Spectroscopic and radiation shielding features of Nemrut, Pasinler, Sarıkamıs and Ikizdere obsidians in Turkey: Experimental and theoretical study

Aygün, Zeynep; Yarbaşı, Necmi; Aygun, M.

doi:10.1016/j.ceramint.2021.08.330

Cited by 18 publications

(12 citation statements)

References 46 publications

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“…Above 5 MeV, the Pair production process starts and MAC values increased with increasing energy [26]. Additionally, we compared the MAC values of BG with those of other reported shielding materials, ordinary concrete (OC), green clay (GC), red clay (RC), pumice, Nemrut obsidian (NO), marble dust (MD) [27][28][29][30] (Fig. 2).…”

Section: Resultsmentioning

confidence: 99%

A comprehensive analysis on radiation shielding characteristics of borogypsum (boron waste) by Phy-X/PSD code

Aygun

Aygün

2023

Rev. Mex. Fís.

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In the present study, radiation shielding characteristics of the borogypsum, which is a waste generated during the boric acid production in Turkey, was analyzed. For this purpose, we used recently developed Phy-X/PSD software, which is provided to calculate shielding parameters such as mass attenuation coefficient, linear attenuation coefficient, half-value layer, tenth-value layer, effective atomic number, total atomic cross section, total electronic cross section, effective conductivity, effective electron number, buildup factors and fast neutron removal cross section in a wide photon energy range. Additionally, mass attenuation coefficients of borogypsum were compared with those of other radiation shielding materials (ordinary concrete, obsidian, pumice, clay) in order to give a significant evaluation about the radiation shielding capability of borogypsum. Half value layer and fast neutron removal cross section values are also evaluated by other materials. It is noticed that borogypsum has higher shielding potential than other reported shielding materials.

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Section: Resultsmentioning

confidence: 99%

A comprehensive analysis on radiation shielding characteristics of borogypsum (boron waste) by Phy-X/PSD code

Aygun

Aygün

2023

Rev. Mex. Fís.

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“…Equivalent atomic number (Z eq ) is an effective parameter in determining energy absorption and absorbed dose. While all partial photon interactions are effective in the determination of Z ef f , Z eq is calculated only by Compton scattering [42]. The calculated Z eq of the alloys are given in Fig.…”

Section: Z Aygunmentioning

confidence: 99%

Study on Radiation Shielding Characteristics of Refractory High Entropy Alloys by EpiXS Code

Aygün

2023

Acta Phys. Pol. A

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Refractory high entropy alloys constituted of refractory alloying elements, such as W, Zr, Nb, Ti, Mo, Ta, and Hf, are of great interest due to their widespread use in areas such as the defense, aerospace, and nuclear power generation industries. Refractory high entropy alloys are one of the subgroups of high entropy alloys and are evaluated as great candidates for replacements of superalloys commonly used at high temperatures due to their good mechanical properties and corrosion and oxidation resistance at high temperatures. The motivation for performing this study is that there is currently no comprehensive analysis of the radiation shielding abilities of this new type of high entropy alloys. The purpose of the study was to evaluate the radiation attenuation parameters such as mass and linear attenuation coefficients, half value layer, mean free path, effective atomic number, and buildup factors of the refractory high entropy alloys, Al0.5Mo0.5NbTa0.5TiZr, Al0.25NbTaTiZr, HfMoScTaZr, Nb40Ti25Al15V10Ta5Hf3W2, NbCrMo0.5Ta0.5TiZr, Ti2VNbMoZr, and W23Mo23V17Cr8Ta7Fe22 by using EpiXS software. The mass attenuation coefficients of the alloys were also calculated by XCOM, a well-known code, to see the consistency of the obtained values. It was concluded that HfMoScTaZr and W23Mo23V17Cr8Ta7Fe22 have more shielding features, while Ti2VNbMoZr has the lowest shielding ability among the alloys.

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“…The issue of protection from ionizing radiation is very important in the world. Researchers working on this subject are doing improvement studies against radiation protection on some materials [4,[22][23][24][25]. For example, [22] investigated the shielding properties of some low-temperature superconducting brazing alloys.…”

Section: Calcium Carbonate and Radiation Shieldingmentioning

confidence: 99%

Nükleer Reaktörlerde Nanoparçacık Olarak Kalsiyum Karbonat Kullanımının Araştırılması

Uzun

Genç

Acır

2023

Konya Journal of Engineering Sciences

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In this study, calcium carbonate (CaCO3) was considered as nanoparticle. In the first part of the study, half-value layer (HVL) and mean free path (MFP) values, which are radiation shielding parameters, were investigated in determined energy ranges by Phy-X open access software. At increasing energy levels, the HVL value reached approximately 10 cm, while the MFP value reached approximately 17 cm. In the second part of the study, the reactor core geometry was modeled with the MCNP code and then the relative power distribution values were determined. COBRA code input was prepared with the determined relative power distribution values and thermal analyzes were made. These analyzes were performed for three different nanoparticle ratios. As a result of the analysis, the temperature value at the end of the channel was 613 K when only water was used as a coolant, while the temperature value at the end of the channel was 611.19 K when 0.03% nanoparticles were used. Although the coolant temperature increased with the nanoparticle ratio, it was observed that the temperature decreased when only water was used.

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Spectroscopic and radiation shielding features of Nemrut, Pasinler, Sarıkamıs and Ikizdere obsidians in Turkey: Experimental and theoretical study

Cited by 18 publications

References 46 publications

A comprehensive analysis on radiation shielding characteristics of borogypsum (boron waste) by Phy-X/PSD code

A comprehensive analysis on radiation shielding characteristics of borogypsum (boron waste) by Phy-X/PSD code

Study on Radiation Shielding Characteristics of Refractory High Entropy Alloys by EpiXS Code

Nükleer Reaktörlerde Nanoparçacık Olarak Kalsiyum Karbonat Kullanımının Araştırılması

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