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Alloying effect on K shell X-ray fluorescence cross-sections and yields in Ti-Ni based shape memory alloys
(Elsevier Science Bv, 2018) Alim, Bunyamin; Han, Ibrahim; Demir, Lutfu
K shell X-ray fluorescence cross-sections (sigma(K alpha), sigma(K beta) and sigma(K)), and K shell fluorescence yields (omega(K)) of Ti, Ni both in pure metals and in different alloy compositions (TixNi1-x; x = 0.3, 0.4, 0.5, 0.6, 0.7) were measured by using energy dispersive X-ray fluorescence (EDXRF) technique. The samples were excited by 22.69 keV X-rays from a 10 mCi Cd-109 radioactive point source and K X rays emitted by samples were counted by a high resolution Si(Li) solid-state detector coupled to a 4 K multichannel analyzer (MCA). The alloying effects on the X-ray fluorescence (XRF) parameters of Ti-Ni shape memory alloys (SMAs) were investigated. It is clearly observed that alloying effect causes to change in K shell XRF parameter values in Ti-Ni based SMAs for different compositions of x. Also, the present investigation makes it possible to perform reliable interpretation of experimental sigma(K alpha), sigma(K beta) and omega(K) values for Ti and Ni in SMAs and can also provide quantitative information about the changes of K shell X-ray fluorescence cross sections and fluorescence yields of these metals with alloy composition. (c) 2017 The Egyptian Society of Radiation Sciences and Applications. Production and hosting by Elsevier B.V.
A comprehensive study on radiation shielding characteristics of Tin-Silver, Manganin-R, Hastelloy-B, Hastelloy-X and Dilver-P alloys
(Springer Heidelberg, 2020) Alim, Bunyamin
In this study, it is aimed to investigate alloys that can replace lead and its derivatives in terms of radiation shielding. A new alternative shielding material must have optimum properties that should be present in a protective material. For this purpose, this study focused on the determination of the radiation-shielding characteristics of five different alloys named Tin-Silver, Manganin-R, Hastelloy-B, Hastelloy-X and Dilver-P. The photon interaction parameters (mu, mu(m), lambda, X-1/2, sigma(T), sigma(e), Z(eff), N-eff, sigma(eff) and RPE) that give significant information about the radiation shielding capacities of the materials were calculated for the alloys in the energy range from 30 to 1333 keV. The narrow-beam transmission geometry was used to determine these parameters accurately and was adjusted such that the error rate is minimized. The present samples were irradiated with photons of nineteen different photon energies emitted from seven different radionuclides (Am-241, Ba-133, Cd-109, Eu-152, Na-22, Cs-137 and Co-60). Photon intensities were measured by using two different detectors (Si(Li) and NaI(Tl)) for convenient photon energy regions. Then, these parameters were also calculated theoretically using Phy-X/PSD software in order to compare the experimental and theoretical results. Furthermore, the R-inc/total, Z(eq), G-P fitting coefficients (a, b, c, d and X-K) and exposure build-up factors (beta) for the alloys were calculated using Phy-X/PSD software at photon energy range from 0.015 to 15 MeV. In order to make a significant comparison about the shielding capacities of investigated alloys, the mu(m) values obtained for the alloys were compared with corresponding values of Pb metal, RS 253 glass and Cupero-Nickel alloy. Consequently, the descending order of MAC values in the all surveyed energy region was obtained as Tin-Silver > Manganin-R > Hastelloy-B > Hastelloy-X > Dilver-P. In the low energy region, it was found that the all present alloys have better shielding performances than RS 253 glass and Cupero-Nickel alloy. The experimental results also revealed that the Tin-Silver alloy has 25% better shielding performance than Pb metal in the energy range of 30-88 keV. Finally, it was concluded that Manganin-R alloy could be considered as the most ideal shielding material in the entire photon energies studied along with its other superior features (high density (10.22 g cm(-3)), high melting point (2500-2600 degrees C), high tensile strength (560-1150 MPa), high modulus of elasticity (320 GPa) and high specific heat (305 J K-1 kg(-1)) although the Tin-Silver alloy had the highest mu(m) values among the examined alloys.
Determination of radioprotective and genotoxic properties of sulfamide derivatives
(Walter De Gruyter Gmbh, 2021) Aygun, Bunyamin; Alaylar, Burak; Akincioglu, Akin; Alim, Bunyamin; Kocaman, Ebu Talip; Karadayi, Mehmet; Abu Al-Sayyed, Mohammed Ibrahim
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.
Development of SiO2 based doped with LiF, Cr2O3, CoO4 and B2O3 glasses for gamma and fast neutron shielding
(Walter De Gruyter Gmbh, 2021) Aygun, Bunyamin; Sakar, Erdem; Karabulut, Abdulhalik; Alim, Bunyamin; Sayyed, Mohammed, I; Singh, Vishwanath P.; Yorgun, Nergiz Yildiz
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.
Evaluation of photon interaction parameters of Anti-HIV drugs
(Pergamon-Elsevier Science Ltd, 2022) Akbaba, Ugur; Sakar, Erdem; Sayyed, M. I.; Alim, Bunyamin; Ozpolat, Ozgur Firat
Medical treatment inevitably exposes individuals to radiation, including those taking drugs used to treat and prevent human immunodeficiency virus (HIV). Motivated by this, we investigated the radiation interaction properties of several HIV drugs to determine the interaction parameters, mass attenuation coefficient (MAC), atomic cross section (ACS), electronic cross section (ECS), effective atomic numbers (Z(eff)), and effective electron density (N-eff). We calculated the values using the Phy-X/PSD software in the range of 0.015-15 MeV. Additionally, we calculated the exposure build-up factor (EBF), and energy absorption build-up factor (EABF) values of the drugs up to 40 mean free path (MFP) using the geometric progression (G-P) method. From our findings, we determined that Combivir, with its relatively high heavy element content, had the highest radiation attenuation capacity, whereas the probability of Lopinavir interacting with photons was the lowest compared with the other drugs. The results of the EBF and EABF parameters, including the scattering effects, ordered the drugs opposite to the primary interaction parameters such as MAC, ACS, ECS, and Z(eff). These findings can guide the treatment process of HIV-positive patients and inform HIV prevention practices conducted alongside radiotherapy, as the interaction between radiation and a drug may cause deterioration in the drug's structure.
Evaluation the gamma, charged particle and fast neutron shielding performances of some important AISI-coded stainless steels: Part II
(Pergamon-Elsevier Science Ltd, 2020) Alim, Bunyamin; Sakar, Erdem; Han, Ibrahim; Sayyed, M., I
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.
Experimental investigation of radiation shielding performances of some important AISI-coded stainless steels: Part I
(Pergamon-Elsevier Science Ltd, 2020) Alim, Bunyamin; Sakar, Erdem; Baltakesmez, Ali; Han, Ibrahim; Sayyed, M., I; Demir, Lutfu
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.
An extensive survey on radiation protection features of novel hafnium iron-borophosphate glasses: Experimental and theoretical study
(Pergamon-Elsevier Science Ltd, 2023) Sakar, Erdem; Alim, Bunyamin; Ertap, Huseyin; Karabulut, Mevlut
This study aimed to determine the radiation (photon and particle) attenuation abilities of Hf added iron-borophosphate glasses considered as a candidate host matrix for Pu containing nuclear waste. Experimental absorption parameters were measured using 133Ba radionuclide for photon radiation, and the same parameters were theoretically calculated using Phy-X/PSD. The obtained data were evaluated comparatively for all glasses depending on the Hf and B contents. It has been determined that all of the glasses examined have photon ab-sorption ability at a level that can be a shielding material for nuclear applications. In addition, the interaction cross-sections with particle radiations were computed using SRIM and ESTAR software. When the data obtained are evaluated thoroughly, it can be said that investigated glasses can be used as shielding in areas that require protection from both photon and particle radiation, in addition to being a candidate material for the vitrification of nuclear wastes containing Pu.
Investigation of alloying effects on XRF parameters of 3d transition metals in Permendur49, Kovar and Ti50Co50 alloys
(Taylor & Francis Ltd, 2018) Alim, Bunyamin; Ugurlu, Mine; Han, Ibrahim; Demir, Lutfu
The alloying effects on X-ray fluorescence (XRF) parameters such as K shell fluorescence cross-sections (sigma(K alpha), sigma(K beta) and sigma(K)), K shell average fluorescence yields (omega(K)) and K to L shell vacancy transfer probabilities (eta(KL)) of V, Ti, Fe, Co and Ni 3d transition metals in Permendur49 (Fe49Co49V2), Kovar (Fe54Ni29Co17) and Ti50Co50 alloys have been carried out by X-ray fluorescence studies. K X-ray intensity ratios of these 3d transition metals in both pure form and present alloys have been measured following excitation by 22.69 keV X-rays from a 10 mCi Cd-109 radioactive point source. The characteristic K-X-ray spectra from samples were detected by a high-resolution Si(Li) solid-state detector. The investigated fluorescence parameters of present 3d transition elements in alloys indicate significant differences with respect to the pure metals. Consequently, the observed change of the investigated fluorescence parameters can be attributed to the delocalization and charge transfer phenomena between the 3d elements in alloys. (c) 2017 The Egyptian Society of Radiation Sciences and Applications. Production and hosting by Elsevier B.V.
MoO3 reinforced Ultra high molecular weight PE for neutrons shielding applications
(Pergamon-Elsevier Science Ltd, 2020) Sayyed, M., I; Abdalsalam, Alyaa H.; Taki, Malaa M.; Mhareb, M. H. A.; Alim, Bunyamin; Baltakesmez, Ali; Sakar, Erdem
Structural, Morphological and neutron attenuation properties of ultrahigh molecular weight polyethylene (UHMWPE) reinforced with molybdenum trioxide composite material obtained by solid state mixing of pellets and powder components via hot pressing have been studied. In this work, Ultra high molecular weight poly-ethylene and MoO3 has been utilized with different concentration using a hot compression iron mold. The changes in the microstructure of the prepared polymer and its particulate composites were evaluated by SEM. In order to investigate the quantitative of all elements used in these samples, we utilized Energy-dispersive X-ray spectroscopy (EDX) to present the profiles of synthesized samples which show a clear peaks C (carbon), and Mo (Molybdenum). The X-ray diffraction of all samples was examined to study the modification of the phase and lattice for UHMWPE before and after the addition of molybdenum trioxide (MoO3). Raman analysis was utilized to explore the crystallinity, molecular interactions, phase, polymorphy, and chemical structure. This technique is based on non-destructive interaction between light with the chemical bonds inside a material. The Raman spectrum for the current work presented within the range of 150-1600 cm(-1). In order to understand the neutron shielding performance for the fabricated UHMWPE with different concentrations of MoO3, 241 Am/Be fast neutron source was used to determine the fast neutron radiation equivalent dose rate. The background absorbed dose rate was measured as 0.98 (+/- 0.017) (mu Sv/h). It was seen that the addition of MoO3 into the UHMWPE enhances the neutron shielding. The dose released from the source was absorbed by 7.71 ( +/- 1.3) %, 18.48 (+/- 2.9) %, 22.26 (+/- 2.4) %, 24.07 (+/- 1.8) % and 26.17 (+/- 1.3) % from UHMWPE with 1, 2, 3, 4 and 5% of MoO3 respectively. Additionally, GEANT4 10.02. p01 version was used to calculate total macroscopic crosssections (TMCS) for the MoO3 doped UHMWPE. According to the results obtained from GEANT4, it was observed that the TMCS values of the UHMWPE increase with increment of the mole fraction of the MoO3 in the structure of UHMWPE examined and that the 5.0% MoO3 sample has the best neutron shielding ability.
Phy-X / PSD: Development of a user friendly online software for calculation of parameters relevant to radiation shielding and dosimetry
(Pergamon-Elsevier Science Ltd, 2020) Sakar, Erdem; Ozpolat, Ozgur Firat; Alim, Bunyamin; Sayyed, M. I.; Kurudirek, Murat
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 (Z(eff), N-eff), effective conductivity (C-eff) 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 ( Na-22, Fe-55, Co-60, Cd-109, I-131, Ba-133, Cs-137, Eu-152 and Am-241) 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.
Precipitation-hardening stainless steels: Potential use radiation shielding materials
(Pergamon-Elsevier Science Ltd, 2022) Alim, Bunyamin; Ozpolat, Ozgur Firat; Sakar, Erdem; Han, Ibrahim; Arslan, Ibrahim; Singh, V. P.; Demir, Lutfu
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.
The relationship between the external magnetic field and K X-ray intensity ratios of immiscible MoxAg1-x alloys
(Pergamon-Elsevier Science Ltd, 2019) Ugurlu, Mine; Alim, Bunyamin; Demir, Lutfu
K beta/K alpha intensity ratios were obtained for Molybdenum-Silver alloys produced in different concentration range in different magnetic fields. It was seen that these values without magnetic field were found slight different from each other for pure Mo, pure Ag, alloyed Mo and alloyed Ag. It was determined that K beta/K alpha intensity ratios change slightly by depending on alloying element composition and it was seen that K beta/K alpha intensity ratios of Mo and Ag are in the range of the literature valuesFurthermore, that these values have same direction with the changing of the magnetic field for all alloying composition may take us conclusion which alloys in different concentration may have same magnetic properties.
A study of gamma attenuation property of UHMWPE/Bi2O3 nanocomposites
(Elsevier, 2019) Abdalsalam, Alyaa H.; Sayyed, M., I; Hussein, Thulfiqar Ali; Sakar, Erdem; Mhareb, M. H. A.; Sakar, Betul Ceviz; Alim, Bunyamin
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 Ba-133 radioactive point source.
Study on the radiation attenuation properties of locally available bees-wax as a tissue equivalent bolus material in radiotherapy
(Pergamon-Elsevier Science Ltd, 2020) Islam, Sazirul; Mahmoud, K. A.; Sayyed, M., I; Alim, Bunyamin; Rahman, Md M.; Mollah, A. S.
In radiation therapy field, bolus material is frequently utilized when treating different areas of a patient, like at the ears or nose, and to provide build-up of dose to the skin surface. The bolus material must be cost effective, suitably flexible to conform to the surface of the patient, and most importantly should be tissue equivalent. The main objective of this work was to estimate the photon attenuation properties of locally available bees-wax and to assess the feasibility of using this bees-wax as a bolus material practice for treatment of cancer patient. The mass attenuation coefficient (mu/p) values have been calculated by using MCNP5 simulation code over the wide range of photon energy (0.015-10 MeV). Some related parameters such as the effective atomic number and the mean free path were also calculated to understand the photon attenuation ability of the investigated bolus material. The attenuation properties were also computed for water, tissue and commercial bolus materials for comparison. Evaluation of the results showed that the radiation attenuation properties of locally available bees-wax have a good similarity to water/tissue. Referring to the results of this study, it is proposed that locally available bees-wax is a suitable substance to be used as bolus material practice for treat of cancer patient.
A surveying of photon and particle radiation interaction characteristics of some perovskite materials
(Pergamon-Elsevier Science Ltd, 2021) Sakar, Erdem; Alim, Bunyamin; Ozpolat, Ozgur Firat; Sakar, Betul Ceviz; Baltakesmez, Ali; Akbaba, Ugur
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, Z(eff), N-eff, C-eff 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.

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