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In this study, S235JR (1.0037), 21NiCrMo2 (1.6523), C45 (1.0503), 42CrMo4 (1.7225) steels were coated with nickel, copper, silver, and tin. Then, the radiation shielding performances of the uncoated and coated steels were investigated. The steels were firstly designed by the coating processes via electrolytic plating method on behalf of Ni, Cu, Ag and Sn metals. The samples were then irradiated by radioactive sources for transmission of the gamma rays at 81–383 keV photon energies to measure linear and mass attenuation coefficients (LAC-µ, MAC-µ/) of the pure and coated steels by Ni, Cu, Ag and Sn. Half and tenth value of layers (HVL and TVL) of investigated materials were then calculated at the same studied photon energies. The materials were compared with each other and some shielding concretes on behalf of mean free paths (MFP) at possible. The coated steels were found to be better shielding materials than the concretes due to lower MFP values, and they were also better shielding than reference materials up to 35.31% relative difference in MFP. It was concluded that coating processes improved the shielding properties of the steels.

In this study, the fast neutron and gamma-ray absorption capacities of the new glasses have been investigated, which are obtained by doping CoO,CdWO4,Bi2O3, Cr2O3, ZnO, LiF,B2O3 and PbO compounds to SiO2 based glasses. GEANT4 and FLUKA Monte Carlo simulation codes have been used in the planning of the samples. The glasses were produced using a well-known melt-quenching technique. The effective neutron removal cross-sections, mean free paths, half-value layer, and transmission numbers of the fabricated glasses have been calculated through both GEANT4 and FLUKA Monte Carlo simulation codes. Experimental neutron absorbed dose measurements have been carried out. It was found that GS4 glass has the best neutron protection capacity among the produced glasses. In addition to neutron shielding properties, the gamma-ray attenuation capacities, were calculated using newly developed Phy-X/PSD software. The gamma-ray shielding properties of GS1 and GS2 are found to be equivalent to Pb-based glass.

TiB2 (titanium diboride) is a transition metal boride with remarkable properties and, its thin-film coatings can be deposited on various substrates to develop the wear resistance properties of substrates. Radiation interaction properties of TiB2 coated glass and HSS are very significant as well for shielding applications and it has not been investigated so far. In this work, linear attenuation coefficient (µ), half-value layer (HVL), tenth-value layer (TVL) and mean free path (MFP) of TiB2 coated glass and HSS (AISI-M2) were measured using a 133Ba radioactive point source at energies 80.8, 276.4, 302.8, 356 and 383.8 keV. A comparison has been made with some radiation shielding concretes with respect to MFP. Energy absorption and exposure buildup factors (EABF and EBF) of composites were also calculated in the experimental energy region 50 – 500 keV. TiB2 coated glass and HSS were found to be better radiation shielding materials than the standard shielding concretes concluding that they can be further developed for radiation shielding applications.

The purpose of the present work is robust calculation of effective atomic numbers ($${Z}_{\text{eff}}$$s) for photon, electron, proton, alpha particle and carbon ion interactions through the newly developed software, Phy-X/ZeXTRa (Zeff of materials for X-Type Radiation attenuation). A pool of total mass attenuation and energy absorption coefficients (for photons) and total mass stopping powers (for charged particles) for elements was constructed first. Then, a matrix of interaction cross sections for elements Z = 1–92 was constructed. Finally, effective atomic numbers were calculated for any material by interpolating adjacent cross sections through a linear logarithmic interpolation formula. The results for $${Z}_{\text{eff}}$$ for photon interaction were compared with those calculated through Mayneord’s formula, which suggests a single-valued $${Z}_{\text{eff}}$$ for any material for low-energy photons for which photoelectric absorption is the dominant interaction process. The single-valued $${Z}_{\text{eff}}$$ was found to agree well with that obtained by other methods, in the low-energy region. In addition, $${Z}_{\text{eff}}$$ values of various materials of biological interest were compared with those obtained experimentally at 59.54 keV. In general, the agreement between values calculated with Phy-X/ZeXTRa and Auto-Zeff and those measured were satisfactory. A comparison of $${Z}_{\text{eff}}$$ values for photon energy absorption calculated with Phy-X/ZeXTRa and literature values for a nucleotide base, adenine, was made, and the relative difference (RD) in $${Z}_{\text{eff}}$$ between Phy-X/ZeXTRa and literature values was found to be 2%

Halloysite is a clay mineral found in the natural environment and it has many applications in chemistry and medical fields. The linear attenuation coefficient (µ) for halloysite nanotubes m...

Optical materials based glasses started to gain much attention due to its thermal and mechanical stability besides its friendly environment, especially in radiation shielding applications. In this work, we synthesized a series of five glasses using melt-quenching-annealing method. The glasses were synthesized was boro-silicate glasses with the composition of (40−x−y) B2O3 - 10 SiO2 - 10 Al2O3 - 30 ZnO - 10 Li2O - x Er2O3 - y Yb2O3, were (x = 1.0 mol %) and (y = 0.5, 1.0, 1.5, 2.0, and 2.5). Specific physical properties for those glasses have been measured and calculated based on related formulas. X−ray diffraction has been utilized to study the glassy nature of these materials, Raman spectrometer study was used to explore the structure of the fabricated glasses. Optical properties were thoroughly studied such as optical absorption, and optical band gap. The basic gamma photon shielding parameters for the prepared glasses were reported between 0.015 and 15 MeV. The mass attenuation coefficient for the prepared samples increases as Yb2O3 concentration increases from 0.5 to 2.5 mol%. The highest and lowest values of the effective atomic number were found for 2.5 Yb+3 and 0.5 Yb+3 which contain the maximum and minimum concentrations of Yb2O3. The radiation shielding results suggested that 2.5 Yb+3 is the superior photons attenuator among the B2O3–SiO2–10Al2O3–ZnO–Li2O–Er2O3−Yb2O3 glasses.

In this study, nanocomposite material made of ultra-high molecular weight and bismuth oxide was developed to be used for protection from nuclear radiation. The traditional hot-pressing technique was used for preparing composite samples. The concentrations of Bi2O3 were selected to be 0.5, 1.0, 1.5, 2.0 wt%. In order to study the changes in surface morphology, we examined all samples by scanning electron microscopic (SEM). We evaluated the semi-quantitative of all elements used to fabricate these samples using EDX. Additionally, all samples including pure Bi2O3 has been examined with X-ray diffraction (XRD). Besides that, Raman spectroscopy of all synthesized polymer matrix was measured to explore the different molecular groups. Also, the photon attenuation ability for the present samples was measured experimentally at eight energies varying from 30.8 keV to 383.9 keV using 133Ba radioactive point source.

The leaded brasses show high machinability and atmospheric corrosion resistance. Hence, they are being used in different applications such as machine parts, valves, fittings etc. Besides, they can serve as radiation shields as they contain lead and their radiation shielding properties were not investigated so far. Thus, the aim of this study is to determine the radiation shielding properties of leaded brasses. Standard (CuZn) and leaded (CuZnPb) brasses were prepared and their mass attenuation coefficients (?/?), half-value layers (HVL), tenth-value layers (TVL), mean free paths (MFP) and effective atomic numbers (Z eff ) were determined. Linear attenuation coefficients (?) of the alloys were measured first at 53, 276, 302, 356 and 383 keV using a HPGe detector and a 133 Ba radioactive source. These values were then used to obtain other parameters. A good agreement was observed between experimental and theoretical results for HVL, TVL and MFP (Dif. ? 9%). Photon buildup through the present materials was studied in terms of exposure buildup factor (EBF). Results were presented and discussed regarding the photon energy and penetration depths. Fast neutron removal cross sections were also calculated for the given alloys. Some alloys were also evaluated morphologically by using EDX mapping. The leaded brasses were compared with standard shielding concretes and superior shielding properties against gammas and fast neutrons were obtained when compared with concretes. © 2019 Elsevier Ltd

Family of lithium zinc fluoroborate glasses with 15ZnF2-10BaO-8Al2O3–12Li2O-(55-x) B2O3-xEr2O3 (x = 0.5, 0.7, 1.1, 1.3 and 1.5 mol%) composition were prepared by conventional melt-quench method. The glasses were characterized to study their structural, physical, optical and radiative properties. The amorphous characteristic of glass was noticed in X-Ray Diffraction pattern. A modification in structure was observed as density values increased with Er2O3 content. UV–Vis–NIR transitions of Er3+ in the host matrix were identified through absorption spectra. Covalent nature of bonding between Er3+ ions and their surrounding ligands was observed through bonding parameter and Judd-Ofelt parameters. Red shift of the fundamental absorption edge in the absorption spectra and decreasing indirect and direct band gaps with increasing Er3+ concentration jointly confirmed the role of Er3+ ions as network modifier. Hypersensitive transitions of Er3+ ion namely 4I15/2 → 2H11/2 & 4I15/2 → 4G11/2 were interpreted through their higher oscillator strengths when compared to other transitions. Emission spectra recorded at 980 nm excitation showed a peak corresponding to 4I13/2 → 4I15/2 NIR transition of erbium ion. Stimulated emission cross section of Er0.5 sample, gain bandwidth and Figure of Merit were found to be 16.79 × 10−21 cm2, 1225.83 × 10−28 cm3 and 37.36 × 10−24 cm2 s respectively. Photoluminescence decay curve of Er0.5 sample was well-fitted to single exponential first order function. The experimental decay lifetime τexp for the 4I13/2 level was measured to be 0.34 ms. The wide frequency range of FWHM (1.02–1.67 × 1013 Hz) and high values of radiative parameters make the glass a suitable candidate as optical amplifier and NIR laser material.

Radiation shielding characteristics of different germanate glasses with compositions of Nd doped Bi2O3–SiO2/GeO2–Nd2O3, Sm3+ doped B2O3–GeO2–Gd2O3, Tb3 doped GeO2–B2O3–SiO2–Ga2O3, TeO2–GeO2–Li2O and Na2O–GeO2–P2O5 glasses have been studied using XCOM program at several photon energies between 0.015 and 10 MeV. Dependencies of their photon attenuation properties with the photon energy and the composition have been investigated. The mass attenuation coefficient values and the effective atomic numbers for Nd doped Bi2O3–SiO2/GeO2–Nd2O3glasses are higher than those of the other samples. 69Bi2O3–30GeO2–1.0Nd2O3 has the highest mass attenuation coefficients among the selected samples. The Zeff results revealed that to increase the photon attenuation ability for the germanate glasses, high Z-elements (such as Bi, Te and Tb) in a suitable concentration must be included. The HVL results for the present germanate glasses suggested that the attenuation capacity of the gamma photons increases as the density of the sample increases, hence, the glass sample with high density must be considered for high attenuation ability. Also, the significant influence of modifier contents on the HVL values namely the attenuation ability has been noticed for Tb3 doped GeO2–B2O3–SiO2–Ga2O3 and TeO2–Li2O–GeO2 glasses. Moreover, the values of the mean free path for the selected samples have been compared with those of different radiation shielding glasses and concrete samples.

Stainless steel is commonly used in radiation applications for its high temperature resistance and fine mechanical properties. In this study, three types of high alloyed stainless-steel samples were produced. Before the production, GEANT4 Monte Carlo simulation toolkit was used to estimate the total fast neutron macroscopic cross sections and gamma mass attenuation coefficients. The hot-pressing process and the powder metallurgy method were applied. We tested samples' chemical and mechanical strength. Samples were exposed to both gamma rays and fast neutrons. The obtained simulation and experimental results for both neutron and gamma radiation are compatible. According to the simulation and experimental results, neutron shielding capacity of the new stainless-steel alloys is higher than the most commonly used 316LN stainless steel in nuclear applications. Among the prepared samples, SSA1 steel has the smallest half value layer at the all examined energies. All the prepared samples posses higher mass attenuation coefficient values and lower half value layer than 316LN steel. This indicates that the produced three new high alloyed stainless-steel samples have high gamma absorption capacity when compared to 316LN steel., University of Ataturk [2016/FM7, FBA-2017-6312]; University of Agri Ibrahim Cecen [MYO. 18.001]; Universiti Putra Malaysia (UPM) under Inisiatif Putra Muda (IPM), This work is financially supported by University of Ataturk with Grant No. 2016/FM7, FBA-2017-6312, University of Agri Ibrahim Cecen with Grant no. MYO. 18.001 and Universiti Putra Malaysia (UPM) under Inisiatif Putra Muda (IPM) is gratefully acknowledged.

Some potential drug active substances with the ability to reduce the effects of radiation on human tissues and cells were investigated. For this purpose, eight different types of sulfamide derivatives were synthesized and nuclear radiation protection parameters were determined. Neutron radiation reduction parameters such as the half-value layer effective removal cross-sections, mean free path, and the number of particles passing through the sample were determined with GEANT4 code. Additionally, the gamma radiation attenuation parameters of the materials examined were determined using Phy-X/PSD software in the energy area of 0.015-15 MeV. These parameters are the half-value layer, mass attenuation coefficient, mean free path, exposure buildup factor and effective atomic number. Neutron radiation absorption experiments were applied using an Am-241-Be fast neutron source. All results obtained for neutron radiation were compared with paraffin and water. It has been found that the ability of sulfamide derivatives to absorb these radiations is superior to reference materials. To determine whether these derivatives could have adverse effects on human health, their genotoxic potential was determined using the Ames/Salmonella bacterial reversion test. The results showed that these derivatives can be considered genotoxically safe in tests at concentrations up to 5 mM. Thus, it is suggested that the derivative materials examined in this study can be used as active substances for a drug to be made for protection against both neutron and gamma radiation., Scientific and Technological Research Council of Turkey (TUBITAK) [112T881]; Ataturk University, The authors are indebted to the Scientific and Technological Research Council of Turkey (TUBITAK, Grant No. 112T881) and Ataturk University for their financial support of this work.

In this study, four newly developed chromium ore based new heavy concretes containing different types of minerals (chromium ore, hematite (Fe2O3), titanium oxide (TiO2), limonite (FeO(OH)nH2O), and siderite (FeCO3) and compounds (galena (PbS), chromium oxide (Cr2O3) and manganese oxide (MnO2) were investigated for neutron and gamma shielding effectiveness. It was observed that the developed concretes have strength up to 30 MPa (4351.131 psi) using mechanical stress tests. In addition, temperature resistance tests were carried out and the results were found to be up to desired level. GEANT4 simulation was employed to determine the effective removal cross-section ΣR (cm−1), transmission number mean free path (MFP), and half value layer (HVL) of the concretes. The equivalent dose rate of fast neutron was calculated using Am–Be source and BF3 proportional counter. Gamma-ray shielding properties mass attenuation coefficients, half-value layer, mean free path, and effective atomic number of the concretes were assessed in the energy range between 0.015 and 15 MeV. The obtained results were compared with paraffin, ordinary concretes, and some heavy concretes. Both theoretical and experimental calculations have shown that all new heavy concretes are capable of absorbing high rates of gamma and neutron radiation than reference samples. In particular, the D3 sample has the maximum neutron attenuation dose value, which contains 55% chromium ore. D2 is superior gamma shielding concrete and this contains 60% chromium ore, 10% hematite, 5% TiO2 and 5% PbS. The new developed concretes are found to be alternative shielding material for the nuclear energy applications.

In this study, six different types of quinoline derivatives were synthesized, which can be used as an anti-radiation drug for active matter and its effects against radiation was determined. The effective removal cross-sections, mean free path, halfvalue layer and neutron transmission number were calculated for fast neutron radiation using the Monte Carlo simulation GEANT4 and FLUKA codes. Gamma radiation shielding parameters such as mass attenuation coefficient (MAC), effective atom number (Zeff), mean free path (MFP), exposure buildup factor (EBF) and halfvalue layer (HVL) were theoretically calculated using WinXCom and Phy-X/PSD software. Neutron equivalent dose measurements were performed using a 241Am–Be fast neutron source and a BF3 gas detector with 4.5 MeV of energy and 74 GBq activity. Both simulation and experimental measurements were compared with paraffin and conventional concrete. It was found that the quinoline derivative shielding material absorbed radiation much better than these reference materials. Additionally, the genotoxic potentials of the derivatives were assessed by using the yeast DEL assay and the results revealed that the derivatives can be considered genotoxically safe at the tested concentrations (up to 5 mM). It has been suggested that this new radiation shielding derivatives material can be used as active ingredients for a drug to be developed against both neutron and gamma radiation.

In this study, it was focused on the research of new materials with high attenuation efficiency that can be used as radiation shielding material due to the incapability of conventional materials. In accordance with this purpose, the radiation shielding capabilities of four different precipitation-hardening stainless steels (PH-SSs), which are symbolized 15-5PH, 15-7PH, 17-4PH and 17-7PH, were determined both experimentally and theoretically in a wide range of radiation energy. For experimental measurements, two different detectors (Si(Li) and Na(Tl)) and twenty-three different photon energies (from 22.1 to 1332.5 keV) emitted from seven different radionuclides were used in narrow-beam transmission geometry. Phy-X/PSD software were used for theoretical calculations. The theoretically calculated parameters were determined both in the photon energies emitted by the radionuclides used in the experiment and in the continuous energy range of 0.015-15 MeV. Furthermore, in order to make a remarkable assessment of the integration of PH-SSs to nuclear energy applications, the all results obtained have been compared with the corresponding values of Fe-based steel concretes (steel-scrap (SS) and steel magnetite (SM)), which are widely used as conventional shield materials in nuclear power plants. Moreover, in order to choose the best material to be used in nuclear applications among the PH-SSs, the results were evaluated comparatively in terms of both the characteristics of the materials and the magnitude of the radiation shielding parameters. Consequently, it was concluded that the material with the best radiation shielding performance among the examined PH-SSs was 15-7PH and the radiation shielding performance ranking was generally in the form of 15-7PH >= 15-5PH > 17-4PH > 17-7PH > SM > SS. Due to both high attenuation efficiency and superior properties for radiation shielding, it was determined that the PH-SSs can be used as new shielding materials in nuclear applications.

In this study, new glasses were designed and produced that did not consist of toxic lead oxide (PbO). Unlike conventional glass with powdered silicon oxide (SiO2) added [cobalt oxide (CoO), cadmium tungsten oxide (CdWO4), bismuth oxide (Bi2O3), chromium oxide (Cr2O3), and boron oxide (B2O3)], new glass specimens were fabricated via melt-quenching. The total macroscopic cross-sections, mean free path, and transmission number were calculated using GEANT4 Monte Carlo code. The equivalent dose rates were measured for 4.5 MeV fast neutrons. Gamma attenuation experiments were conducted at several energies in a range of 53-383 keV. The experimental and theoretical results were compared with those of construction concrete, paraffin, glasses containing lead, borosilicate, normal window, and soda glasses. The new glass minimized both gamma and neutron radiation leaks that may occur in various fields such as radiation treatment, nuclear power plants, radioactive waste transport and storage, and space and laboratory research., Ataturk University [2015/337, FBA-2017-6312]; Agri Ibrahim Cecen University [MYO.18.001-19.001], This study was supported by the Ataturk University Scientific Research Projects (2015/337, FBA-2017-6312) and Agri Ibrahim Cecen University (grant no. MYO.18.001-19.001).

In this study, it has been investigated of the Compton profiles (CP) of the Ar and O2 gases using a Compton spectrometer having annular 241Am radioactive source. The photons emitted from the radioactive source and scattered photons from the samples were recorded using HPGe detector. In order to obtain experimental Compton profiles of the samples the Warwick codes were used. The experimental results obtained were compared with the theoretical results calculated by Hartree-Fock method. The results clearly show that the experimental and theoretical results are in good agreement, especially in the high momentum region. It was observed that while the difference between the experimental and theoretical results of Ar and O2 gases in the pz = 0 region is about 4%, this difference is below 1% after pz = 2., Bu çalışmada, dairesel 241Am radyoaktif kaynağa sahip bir Compton spektrometresi kullanılarak Ar ve O2 gazlarının Compton profilleri araştırılmıştır. Radyoaktif kaynaktan yayınlanan fotonlar ve numunelerden saçılan fotonlar HPGe detektörü kullanılarak kaydedildi. Numunelerin deneysel Compton profillerini elde etmek için Warwick kodları kullanıldı. Elde edilen deneysel sonuçlar Hartree-Fock yöntemi ile hesaplanan teorik sonuçlarla karşılaştırıldı. Sonuçlar, özellikle yüksek momentum bölgesinde deneysel ve teorik sonuçların uyumlu olduğunu açıkça göstermektedir. pz = 0 bölgesindeki Ar ve O2 gazlarının deneysel ve teorik sonuçları arasındaki fark yaklaşık % 4 iken pz = 2'den sonra bu farkın % 1'in altında olduğu görülmüştür.

Purpose: Quinoline is formed by various natural compounds, such as alkaloids from the cinchona plant, which exhibit various biological activities, and is an important building material for the development of new drugs. Quinoline can be used in anti-radiation drug development but radiation interaction properties must be determined. Material and methods: In this study, six types of synthesized quinoline derivatives were used. Fast neutron removal cross-section, mean free path, half value layer and transmission number were theoretically determined by using GEometry ANd Tracking 4 and FLUktuierende KAskade simulation codes for neutron shielding. Neutron dose absorption rates were determined using the(241)Am-Be fast neutron source and the Canberra NP series portable BF(3)gas proportional neutron detector. Gamma radiation shielding parameters were determined by using WinXCom and PSY-X/PSD software. Additionally, the genotoxic potentials of the derivatives were assessed by using the Ames/Salmonellabacterial reversion assay. Results and conclusions: Neutron shielding parameters such as removal cross-section, mean free path, half value layer and transmission number were theoretically determined for fast neutrons. To determine neutron absorption capacity of quinoline derivatives, neutron absorption, experiments were conducted. In addition, gamma radiation shielding parameters were calculated such as the mean free path (MFP), mass attenuation coefficient (mu t), half value thickness layer (HVL) and effective atomic number (Zeff) in the energy range of 0.015-15 MeV. The results of the all quinoline derivatives have excellent fast neutron shielding power compared to ordinary concrete. In addition, all quinoline derivatives have been found to have the capacity to attenuate gamma radiation. Moreover, they absorb well in both types of radiation, do not cause secondary radiation, and they are genotoxically safe at the tested concentrations. This study has demonstrated that these products can be used as active ingredients for a drug to be developed against radiation.

This is the second part of a two-part study on the investigation of radiation shielding performances of some important AISI-coded stainless steels (AISI-302, 304, 321 and 430). Part 1 addressed experimental evaluation by means of measured photon-material interaction parameters. In this second part, we focused on the calculation and discussion of other interaction parameters, which are a guide to choice optimum shielding materials in the nuclear processes for the present AISI-coded stainless steels. The present stainless steels have superior mechanical properties, high temperature and corrosion resistances and these properties can make them favorite materials for nuclear applications. For this reason, firstly, the incoherent scattering/total attenuation ratio (R-inc/total) and equivalent atomic number (Z(eq)) were calculated in the energy region of 0.015-15 MeV. Secondly, the exposure build-up factor (EBF) and energy absorption build-up factor (EABF) were determined to select steels by using Geometric Progression (G-P) fitting method, which have five parameters (a, b, c, d and X-k coefficients), up to penetration depth of 40 MFP at energy 0.015-15 MeV. Thirdly, the mass stopping powers (MSPs; dE/rho dx ; MeVcm(2)/g) and ranges (R-e, R-p and R alpha; mu m) for electron, proton and alpha particle interactions were calculated at energy 10 keV-20 MeV. Finally, the fast neutron removal cross-sections (FNRCSs; Sigma R; cm(-1)) were calculated. To be able to make comparison and a satisfying assessment about radiation shielding capabilities of present AISI-coded steels, all parameters were also computed for ordinary (OC), steel-scrap (SS) and steel-magnetite (SM) concretes (Fe-based steel concretes) that are most commonly used as a shielding material in many nuclear applications. The shielding capabilities of the present stainless steels against both gamma and the fast neutron and charged particle radiation were evaluated in the light of the calculated parameters. As a result of the mutual evaluation of the results obtained for the shielding concretes and the examined stainless steels, it was found that present stainless steels had excellent shielding properties compared to shielding concretes in terms of both photon radiation and particle radiation., Bayburt University Research Fund [2018/01-69001-04], This study was product with the support of Bayburt University Research Fund under Project No. 2018/01-69001-04.

The investigation of radiation shielding performances of AISI-302, 304, 321 and 430 stainless steels which have wide range of application because of their superior mechanical properties, temperature and corrosion resistances was aimed in this study. In accordance with this purpose, photon-shielding parameters of these stainless steels were calculated both experimentally and theoretically. These parameters calculated are linear attenuation coefficient, mass attenuation coefficient, mean free path, half-value layer, quarter-value layer, tenth-value layer, total atomic cross-section, total electronic cross-section, effective atomic number, effective electron number and effective conductivity. They were experimentally measured at twenty-three different energies in the range 22 keV and 1333 keV. The photon energies were obtained from seven different radioactive sources (Na-22,Co- 60, Am-24(1) (109)cd , (137)cs, Eu-152 and Ba-133) . The Si(Li) and NaI(Tl) detectors were separately used taking into account of energy-efficient regions to counting process at narrow-beam transmission geometry. In addition, all these parameters were computed at the 15 keV-15 MeV wide energy range, theoretically. In order to make a satisfying assessment about radiation shielding capabilities of AISI 302, 304, 321 and 430 alloys, all calculations were also made for ordinary, steel-scrap and steel-magnetite concretes (Fe-based steel concretes) that are most commonly used as shielding material in many nuclear applications. According to the results obtained, it was observed that the radiation shielding performances of AISI 300 austenitic stainless steel series with containing Ni are superior to that of both AISI 430 ferritic stainless steel and examined concretes., Bayburt University Scientific Research Projects Coordination Department [2018/01-69001-04], This research has been supported by Bayburt University Scientific Research Projects Coordination Department. Project Number: 2018/01-69001-04.

In this study it has been investigated the effect of gamma and neutron radiation on the electron momentum distribution (Compton profile) of the Multiwall Carbon Nanotube (MWCNT) using a Compton spectrometer with an annular 241Am radioactive source. The samples were irradiated with 10 kGy (kGy) gamma rays, thermal and fast neutrons. The photons emitted from the 241Am source were incident on the irradiated samples and the scattered photons from the samples were recorded using HPGe detector. Scanning Electron Microscopy (SEM) and Transmission Electron Microscopy (TEM) results are also given to show the changes at the atomic structure of the MWCNT. The results clearly show that the Compton profile of multi-walled carbon nanotubes has changed with gamma and neutron irradiation. These changes are attributed to the delocalization of the electrons in the sample (in real space) which is clearly seen in the increased height of Compton profile of MWCNT at low momentum range (localization in momentum space) during sample’s irradiation.

A new series of heavy metal oxide (HMO) glasses in the 10WO3-xMoO3-(90-x)TeO2, x = 10–40 mol% system have been developed using melt quenching technique to investigate their potentiality for radiation shielding applications. Gamma attenuation parameters such as mass attenuation coefficient (MAC) and half value layer (HVL) were measured in a good transmission geometry. The MACs were then used to calculate effective atomic number (Zeff). A HPGe detector was used to detect gamma rays of energies 81 keV, 276 keV, 303 keV, 356 keV and 384 keV emitted through a 133Ba radioactive source. MACs, HVLs and Zeffs were also calculated in a continuous energy region. One more relevant gamma shielding parameter, the buildup factor was also estimated for the glass samples in a continuous energy region at different penetration depths. Moreover, the developed glasses were investigated with respect to their shielding ability against fast neutron and charged particle radiation in the light of the calculated ranges for electron, proton and alpha particle interactions and macroscopic removal cross sections for fast neutrons. The results were compared with ordinary concrete and a lead (Pb) based glass sample wherever possible. It was concluded that the 10WO3-10MoO3-80TeO2 glass sample showed excellent shielding properties when compared to other glasses as well as concrete and Pb-based shielding glass.

In this study, we aimed to determinate of the photon and particle radiation interaction parameters of six different perovskites to help use perovskite materials in radiation applications. The parameters that are aimed to be investigated are MAC, HVL, MFP, Zeff, Neff, Ceff and EBF for photons, range values for charged particles, and FNRCS values for neutrons. The photon-interaction parameters the FNRCS values of the perovskites were calculated using Phy-X/PSD software in the energy range of 1 keV–100 GeV for photons and at 4.5 MeV energy for neutrons, respectively. Moreover, the range values of the perovskites were calculated using SRIM Monte Carlo software (for H+ and He++ particles) and ESTAR NIST software (for electrons) in the energy range from 0.01 MeV to 20 MeV. In order to make a notable assessment about the radiation interaction possibilities of the perovskites, the results obtained were compared with some standard shielding materials. According to the results obtained for all radiation types examined, it was determined that all calculated parameters were strongly dependent on both the type and energy of the radiation and the type of material. Additionally, it was observed that the order of preference of the examined materials as armor material in radiation applications varies according to the radiation type and energy. Consequently, it was determined that while the most suitable material in terms of photon shielding is P6 (Cs2SnI6) inorganic perovskite among the perovskites examined, this sample is not suitable material for neutron shielding applications.

In this work, ultrahigh molecular weight polyethylene reinforced with Tungsten trioxide WO3 composite was synthesized. The SEM explores the morphological characteristics for current samples, and the obtained results show the homogenous disperse for WO3 particles in the UHMWPE matrix with little tendency of agglomerations. EDX profiles appear the increment of W (Tungsten) peak with increasing WO3 concentrations. While the XRD results show the same structure phase for all samples, but the addition of WO3 shows slight shifting in prominent peaks at 21 degrees and 24 degrees. The Raman spectrum exhibits four additional peaks for a sample containing 5 mol% of WO3 that affirms the existence of WO3 in this sample only. On another side, the 241Am/Be source, GEANT4, and Phy-X program were utilized to determine the neutron shielding features. Furthermore, the proton shielding properties were evaluated. Lastly, it was concluded that the prepared polyethylene could be utilized for neutron shielding applications.

In this study, it has been focused on the investigation of particle-shielding performances of precipitation-hardening stainless steels (PH-SSs). In line with this focus, the stopping powers and ranges values of four different PH-SSs (15−5PH, 15−7PH, 17−4PH and 17−7PH) for energetic charged particles (proton, electron and alpha particles) were carried out in the kinetic energy range of 0.01-20 MeV. In addition, the fast neutron removal cross-section values of PH-SSs examined for neutrons were calculated at 4.5 MeV. In order to achieve a remarkable conclusion about the particle-absorbing capacities of the PH-SSs investigated, all calculations were also performed for some concretes (steel-magnetite, steel-scrap and ordinary concretes) used as shielding materials in nuclear applications. The results obtained were comparatively presented as a function of kinetic energy of particles. In addition, the results obtained were evaluated in terms of both types of particle and phase structures of materials examined. According to the results obtained, it was observed that the all investigated parameters are independent of phase structures of PH-SSs, that the all calculated parameters for PH-SSs examined are very close to each other, and that the particle-shielding performances of PH-SSs under examination are better than comparison concretes. As a result of the data obtained from this study, it was observed that PH-SSs can be used as an alternative material in areas where particle radiation safety is required because of their superior characteristic and shielding properties.

Halloysite clay is a mineral found in natural and it has many applications in chemistry (for catalytic and extraction) and also in the medical field (for drugs delivery), so it is important to study the shielding properties of natural and modified nanotube Halloysite. The mass attenuation coefficient was simulated for natural Halloysite clay mineral and four others modified halloysite nanotubes using MCNP 5 code for incident gamma ray energies between 0.015 and 15 MeV. The mass attenuation coefficient was also calculated using the XCOM database for studied samples in the same energy range. The results obtained by the MCNP simulation were close to those obtained by XCOM calculation. Moreover, other shielding properties that described the interaction of incident gamma rays with Halloysite composites, such as the HVL, MFP, Zeff, and Neff were calculated using the simulated μm for gamma rays between 0.015 and 15 MeV.

In the present work, we developed three new high temperature resistant heavy concretes as novel radiation shielding materials. For this purpose, chrome ore (FeCr2O4), hematite (Fe2O3), titanium oxide (TiO2), aluminum oxide (Al2O3), hematite [FeO(OH) nH(2)O], siderite (FeCO3), barite (BaSO4), nickel oxide (NiO) materials and alumina cement were used. Mass combination ratios of components and total macroscopic cross sections (scattering, absorption, capture, fission) of the samples were calculated by using GEANT4 code. The resistances of the prepared samples were evaluated in terms of compression strength after exposure at the 1000 degrees C temperature. Neutron equivalent dose rate measurements were carried out by using 4.5 MeV Am-241-Be neutron source and BF3 detector. All results were compared with normal weight concrete and paraffin. The results of neutron dose indicate that neutron absorption ability of the new heavy concretes is higher than normal weight concrete and paraffin. In addition to neutron measurements, different gamma-ray shielding parameters such as mass attenuation coefficient (MAC), effective atom numbers (Z(eff)), half value layer (HVL) and mean free path (MFP) have been calculated using WinXCOM software in order to investigate the effectiveness of using the prepared concretes as a radiation shielding materials. Gamma-ray results were compared with concretes and Pb-based glass., Ataturk University [2016/FM71]; Agri Ibrahim Cecen University [MYO.18.001], This work is financially supported by Ataturk University with Grant No. 2016/FM71 and Agri Ibrahim Cecen University with Grant no. MYO.18.001.

In this study, 12 different concentrations of shielding materials were developed and produced. They were covered with high temperature resistant (1500 degrees C) sodium silicate sealing paste. Epoxy resin was produced by adding different percentages of additive materials such as chromium oxide (Cr2O3), lithium (LiF), and nickel oxide (NiO). The GEANT4 and FLUKA codes of the Monte Carlo simulation toolkit were used to determine the mixing ratios. The total macroscopic cross-sections, effective removal cross-sections, mean free path, half value layer, and transmission neutron number were determined for fast neutron radiation using GEANT4 and FLUKA simulation codes. The mass attenuation coefficient, the effective atomic number and half-value layer (HVL) of the samples were calculated using Phy-X/PSD software. The absorbed dose was measured. In this study, an Am-241-Be neutron source with 74 GBq activity and average neutron energy of approximately 4.5 MeV and a BF3 gas detector were used. Both simulation and experimental measurements were compared with paraffin and conventional concrete. The new composite shielding material absorbed radiation much better than the reference materials. This new radiation shielding composite material can be used in nuclear medicine, transport and storage of radioactive waste, nuclear power plants, and as a shielding material for neutron and gamma radiation., Project of Agri Ibrahim Cecen University Scientific Research Projects [MYO 18.001-19.001], This study was supported by the Project of Agri Ibrahim Cecen University Scientific Research Projects (MYO 18.001-19.001).

In this study, gamma ray and neutrons shielding features were evaluated for La+3 co-doped zinc borotellurite glasses with chemical formula {[(TeO2)0.70(B2O3)0.30]0.7(ZnO)0.30}1-x(La2O3)x: 0.01≤ x ≤ 0.05 mol%. Firstly, the mass and linear attenuation coefficients (MAC, LAC) for glasses were calculated via Photon Shielding and Dosimetry (PSD) software (Phy-X/PSD) in the energy range of 0.015–15 MeV. Depending on MAC and LAC, effective shielding parameters: Half value layer and mean free path (HVL, MFP), effective electron density, atomic number, and conductivity (Neff, Zeff, Ceff), exposure and energy absorption buildup factors (EBF, EABF) have been evaluated. In addition, effective fast neutron removal cross section (FNRCS) for the studied glasses have been calculated. The obtained data were compared with those of some commercial glasses and concrete. Results reveal that HVL for all samples can be arranged in the order TBZL1>TBZL2>TBZL3>TBZL4>TBZL5. The HVL, TVL and MFP values of TBZL5 glass are 2.988 cm, 9.927 cm, and 4.311 cm, respectively. TBZL5 glass has the highest Ceff values and TBZL1 glass has the lowest Ceff values. EBF values change range from 1 to 4 at 1 MFP and from 1-1010 at 40 MFP value. Therefore, it can be among the alternative materials that can be preferred in radiation application areas.

In this study, a comprehensive study on photon and fast neutron interactions was conducted to determine the possible uses of four different copper-based Nickel–Silver (NS) alloys as alternative protective materials. For this purpose, photon interaction parameters (μ, μm, X1/2, σT, Zeff, Neff, Ceff) of NS alloys which have Cu65Ni18Zn17, Cu62Ni18Zn20, Cu64Ni12Zn24 and Cu55Ni18Zn27 compositions were presented experimentally in the photon energy range of 30–1333 keV using ideal transmission geometry conditions. In order to compare experimental and theoretical results and to a comprehensive evaluation in wide energy range (0.015–15 MeV), these parameters were also calculated using WinXCOM based Phy-X/PSD software. It was found that there is a good agreement between experimental and theoretical results, and that the maximum relative difference is approximately 1.2%. In order to test the suitability of the radiation shielding capacities of the studied alloys for nuclear applications, all parameters were also calculated theoretically for ordinary concrete (OC), basalt (BM) and steel magnetite (SM) concretes. Furthermore, the exposure build-up factors for the alloys and concretes were calculated using G-P fitting method at photon energy range from 0.015 to 15 MeV up to 40 mean free path (MFP) penetration depth. Moreover, the fast neutron removal cross-sections of the materials were determined using Phy-X/PSD software. According to the data obtained, it has been observed that the shielding capacities of NS alloys are far superior to selected concretes for both photon radiation and fast neutrons. It was revealed in this study that NS alloys may be an alternative shielding material candidate due to their high density, high melting points (about 1100 °C) and good mechanical strength.

In this work, five samples of high-density polyethylene have been made by varying bismuth oxide (Bi2O3) concentration 0.5, 1.0, 1.5 and 2.0 wt%. Scanning electron microscopic (SEM) has been used to analysis of the samples to point out the changes in the surface morphology. Energy Dispersive X-ray (EDX) has been performed for evaluating chemical composition of the prepared samples. X-ray diffraction (XRD) spectra of the pure Bi2O3, pure high-density polyethylene (HDPE) and HDPE with different amount of Bi2O3 have been investigated. Additionally, the Raman spectroscopy of all synthesized polymer matrix were measured to explore the different molecular groups. Finally, the mass attenuation coefficients μ/ρ for the samples have been measured using narrow beam of gamma-ray at eight energies between from 30.8 to 383.8 keV. The effect of the photon energy and the addition of Bi2O3 on the gamma-ray shielding ability of the prepared sample have been discussed. In conclusion, the prepared samples showed good attenuation properties.

In the present work, we fabricated a series of six glasses to be utilized in the field of radiation shielding application. Glasses have been synthesized using a melt-quenching ordinary technique. In this work, we investigated the structural properties of these glasses using Raman spectroscopy. Moreover, optical properties have been studied in the present work. The radiation attenuation ability for the present samples was also investigated and measured using transmission geometry between 81 and 964.1 keV. The mass attenuation coefficient was measured and the results were validated by the WinXcom program. Also, radiation protection efficiency (RPE) was evaluated and discussed in terms of photon energy and Bi2O3 concentration. From RPE curve, we found that the fabricated glasses can be used as effective shielding materials especially for the low energies (81–383 keV). The half value layer also was calculated and the results of this parameter showed that S6 (contains 60 mol% of Bi2O3) has the higher probability of the interaction with gamma photons, leading to less number of photons transmitted this sample and thus better photon attenuator.

In order to investigate new candidate glasses for gamma shielding application, we synthesized a number of glasses with composition of (50+x)Bi2O3-(30-x)B2O3-10ZnO-5BaO-5Li2O where x = 10, 15 and 20, all in mol%. We used the conventional melt-quenching-annealing technique with melting temperature at 975 °C and 300 °C for 30 min and 5 h, respectively. Density and other important physical properties have been measured and calculated using related methods and formulas. Moreover, X-ray diffraction have been utilized for all samples to explore the structure of these glasses, the XRD profile have been recorded between 10° to 80° for all samples, while the functional groups of the elements evolved in these glasses have been studied using FTIR with the range of 4000–400 cm−1. Additionally, optical absorption for the synthesized glasses have been measured in the range of 200–800 nm to investigate the cut-off wavelength and optical band gap. Besides, the mass attenuation coefficient values of the present glasses have been estimated through WinXCom software as well as MCNPX computer code and the obtained results were used to determine the effective atomic number (Zeff), the half value layer (HVL) and the mean free path (MFP). From the derived results, it was found that S3 is the superior glass sample in terms of shielding performance on account of larger Zeff values and lower MFP/HVL values among the investigated glasses. The present glasses indicate potentiality to be evaluated as shielding absorbers and for an improved shielding effectiveness of the Bi2O3-B2O3-ZnO-BaO-Li2O glasses, a large Bi2O3 concentration would be required.

Authors have investigated a series of newly developed Pr3þ doped 10ZnF2 – (5-y) Al2 O3–30LiF – 55B2O3 – yPr6011 (y ¼0–0.5 mol %) glasses synthesized through melt quench technique with an objective to analyse its optical, structural, thermal, morphological, mechanical and radiation shielding capabilities. The structural evolution was systematically investigated by density, X-ray diffraction (XRD), Fourier-transform infrared spectroscopy (FTIR) and Energy dispersive analysis (EDAX). The overlaid absorbance (3H4→1D2) and emission (1D2→3H4) bands of 0.05 mol% of Pr3þ-doped ZAlFB glass indicated the cross-relaxation channel for energy transfer between Rare-Earth (RE) ions. The ZAlFB:Pr3þ glasses excited at 445 nm exhibited intense reddish orange emission with 1D2→3H4 transition at 605 nm. This proves its suitability in reddish orange LEDs. Luminescence quenching was observed past 0.05 mol% of Pr3þconcentration in ZAlFB glass. The 1D2→3H4 transition exhibited maximum branching ratio (βr ¼0.8601) in Pr0.5 glass. All the Pr3þ doped glasses revealed strong thermal stability with ΔT > 100 �C. Pr0.5 glass sample showed maximum thermal strength and mechanical hardness (Vicker’s Microhardness tester). Hence, compromise over the hardness or the optical properties of the samples were studied in the ZAlFB:Pr3þ glasses. Radiation shielding properties indicated 0.5 mol% Pr3þ doped sample as a superior gamma rays shielder among the investigated ZnF2–Al2O3–LiF–B2O3–Pr6O11 glass system with favourable luminescent and radiation shielding properties, these Pr3þ doped ZAlFB glasses can be used as photonic/lasing devices in radiation zones as well.

A user friendly online Photon Shielding and Dosimetry (PSD) software available at https://phy-x.net/PSD has been developed for calculation of parameters relevant to shielding and dosimetry. These parameters include linear and mass attenuation coefficients (LAC, MAC), half and tenth value layers (HVL, TVL), mean free path (MFP), effective atomic number and electron density (Zeff, Neff), effective conductivity (Ceff) energy absorption and exposure buildup factors (EABF, EBF). The software can generate data on shielding parameters in the continuous energy region (1 keV-100 GeV). Also, some well-known radioactive sources (22Na, 55Fe, 60Co, 109Cd, 131I, 133Ba, 137Cs, 152Eu and 241Am) along with their energies and some characteristic (K-shell) X-ray energies of Cu, Rb, Mo, Ag, Ba and Tb elements are available in the software and can be selected by the user. Thus, one can obtain the shielding parameters at photon energies available for the predefined energies. Moreover, another parameter relevant to shielding i.e. the fast neutron removal cross section (FNRCS) can be calculated for a compound or a mixture using this software. The software is freely available online after having registered to the Phy-X platform.

WOS: 000390072000017, The K X-ray intensity ratios of some elements (Z & $2gt;70) were measured by using an Energy Dispersive X-Ray Fluorescence Spectrometer, which has an intense radioisotope source and an HPGe detector. The experimental results had uncertainties about 4% and were in good agreement with theoretical results of Scofield. In order to obtain more reliable results, the experiments should be carried out with synchrotron radiation having a more intense and monochromatic radiation source and detectors with better resolutions.

In this study, it has been measured the Compton Profile of the CO2 gas at different pressures by using a Compton Profile Spectrometer with an annular Am-241 radioactive source and a HPGe detector. CO2 gas molecules sealed in a gas chamber at different pressures. The gas pressure had been set by using an analog manometer before the measurements. The γ-rays emitted from source was incident into the gas from a hostaphan window. The detector recorded the scattered photons from molecules. To obtain correct Compton Profile values, the raw data were corrected for some effects; i.e. scattering from the gas chamber’s walls, absorption effects of windows on gas chamber and detector, and multiple scattering corrections. A Matlab Code has been used for all calculations. The results clearly demonstrate the valance electronic structure of the materials is highly depending on the pressure. According to our experimental results, when the pressure in the gas chamber increase the Compton Profiles of valance electrons chang...

In this work, manganese (II, III) oxide, (Mn3O4) doped zinc soda lime silica glasses have been synthesized using a conventional melt-quenching process and followed by control heat treatment process. The crystal phase composition and optical properties of α-Zn2SiO4:Mn3O4 based glass-ceramics are comprehensively studied. The physical properties and crystal growth of α-Zn2SiO4 phase were measured by density analysis, linear shrinkage, X-ray diffraction (XRD) and Fourier transform infrared reflection (FTIR) spectroscopy. From the measurement, the average density and linear shrinkage of α-Zn2SiO4:Mn3O4 based glass-ceramics increased with increasing heat treatment temperature. Besides, the presence of Zn–O–Si bands indicates the formation of α-Zn2SiO4 crystal phase and causing the decrement of energy band gap. The photoluminescence spectra of Mn2+ ions exhibit emission transitions of 4T1(G)–6A1(S) and show a prominent green emission colors of α-Zn2SiO4 phase at 524 nm. Keywords: α-Zn2SiO4, Glass-ceramic, Phosphor, Crystal growth, Optical properties

Physical, mechanical and radiation shielding properties of ZnO-MoO3-TeO2 glasses were studied. Density, molar volume, oxygen molar volume, oxygen packing density were evaluated for the interpretation of physical properties. Mechanical properties were determined through Vickers hardness measurements. The shielding estimation was accomplished by studying linear attenuation coefficient (LACμ), mass attenuation coefficient (MAC), effective atomic number (Zeff), effective electron density (Neff), mean free path (mfp), exposure buildup factor (EBF) and energy absorption buildup factor (EABF). The glasses were irradiated by 133Ba radioactive source emitting gamma rays in the range of 79.61 keV to 383.80 keV to determine LACs and MACs. mfp values were calculated for present glasses and compared with various concretes and a commercial window glass in energy region 81–384 keV. The glass structure became stronger and mechanical properties showed an increment with increasing MoO3 content. Synthesized glasses have lower mfp values indicating better shielding properties than concretes and window glass.

Authors report the change in lead fluoroborate glass properties with change in RE2O3 (RE = Eu, Sm, Nd) chemical composition. The RE2O3 exhibited improvement in the radiation shielding properties of the glass samples. The gamma rays shielding capabilities of the samples were studied using the WinXcom software (for Eu2O3, Sm2O3 doped glasses) and Monte Carlo simulation (for Nd2O3 doped glasses). The results exhibited that the mass attenuation coefficient (μm), effective atomic number (Zeff), and half value layer (HVL) depends on the concentration of RE2O3 and addition of the same significantly increased the shielding capabilities of the glass samples against gamma rays. The increase in photon energy revealed the decrease in radiation shielding properties. The reported density and radiation attenuation properties of RE2O3 doped lead fluoroborate glasses are predominant in radiation shielding applications which will be useful in high strength structures. Of all the glass samples 2.5 mol% of Eu2O3, Sm2O3 and Nd2O3 doped glasses showed enhanced shielding properties.

In the present work, seven glass samples have been prepared utilizing melt-quenching method with composition of 40B2O3-10SiO2-10Al2O3-30ZnO-10 (Li2O/Na2O/K2O/MgO/CaO/SrO/BaO) all in mol%. Scanning electron microscope (SEM) and Energy-dispersive X-ray spectroscopy (EDX) have characterized for H3 (K2O) and H7 (BaO), to examine the structural properties. X-ray Photoelectron Spectroscopy (XPS) has shown that the boron (B) element composition is highest after oxygen elements in all the glasses. It has been also observed that incorporation of potassium (K) and strontium (Sr) elements are maximum compared to the other doped elements into the glass. Further, the photon shielding for H1-H7 samples were also studied. We calculated the mass attenuation coefficients (μ/ρ) for the present samples at some energies between 0.015 and 10 MeV. The results revealed that H7 (BaO) sample owns the highest μ/ρ values followed by H6 (SrO) while H1 (Li2O) has the lowest μ/ρ. Moreover, H7 and H6 samples have higher effective atomic number than the rest of glasses. H7 sample has excellent shielding properties when compared with the other glasses. We found that the composition of the sample affects the attenuation of the glasses and high attenuation can be achieved when we used heavy metal oxides (such as BaO). Keywords: X-ray photoelectron spectroscopy, Borosilicate glasses, Radiation, Attenuation