creating homogeneous and well-structured materials that can be effectively used in gamma-ray shielding applications.

In the field of dentistry, the utilization of dental X-rays plays a pivotal role in ensuring accurate diagnoses for various dental conditions. A crucial aspect of this practice involves understanding how these X-ray emissions interact with dental braces. In the presented study, the details of how X-rays and gamma rays interact with different materials used in dental braces, namely stainless steel, nitinol, elgiloy, and beta-titanium alloys, were examined. This investigation was carried out through a combination of advanced simulation codes such as FLUKA and GEANT4, alongside theoretical calculations using the WinXCOM approach. A comprehensive analysis was conducted at fourteen distinct energy levels, ranging from 20 to 150 keV with 10 keV increments. The primary focus of this study revolves around quantifying the shielding characteristics of gamma and X rays as they traverse through these dental brace materials. To achieve this, some gamma/X-ray shielding parameters, buildup-factors, and kerma relative to air were meticulously simulated and calculated. Additionally, the energy deposits within these materials and the subsequent generation of secondary radiations are thoroughly explored. Significantly, these results highlight that elgiloy alloy demonstrates the highest attenuation of X-ray and gamma ray intensities compared to the other considered materials. This comprehensive study thus offers valuable insights into the behavior of dental braces when subjected to ionizing radiation, with potential implications for patient safety and diagnostic accuracy in dental radiology.

This study focuses on the comparative analysis of ABS polymer samples produced using two distinct manufacturing techniques: 3D printing and the sol-gel methods. In the first approach, ABS polymer was augmented with rare earth oxides, Er2O3 and Gd2O3, in nano powder form and fabricated into test specimens using 3D printing technology. In the second approach, identical samples were prepared via the sol-gel technique involving mold-based fabrication. Elemental content analysis revealed no significant differences between the samples produced by the two methods. The study proceeds to evaluate the gamma-ray shielding, neutron shielding, temperature resistance, and SEM/EDS pictures of ABS samples generated through both techniques. 3D printing method exhibited more favorable results in terms of structure morphology and thermal stability while there is no significant difference for radiation shielding. The results provide insights into the performance and suitability of each production method for radiation shielding applications. This research not only contributes to enhancing radiation shielding technology but also informs the selection of the most appropriate fabrication method for specific applications in nuclear technologies and diagnostic energy range in medical purposes.

The research aims to exploring the gamma-ray shielding capacities of polyacrylonitrile/chrome-filled polymer composites through a combination of experimental, theoretical and simulation methods. Additionally, employing MCNPv6 and GEANT4 simulation tools, the study evaluates the materials' performance against neutron radiation. The materials were subjected to various gamma-ray energy levels, and their shielding efficacies are analytically quantified using parameters such as Radiation Protection Efficiency (RPE), Mass Attenuation Coefficient (MAC), Linear Attenuation Coefficient (LAC), and Half-Value Layer (HVL). At various neutron energies and sample thicknesses, the numbers of transmitted neutrons were evaluated. Notably, composite P0Cr50 (not contain polyacrylonitrile and containing 50% chromium) emerges prominently, demonstrating superior radiation shielding characteristics against both gamma and neutron radiations. This attitude is attributed to its optimal chrome dispersion and density, positioning it as a promising candidate for radiation shielding applications in industrial and nuclear domains.

In this study, we employed 3D printing technology to fabricate poly lactic acid (PLA) polymer samples infused with gadolinium oxide nanoparticles at additive rates of 10% and 20%. The objective was to explore their potential as radiation shielding aprons within the medical X-ray and thermal neutron energy spectrum. To facilitate comparisons, a PLA polymer sample with no additive was also produced. The homogeneity and well-defined structures of the PLA samples were observed using SEM and EDS analyses. Additionally, the excellent thermal stability of the proposed test samples was reported. In terms of gamma-ray shielding, there is a remarkable consistency between experiment, theory and simulation outcomes with a maximum discrepancy of approximately 5%. P-PLA-Gd20 sample exhibits attenuation capabilities against X-rays to a level that could serve as an alternative to lead. Additionally, the thermal and fast neutron attenuation effectiveness of the prepared samples were determined. A shielding effectiveness of 100% against thermal neutrons was achieved using a 10 mm sample thickness and the P-PLA-Gd20 sample. The findings consistently highlight the efficacy of the proposed polymer sample with a 20% gadolinium oxide nanoparticle additive, positioning it as a viable and promising alternative to traditional lead aprons.

The natural gas combined cycle power plant is one of the best options for generating electricity due to its use of low carbon fuels, high efficiency, and operational flexibility. These plants consist of a combination of Brayton and Rankine cycles, and investigation of these cycles is performed in this paper. Here the parameters of pressure and temperature used in the calculations are taken from a combined cycle power plant. The net power output of the system at 25 °C ambient temperature and 101.325 kPa pressure was calculated as 45 and 12 MW for Brayton and Rankine cycles, respectively. In addition, Brayton, Rankine, and combined cycle efficiencies were calculated as 37.5%, 27%, and 47.5%, while the exergy efficiencies were determined as 36%, 44%, and 46%, respectively. In the system elements, the most energy was lost in the combustion chamber and the highest exergy efficiency was achieved in the compressor at 95% level. Impacts of an increase in ambient temperature, compressor pressure ratio, and change on turbine inlet temperature were further investigated. Energy (Sankey) and exergy (Grossman) flow diagrams were further drawn based on the analyses obtained from the combined cycle power plants.

ÖzDue to the increasing energy need, countries are required to optimize their usage of energy sources for sustaining developments.One of the options to meet the sustainable energy is the use of nuclear power plants (NPPs).However, building and using NPPs represent a great challenge to policy makers of the countries: acceptance of this technology by the citizens.Turkey is one of the countries decided to establish NPPs and adjust their policy in this regard.The country's first NPP is already under construction in Mersin, and the second will be established in Sinop.A survey to evaluate public acceptance of NPPs was given to 838 individuals from different cities of Turkey.The participants were interviewed face-to-face between January and March 2018.The endorsement and opposition rates were determined as 42.3% and 31.1%,respectively.The margin of error at 95% CL was found to be

Hamamatsu single anode R7761 and multi-anode R5900-00-M16 Photomultiplier Tubes have been characterized for use in a Secondary Emission (SE) Ionization Calorimetry study. SE Ionization Calorimetry is a novel technique to measure electromagnetic shower particles in extreme radiation environments. The different operation modes used in these tests were developed by modifying the conventional PMT bias circuit. These modifications were simple changes to the arrangement of the voltage dividers of the baseboard circuits. The PMTs with modified bases, referred to as operating in SE mode, are used as an SE detector module in an SE calorimeter prototype, and placed between absorber materials (Fe, Cu, Pb, W, etc.). Here, the technical design of different operation modes, as well as the characterization measurements of both SE modes and the conventional PMT mode are reported.

Prediction of $Z\rightarrow l^{+}l^{-}$ production cross section (where $l^{\pm} =e^{\pm},\mu^{\pm}$) in proton-proton collisions at $\sqrt{s}$=14 TeV is estimated up to next-to-next-to-leading order (NNLO) in perturbative QCD including next-to-leading order (NLO) electroweak (EW) corrections. The total inclusive Z boson production cross section times leptonic branching ratio, within the invariant mass window $66<m_{ll}<116$ GeV, is predicted using NNLO HERAPDF2.0 at NNLO QCD and NLO EW as $\sigma_{Z}^{Tot}$= 2111.69$_{-26.92}^{+26.31}$ (PDF) $\pm11$ ($\alpha_{s}$) $\pm$17 (scale) $^{+57.41}_{-30.98}$ (parameterization and model). Theoretical prediction of the fiducial cross section is further computed with the latest modern PDF models (CT14, MMHT2014, NNPDF3.0, HERAPDF2.0 and ABM12) at NNLO for QCD and NLO for EW. The central values of the predictions are based on DYNNLO 1.5 program and the uncertainties are extracted using FEWZ 3.1 program. In addition, the cross section is also calculated as functions of $\mu_{R}$ and $\mu_{F}$ scales. The choice of $\mu_{R}$ and $\mu_{F}$ for scale variation uncertainty is further discussed in details.

Due to the increase in energy consumption and environmental pollution in recent years, countries have included renewable energy in their long-term energy policies by supporting researches to increase the usage diversity and performance of renewable energy sources. Solar energy, one of these renewable energy types, and its various applications are of great importance to increase the energy production diversity. In this context, evaluation of monocrystalline and polycrystalline photovoltaic panel performance was performed under Sinop climate conditions. In the first stage, the most suitable panel tilt for Sinop province was found by recording the voltage and current values of the panels at different panel angles. Then, in different days, the efficiencies of the panels were calculated using the determined optimum angle and compared with the literature. Finally, the effect of temperature change on the panels was evaluated. With this study, the most suitable panel type is determined for Sinop province and its surrounding conditions, thus preventing unnecessary investments and efficiency losses.

Predictions of fiducial cross sections, differential cross sections and lepton charge asymmetry are presented for the production of $W^{\pm}$ bosons with leptonic decay up to next-to-next-to-leading order (NNLO) in perturbative QCD. Differential cross sections of $W^{\pm}$ bosons and W boson lepton charge asymmetry are computed as a function of lepton pseudorapidity for a defined fiducial region in $pp$ collisions at $\sqrt{s}=13$ TeV. Numerical results of fiducial $W^{\pm}$ cross section predictions are presented with the latest modern PDF models at next-to-leading order (NLO) and NNLO. It is found that the CT14 and NNPDF 3.0 predictions with NNLO QCD corrections are about 4$\%$ higher than the NLO CT14 and NNPDF 3.0 predictions while MMHT 2014 predictions with NLO QCD corrections are smaller than its NNLO QCD predictions by approximately 6$\%$. In addition, the NNLO QCD corrections reduce the scale variation uncertainty on the cross section by a factor of 3.5. The prediction of central values and considered uncertainties are obtained using FEWZ 3.1 program.

Enerji, sanayileşmenin alt yapısı ve günlük hayatın vazgeçilmez bir unsurudur. Bu nedenle, enerji ihtiyacı ulusal ve uluslararası gündemde oldukça önemli bir yer tutar. Enerji ihtiyacının her geçen gün artması ve sanayileşme hedefleri gerçekleştirilirken önemli çevre sorunlarının ortaya çıkmış olması gibi nedenlerle yenilenebilir enerji kaynaklarının kullanımına olan ilgiyi artırmıştır. Kanatlı hayvan yetiştiriciliği Türkiye ve Dünyada hızlı büyüyen sektörlerden biridir. Bununla birlikte son zamanlarda çiftlik kapalı alanlarında iklimlendirme-havalandırma, aydınlatma ve besleme sistemleri kullanılması üretim kalite ve verimlerinin hızla artmasını sağlamaktadır. Buna endeksli olarak, daha iyi kalite ve yüksek verime ulaşabilmek için kullanılan yöntem ve makinelerden dolayı enerji tüketimi de doğru orantılı olarak artmaktadır. Yapılan bu tesis tasarımıyla tavuk çiftliğinin çatısına yerleştirilen güneş panellerinden elde edilen elektrikle yemleme cihazlarının elektrikli motorları, aydınlatma ve iklimlendirme sisteminin elektriğinin karşılanması amaçlanmıştır. Tavuk çiftliğinin aylık ortalama elektrik tüketimi ise 2778 kWh bulunmuştur. 1000 adet tavuğun yetiştirileceği çiftlikte aylık ortalama elektrik tüketim maliyeti 1290 TL, yıllık toplam maliyeti ise 15.480 TL olarak bulunmuştur. Çatıya kurulacak olan sistemin aylık ortalama üretimi 2875 kWh olarak hesaplanırken yıllık toplam elektrik üretimi 34510 kWh bulunmuştur. Çatıya yerleştirilen fotovoltaik panellerin kendini amorti süresi 6 yıl olarak hesaplanmış ve güneş enerji ile üretim yapan bu tesis tasarımı sayesinde 32439.4 kg CO2 salınımı da engellenmiştir.

In this study, the linear attenuation coefficients of the doped carbon fiber-reinforced epoxy composites (Boron Oxide (B2O3), Lead Monoxide (PbO) and Zinc Borate (2ZnO 3B2O3 3H2O)) for the gamma radiation are investigated with the help of the High Purity Germanium (HPGe) Detector. The doped carbon fiber-reinforced epoxy composites were prepared with different proportions of additive materials (10, 20, and 30 wt%) so that impact of the additive amount on radiation shielding could be properly analysed. The specimens were tested at 7 different energy levels ranging from 82.0 to 1332.0 keV with the use of HPGe detector. Further on, the effect of additive materials on mechanical properties was also examined. Findings indicate that all additives into composite materials improve the gamma attenuation ability, and the best gamma shielding characteristic is obtained in the case of 30 wt% Lead Monoxide sample. On the other hand, 10 wt% additive materials provide increase in stiffness compared with undoped samples.

In the last few decades, the challenges of ionizing radiationIonizing radiation shieldingRadiation shielding have begun gaining attention of investigators in order to minimize the harmful effectsHarmful effects of various radiations especially on workers who are interested in the outcome of a nuclearNuclear or radiologicalRadiological situation that requires protectionProtection. In this context, the presented chapter focuses on the shieldingShielding preparation, materials designMaterials design, photonPhoton, and neutron shieldingNeutron shielding performancesPerformance of polymer-based compositesPolymer-based composite doped with bismuth nitrateBismuth nitrate in different weight ratiosWeight ratio. Here, the photon attenuationPhoton attenuation behavior of the prepared compositesComposite is determined using a gamma spectrometerGamma spectrometer equipped with High Purity Germanium (HPGe) detectorHPGe detector that covers a wide energyEnergy range varying from 0.060 to 1.408 meV. Besides, the obtained experimental dataExperimental data are further compared with the results of theoreticalTheoretical (WinXCOM softwareWinXCOM software) and Monte Carlo simulation (GEANT4)Monte Carlo simulation (GEANT4). In addition, the fast neutronFast neutron massMass removal cross sectionsCross section and the numbers of transmitted neutronsNeutron at different thicknessThickness and neutronNeutron energiesEnergy are estimated with the use of GEANT4Monte Carlo simulation (GEANT4) simulationsSimulation by codingCoding the elemental compositions of the fabricated compositesComposite. The results showed that the gamma attenuationGamma attenuation was improved with the increase of BiNOBiNO dopantDopant amount. Among the prepared samples, the sample with 20% BiNOBiNO concentrationConcentration was found to be the best radiation shieldingRadiation shielding material. In addition to being used for the ionizing radiationIonizing radiation shieldingRadiation shielding, such polyesterPolyester compositesComposite can also be used as shielding absorbersShielding absorber for the low-energyLow-energy ionizing radiationIonizing radiation. In short, it is expected that the researchers and scientists in the fieldsField of nuclearNuclear and medical physicsMedical physics will benefit from this chapter.

Measurement of the muon charge asymmetry in inclusive $pp$$\rightarrow$$W(\mu\nu)$ + X at $\sqrt{s}$ = 8 TeV is presented. The data sample corresponds to an integrated luminosity of 18.8 $fb^{-1}$ recorded with the CMS detector at the LHC. With a sample of more than a hundred million $W$$\rightarrow$$\mu$$\nu$ events, the statistical precision is greatly improved in comparison to previous measurements. This new result can provide additional constraints on the parton distribution functions of the proton. This measurement is used together with the cross sections for inclusive deep inelastic ep scattering at HERA in a next-to-leading-order QCD analysis. The impact to the valence quark distributions is demonstrated.

Hamamatsu single anode R7761 and multi-anode R5900-00-M16 Photomultiplier Tubes have been characterized for use in Secondary Emission Ionization Calorimetry study, that is a novel techique to measure the electromagnetic shower particles in extreme radiation environment. There are different SE modes used in the tests, developed from conventional PMT mode. Here, the technical design of secondary emission modules and characterization measurements of both SE modes and the PMT mode are reported.

Measurement of the muon charge asymmetry in inclusive $pp$$\rightarrow$$W(μν)$ + X at $\sqrt{s}$ = 8 TeV is presented. The data sample corresponds to an integrated luminosity of 18.8 $fb^{-1}$ recorded with the CMS detector at the LHC. With a sample of more than a hundred million $W$$\rightarrow$$μ$$ν$ events, the statistical precision is greatly improved in comparison to previous measurements. This new result can provide additional constraints on the parton distribution functions of the proton. This measurement is used together with the cross sections for inclusive deep inelastic ep scattering at HERA in a next-to-leading-order QCD analysis. The impact to the valence quark distributions is demonstrated.

The proton-proton collision energy at Large Hadron Collider (LHC) has been 7, 8 and 13 TeV recently with the goal of reaching to 14 TeV which is the maximum capacity of the LHC. However, there is still more physics yet to be explored and tested beyond the energy regime of the LHC to reach new discoveries. Therefore, a new collider bigger than the LHC machine, which will be able to collide protons at 100 TeV center-of-mass energy, is under consideration by the high-energy physics community. To provide an insight to the transition from LHC to 100 TeV collider, some properties of W and Z processes are investigated in a range of collision energy from 7 to 100 TeV using HERAPDF2.0, MMHT2014, NNPDF3.1 and CT14 NNLO PDF models at NNLO QCD. The considered properties are the production rates of W and Z bosons, the change of uncertainties (PDF, renormalization and factorization scales, strong coupling constant, model and parameterization), W boson lepton charge asymmetry, forward-backward asymmetry, and k-Factors of W and Z bosons.

Parton distribution functions (PDFs) describe the internal structure of the proton and are necessary inputs to almost all theory predictions of hadron colliders. One way to do a precise measurement of a PDF is to measure the lepton charge asymmetry of W boson where u$\bar{d}\to W^{+}$ and $d\bar{u}\to W^{-}$. Therefore, u, d, $\bar{u}$, and $\bar{d}$ quark shapes of the most modern PDF models (NNPDF3.1, NNPDF3.0, CT14, MMHT2014, and HERAPDF2.0) are inspected using the APFEL online cluster in this paper. The ratio of $d$ to $u$ is further investigated since the charge asymmetry is sensitive to the value of $d$ over $u$ momentum distributions in the proton. $Q$ scale dependence of PDFs are further studied in a range from 1 to 100 GeV.

The proton-proton collision energy at Large Hadron Collider (LHC) has been 7, 8 and 13 TeV recently with the goal of reaching to 14 TeV which is the maximum capacity of the LHC. However, there is still more physics yet to be explored and tested beyond the energy regime of the LHC to reach new discoveries. Therefore, a new collider bigger than the LHC machine, which will be able to collide protons at 100 TeV center-of-mass energy, is under consideration by the high-energy physics community. To provide an insight to the transition from LHC to 100 TeV collider, some properties of W processes are investigated in a range of collision energy from 7 to 100 TeV using HERAPDF2.0, MMHT2014, NNPDF3.1 and CT14 NNLO PDF models at NNLO QCD. The considered properties are the production rates of W, the change of uncertainties (PDF, renormalization and factorization scales, strong coupling constant, model and parameterization), and W boson lepton charge asymmetry.

The proton-proton collision energy at Large Hadron Collider (LHC) has been 7, 8 and 13 TeV recently with the goal of reaching to 14 TeV which is the maximum capacity of the LHC. However, there is still more physics yet to be explored and tested beyond the energy regime of the LHC to reach new discoveries. Therefore, a new collider bigger than the LHC machine, which will be able to collide protons at 100 TeV center-of-mass energy, is under consideration by the high-energy physics community. To provide an insight to the transition from LHC to 100 TeV collider, some properties of W processes are investigated in a range of collision energy from 7 to 100 TeV using HERAPDF2.0, MMHT2014, NNPDF3.1 and CT14 NNLO PDF models at NNLO QCD. The considered properties are the production rates of W, the change of uncertainties (PDF, renormalization and factorization scales, strong coupling constant, model and parameterization), and W boson lepton charge asymmetry.

Enerjide sürekliliği sağlayabilmek ve dışa bağımlılığı en aza indirebilmek için ülkelerin birden çok enerji kaynağını kurulu sistemler halinde yönetebilmesi gerekmektedir. Nükleer enerji düşük karbon salımlı bir enerji kaynağı olması sebebiyle çağımızın iklim değişikliği sorunuyla mücadelede kilit rol oynama potansiyeline sahip bir enerji türü olarak değerlendirilmektedir. Nükleer santraller kullandığı yakıt kütlesine oranla yüksek miktarda enerji açığa çıkarabilmesi, hava olaylarından etkilenmeden devamlı olarak enerji üretebilmesi ve elektrik üretim maliyetleri konusundaki öngörülebilirliği gibi kendine özgü özellikleri ile ülkeler tarafından tercih edilmektedir. Türkiye, Japonya ve Güney Kore nükleer güç santrali teknolojilerine sahip olabilmek için erken bir dönemde ve yaklaşık olarak aynı zaman diliminde adımlar atmaya başlayan ülkelerdendir. Japonya ve Güney Kore günümüzde kurulu birçok nükleer santrali ve geliştirmekte olduğu kendi tasarımlarıyla çeşitli alanlarda ulusal ve uluslararası projeler yürütmekte olan iki ülke konumundadır. Türkiye’de başlatılan girişimler için süreç aynı şekilde ilerlememiş ve yapılması planlanan ilk santralin inşaatına 2010’lu yıllarda başlanabilmiştir. Bu çalışmada nükleer güç santrali teknolojilerini elde etme süreçleri birbirine yakın zamanlarda başlamış olan bu üç ülkenin faaliyet süreçleri kronolojik bir düzende ele alınmış ve zaman içerisinde atılan adımlar karşılaştırılmıştır. Türkiye için mevcut durum değerlendirilerek geleceğe yönelik önerilere yer verilmiştir.

Electromagnetic calorimetry in high-radiation environments, e.g., forward regions of lepton and hadron collider detectors, is quite challenging. Although total absorption crystal calorimeters have superior performance as electromagnetic calorimeters, the availability and the cost of the radiation-hard crystals are the limiting factors as radiation-tolerant implementations. Sampling calorimeters utilizing silicon sensors as the active media are also favorable in terms of performance but are challenged by high-radiation environments. In order to provide a solution for such implementations, we developed a radiation-hard, fast and cost-effective technique, secondary emission calorimetry, and tested prototype secondary emission sensors in test beams. In a secondary emission detector module, secondary emission electrons are generated from a cathode when charged hadron or electromagnetic shower particles penetrate the secondary emission sampling module placed between absorber materials. The generated secondary emission electrons are then multiplied in a similar way as the photoelectrons in photomultiplier tubes. Here, we report on the principles of secondary emission calorimetry and the results from the beam tests performed at Fermilab Test Beam Facility as well as the Monte Carlo simulations of projected, large-scale secondary emission electromagnetic calorimeters.

In high-radiation environments, electromagnetic calorimetry is particularly challenging. To address this, a feasible approach involves constructing a sampling calorimeter that employs radiation-hard active media, albeit at the expense of high energy resolution. In response, we developed an innovative technique, secondary emission calorimetry, which offers radiation resistance, rapid response, robustness, and cost-effectiveness. Our efforts involve the creation of prototype secondary emission sensors, subjected to comprehensive testing within test beams. In the secondary emission detector module, incident charged hadrons or electromagnetic shower particles trigger the generation of secondary emission electrons from a cathode. These generated electrons are subsequently amplified in a manner similar to the process within photomultiplier tubes. This report provides an insight into the principles underlying secondary emission calorimetry, presents findings from beam tests, and outlines Monte Carlo simulations that project towards the potential application of large-scale secondary emission electromagnetic calorimeters.

In this paper, fiducial cross-sections of lepton pairs with opposite charge via Z → l+ l- (l± = μ±, e±) are calculated at a center-of-mass energy of 14 TeV by applying different transverse momentum selections to evaluate their impact on the production cross-section as well as the differential cross-section of Z bosons in terms of lepton pseudorapidity. The predictions are computed by next-to-next-to-leading order quantum chromodynamics including next-to-leading order electroweak corrections. Forward-backward asymmetry prediction for the Drell?Yan production in proton-proton collision is further calculated at 14 TeV using HERAPDF2.0, MMHT2014, NNPDF3.1, and CT14 parton distribution function models. Then 14 TeV QCD predictions of forward-backward asymmetry are presented as a function of dilepton mass for four different Z boson rapidity regions.

The Large Hadron Collider (LHC) at CERN has been designed to collide beams of protons at 7, 8, 13, and 14 TeV center-of-mass energies and a new hadron collider called the Future Circular Collider (FCC), which is larger and more energetic than the LHC, is being planned for the near future. The maximum planned energy for FCC is 100 TeV center-of-mass energy. In this regard, we present the leading order and next-to-leading order cross-section predictions of two simultaneously produced opposite-sign W bosons at 7, 8, 13, 14, and 100 TeV center-of-mass energies by using the MCFM MC generator. The results are obtained by CT14, MMHT2014, and MSTW2008 parton distribution functions. Finally, the advantage of increasing collision energy at hadron colliders is discussed by comparing the amount of data recorded at different center-of-mass energies for the pp → W+W- process.

Akciğer nodülleri kanser vakalarında sıkça gözlenmektedir.Günümüzde nodüller, tomografi veya MRI gibi teknolojiler kullanılarak görüntülenebilmektedir.Ancak, x-ray görüntüleme yaygın kullanımının yanı sıra düşük maliyetli bir yöntemdir.Bu bağlamda, nodüllerin gelişimlerinin sık aralıklarla takip edilmesinde x-ray görüntülerinin kullanılması birçok yönden fayda sağlamaktadır

ÖzDue to the increasing energy need, countries are required to optimize their usage of energy sources for sustaining developments.One of the options to meet the sustainable energy is the use of nuclear power plants (NPPs).However, building and using NPPs represent a great challenge to policy makers of the countries: acceptance of this technology by the citizens.Turkey is one of the countries decided to establish NPPs and adjust their policy in this regard.The country's first NPP is already under construction in Mersin, and the second will be established in Sinop.A survey to evaluate public acceptance of NPPs was given to 838 individuals from different cities of Turkey.The participants were interviewed face-to-face between January and March 2018.The endorsement and opposition rates were determined as 42.3% and 31.1%,respectively.The margin of error at 95% CL was found to be