High alloyed new stainless steel shielding material for gamma and fast neutron radiation

Aygün, Bünyamin

doi:10.1016/j.net.2019.08.017

Cited by 192 publications

(49 citation statements)

References 10 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…However, highest and lowest MAC values of concrete are 110.10 cm 2 /g and 0.06 cm 2 /g at same energy range, respectively. In the low energy region, the LAC and MAC values are high, but show a rapid downward trend with increasing photon energy (Agar et al, 2019;Aygün, 2020). This finding related to the prominence of the photoelectric absorption process.…”

Section: Resultsmentioning

confidence: 87%

“…Another essential process which is called Compton scattering dominates the middle energy area. The MAC values in this area gradually decrease with the increase in energy (Aygün, 2020).…”

Section: Resultsmentioning

confidence: 94%

“…The impregnated wood has shown the lower HVL and TVL values than pine wood. The smaller HVL means a better ability to absorb radiation for the materials (Aygün, 2020). The penetrating radiation through a specific thickness of material depends on the energy of the photons and the characteristics (density and atomic number) of the material (Akkaş, 2016).…”

mentioning

confidence: 99%

See 2 more Smart Citations

Investigation of the Radiation Shielding Properties of Black Pine Wood Impregnated with Boric Acid

Özkan

2020

Kastamonu Üniversitesi Orman Fakültesi Dergisi

View full text Add to dashboard Cite

Aim of study:The present work is to investigate the radiation shielding properties of impregnated black pine (Pinus nigra Arnold subsp. pallasiana) wood material by measuring linear attenuations coefficient, mass attenuations coefficient, half value and tenth value layer thickness for different gamma energies from 5 keV to 1000 keV.Material and methods: The values of linear attenuation coefficient (1/cm), mass attenuation coefficient (cm 2 /g), half value and tenth value layer thickness of impregnated wood material were calculated in energy range between 5 to 1000 keV using the WinXCOM based Phy-X/PSD software and compared with concrete.Main results: It has been found that the linear attenuation coefficient and the mass attenuation coefficient of impregnated wood decrease as photon energy increases. But, half value layer and tenth value layer of impregnated wood increased as photon energy increased. As a result, it was found that the radiation shielding properties of wood increasing with boric acid impregnation.Highlights: The radiation shielding properties of impregnated wood are higher than pine wood because of its high density and chemical composition, which contains boron elements.

show abstract

Section: Resultsmentioning

confidence: 87%

“…Another essential process which is called Compton scattering dominates the middle energy area. The MAC values in this area gradually decrease with the increase in energy (Aygün, 2020).…”

Section: Resultsmentioning

confidence: 94%

See 1 more Smart Citation

Investigation of the Radiation Shielding Properties of Black Pine Wood Impregnated with Boric Acid

Özkan

2020

Kastamonu Üniversitesi Orman Fakültesi Dergisi

View full text Add to dashboard Cite

show abstract

“…It is vital to explore definite parameters, such as linear attenuation coefficient ( μ ), mass attenuation coefficient (μ/ρ), effective atomic number ( Z eff ), effective electron density ( N eff ), half-value layer (HVL), tenth-value layer (TVL), mean free path (MFP), radiation protection efficiency (RPE), equivalent atomic number ( Z eq ), exposure buildup factor (EBF), and energy absorption buildup factor (EABF) for γ -rays and other quantities, such as macroscopic effective removal cross-sections for fast neutrons ( Σ R ), scattering cross-sections (coherent ( σ cs ) and incoherent (σ ics )), and absorption cross-section ( σ A ), including total cross-section ( σ T ) for slow or thermal neutrons, by utilizing appropriate experimental procedures or theoretical and simulation methods to test glasses [ 8 , 9 , 10 , 11 , 12 , 13 , 14 , 15 , 22 ], glass ceramics [ 23 ], ceramics [ 24 ], metallic glasses [ 25 ], concretes [ 26 , 27 ], steels [ 28 ], alloys [ 29 , 30 , 31 ], and polymers [ 32 , 33 ], etc. for radiation shielding.…”

Section: Introductionmentioning

confidence: 99%

Detailed Inspection of γ-ray, Fast and Thermal Neutrons Shielding Competence of Calcium Oxide or Strontium Oxide Comprising Bismuth Borate Glasses

Lakshminarayana

Elmahroug

Kumar³

et al. 2021

Materials

View full text Add to dashboard Cite

For both the B2O3-Bi2O3-CaO and B2O3-Bi2O3-SrO glass systems, γ-ray and neutron attenuation qualities were evaluated. Utilizing the Phy-X/PSD program, within the 0.015–15 MeV energy range, linear attenuation coefficients (µ) and mass attenuation coefficients (μ/ρ) were calculated, and the attained μ/ρ quantities match well with respective simulation results computed by MCNPX, Geant4, and Penelope codes. Instead of B2O3/CaO or B2O3/SrO, the Bi2O3 addition causes improved γ-ray shielding competence, i.e., rise in effective atomic number (Zeff) and a fall in half-value layer (HVL), tenth-value layer (TVL), and mean free path (MFP). Exposure buildup factors (EBFs) and energy absorption buildup factors (EABFs) were derived using a geometric progression (G–P) fitting approach at 1–40 mfp penetration depths (PDs), within the 0.015–15 MeV range. Computed radiation protection efficiency (RPE) values confirm their excellent capacity for lower energy photons shielding. Comparably greater density (7.59 g/cm3), larger μ, μ/ρ, Zeff, equivalent atomic number (Zeq), and RPE, with the lowest HVL, TVL, MFP, EBFs, and EABFs derived for 30B2O3-60Bi2O3-10SrO (mol%) glass suggest it as an excellent γ-ray attenuator. Additionally, 30B2O3-60Bi2O3-10SrO (mol%) glass holds a commensurably bigger macroscopic removal cross-section for fast neutrons (ΣR) (=0.1199 cm−1), obtained by applying Phy-X/PSD for fast neutrons shielding, owing to the presence of larger wt% of ‘Bi’ (80.6813 wt%) and moderate ‘B’ (2.0869 wt%) elements in it. 70B2O3-5Bi2O3-25CaO (mol%) sample (B: 17.5887 wt%, Bi: 24.2855 wt%, Ca: 11.6436 wt%, and O: 46.4821 wt%) shows high potentiality for thermal or slow neutrons and intermediate energy neutrons capture or absorption due to comprised high wt% of ‘B’ element in it.

show abstract

“…In the past few years, researchers have conducted various studies to find the best materials for reducing exposure to radiation and thus protecting people working in the field of radiation, as well as people exposed to radiation due to side effects [1][2][3][4][5][6][7][8][9][10][11]. Glass has features that make it distinct from other materials, such as visible light being able to pass through it, the ease of preparing glass in different and simple ways, and the possibility of changing the density of the glass during the preparation of glass samples.…”

Section: Introductionmentioning

confidence: 99%

Gamma Ray Shielding Properties of Yb3+-Doped Calcium Borotellurite Glasses

Almuqrin

Sayyed

2021

Applied Sciences

View full text Add to dashboard Cite

This research work aims to investigate the radiation shielding ability of a Yb3+-doped calcium borotellurite glass system. The system has the basic composition of CaF2–CaO–B2O3–TeO2–Yb2O3 but is denoted as TeBYbn for simplicity. The effect of increasing the TeO2 content in the glasses from 10 to 54 mol% was investigated, with five different chosen compositions and densities. The Phy-X/PSD program was used to investigate the mass attenuation coefficient (µ/ρ) of the samples. The mass attenuation coefficients were theoretically determined by using an online software for the calculation of shielding parameters. Other parameters were then calculated and analyzed, such as the linear attenuation coefficient (µ), transmission factor (TF), radiation protection efficiency (RPE), effective atomic number (Zeff), and mean free path (MFP). TeBYb5, the glass with the greatest TeO2 content, was shown to have the greatest µ/ρ; however, at greater energies, the differences between the values are practically negligible. µ was shown to increase with density, such as from 0.386 cm−1 to 0.687 cm−1 for TeBYb1 and TeBYb5 at 0.284 MeV, respectively. The least TF was found for samples with a thickness of 1.5 cm, proving an inverse correlation between the thickness of the sample and the TF. The HVL and TVL of the glasses decreased as the density of the samples increased, which means that TeBYb1 is the least effective out of the investigated glasses. The five samples proved to have a lower MFP than some other shielding glasses, demonstrating their capabilities as radiation shields. Based on the calculated parameters, TeBYb5 indicated the greatest photon attenuation ability.

show abstract

High alloyed new stainless steel shielding material for gamma and fast neutron radiation

Cited by 192 publications

References 10 publications

Investigation of the Radiation Shielding Properties of Black Pine Wood Impregnated with Boric Acid

Investigation of the Radiation Shielding Properties of Black Pine Wood Impregnated with Boric Acid

Detailed Inspection of γ-ray, Fast and Thermal Neutrons Shielding Competence of Calcium Oxide or Strontium Oxide Comprising Bismuth Borate Glasses

Gamma Ray Shielding Properties of Yb3+-Doped Calcium Borotellurite Glasses

Contact Info

Product

Resources

About