Şakar, E.; Özpolat, Ö.F.; Alım, B.; Alsaif, Norah A.M.; Rammah, Y.S.

The main high energy radiation-matter interaction parameters of the 30B2O3-(70-x)TeO2-xBi2O3, where x = 40, 50, 60 and 70 mol% (BTB) glasses have been studied in the wide energy range. The theoretical calculations were made for some special X and γ-ray energies emitted from Fe (55), Am (241), Cs (137) and Co (60) radioactive sources for photon energies in the range of 15 keV - 15 MeV. All evaluated radiation shielding parameters were compared with some selected concretes (Ordinary concrete (OC), Hematite-Serpenite (HS) and Basalt-Magnetide (BM)), and glasses (Te and Pb based). The BTB- glasses have higher mass attenuation coefficient (MAC) values than other glasses (Te and Pb based) and concretes (OC, HS, and BM). The half value layer (HVL) of the investigated BTB-glasses has the following trend: OC > HS > BM > Te-Glass > Pb-glass > BTB40 > BTB50 > BTB60 > BTB70. In terms of mean free path (MFP), the BTB70 coded glass has the lowest MFP values due to the highest Bi2O3 content. In terms of the Zeff values of BTB coded glasses vary between 70 and 75 at the lowest energy level. The effective atomic number (Zeff) values in this energy region were 48.974 and 63.102 for Te and Pb glasses, respectively, and 13,339, 15.520 and 15.894 for OC, HS and BM concretes. The BTB-coded glasses have lower exposure buildup factor (EBF) than all other glass and concrete up to 3 MeV photon energies. The energy absorption buildup factor (EABF) values range from 1 to 4.2 for all samples at 1 MFP and at 40 MFP values, it reaches 108 for BTB coded glasses and 1010 for Te-based glass. Results confirmed that BTB- glasses, especially BTB70 glass sample can be used in applications requiring radiation safety.

AtıfScopus17·WoS16·OpenAlex17

İncele

Özpolat, Ö.F.; Alım, B.; Şakar, E.; Büyükyıldız, M.; Kurudirek, M.

The purpose of the present work is robust calculation of effective atomic numbers (Zeffs) 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 Zeff for photon interaction were compared with those calculated through Mayneord’s formula, which suggests a single-valued Zeff for any material for low-energy photons for which photoelectric absorption is the dominant interaction process. The single-valued Zeff was found to agree well with that obtained by other methods, in the low-energy region. In addition, Zeff 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 Zeff 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 Zeff between Phy-X/ZeXTRa and literature values was found to be 2% < RD < 11%, at low photon energies (1–100 keV), while it was less than 1% at energies higher than 100 keV. Highest Zeff values were observed at low photon energies, where photoelectric absorption dominates photon interaction. For electrons, corresponding RD(%) values in Zeff were found to be in the range 0.4 ≤ RD(%) ≤ 1.7, while for heavy charged particle interactions it was 2.4 ≤ RD(%) ≤ 4.2 for total proton interaction and 0 ≤ RD(%) ≤ 8 for total alpha particle interaction. In view of the importance of Zeff for identifying and differentiating tissues in diagnostic imaging as well as for estimating accurate dose in radiotherapy and particle-beam therapy, Phy-X/ZeXTRa could be used for fast and accurate calculation of Zeff in a wide energy range for both photon and charged particle (electrons, protons, alpha particles and C ions) interactions.

AtıfScopus88·WoS77·OpenAlex94

İncele

Alım, Bünyamin; Şakar, E.; Baltakesmez, Ali; Han, İbrahim; Sayyed, M.I.; Demir, Lütfü

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 (22Na, 60Co, 241Am, 109Cd, 137Cs, 152Eu and 133Ba). 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.

AtıfScopus52·WoS46·OpenAlex57

İncele

Rammah, Y.S.; Özpolat, Ö.F.; Alım, B.; Şakar, E.; El-Mallawany, R.; El-Agawany, F.I.

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.

AtıfScopus48·WoS47

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