An extensive study on the neutron-gamma shielding and mass stopping power of (70-x) CRT–30K<sub>2</sub>O–xBaO glass system for <sup>252</sup>Cf neutron source

Sarıhan, Mucize; Malidarre, Roya Boodaghi; Akkurt, I.

doi:10.1080/09593330.2021.1987529

Cited by 24 publications

(6 citation statements)

References 29 publications

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“…Here -dE/dx is a stopping power, E is the energy and x is the distance of the charged particle through a medium [18,22,28].…”

Section: Methodsmentioning

confidence: 99%

Efficacy of barium and calcium additives in lithium silicate glasses for nuclear shielding applications

Yilmaz Alan

2024

Phys. Scr.

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This study presents a detailed investigation into the nuclear radiation shielding capabilities of lithium silicate (Li2O-SiO2) glass systems, specifically examining the impact of doping with barium oxide (BaO) and calcium oxide (CaO). Utilizing advanced simulation tools, including PAGEX and SRIM for charged particle interactions, and Phy-X/PSD for gamma-ray attenuation analysis, the radiation shielding effectiveness of BaO-based and CaO-based lithium silicate glasses were systematically compared. The gamma attenuation parameters (LAC, MAC, TVL, HVL, EBF, EABF, MFP, Zeff, Neff, FNRCS, and Zeq) of investigated glass samples were computed via the Phy-X/PSD program (15 keV-15 MeV energy). The HVL values vary between 0.007–14.203 cm, and the TVL values vary between 0.054–47.182 cm for all samples in the selected energy range. The highest and lowest values of FNRCS were observed for samples BaO20 and CaO5, with the values 0.093 and 0.1 cm−1, respectively. KERMAs were calculated using PAGEX software between the 1.5 keV and 20 MeV energy range, with the highest KERMA obtained for the BaO20 sample at 0.05 MeV and the lowest KERMA obtained for the CaO5 sample at the lowest density. The mass stopping power quantities were computed between 1 keV-10 GeV energy with PAGEX. The projected range values were calculated with SRIM codes. The lowest projected range values for both alpha particles and protons were obtained for the BaO20 sample with maximum density (3.391 g cm−3). The sample with BaO20 code showed better shielding potential for alpha and proton particles with lower values of projected range and mass stopping power. Findings reveal that the Li2O-BaO-SiO2 glass composition exhibits superior gamma-ray attenuation properties compared to its CaO-doped counterpart, with the BaO20 sample demonstrating particularly enhanced performance.

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“…Here -dE/dx is a stopping power, E is the energy and x is the distance of the charged particle through a medium [18,22,28].…”

Section: Methodsmentioning

confidence: 99%

Efficacy of barium and calcium additives in lithium silicate glasses for nuclear shielding applications

Yilmaz Alan

2024

Phys. Scr.

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“…Using watt ssion distribution with constant parameters (a = 1.180000, b = 1.03419) (see Eq. 1) [1,[11][12] and the doppler effect the neutron and gamma photon spectra are derived [1]. A more in-depth examination of these methods can be found elsewhere.…”

Section: Methodsmentioning

confidence: 99%

“…The neutron and gamma photon spectra are provided and then using the ux-todose conversion function which combines DFn and F4 tally cards, the Equivalent dose rate is estimated. The DFn card can be de ned as seen below [11][12]:…”

Section: Mcnpx Simulation Studymentioning

confidence: 99%

A Monte Carlo Study on Skin Dose Contamination Coefficients of 252Cf Radionuclide

Malidarre¹,

Akkurt²

2023

Preprint

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Handling of 252Cf radionuclide source can lead to contamination of the skin surface in case of an accident. There is still an increasing demand to have dose conversion coefficients of each primary particle and different sources. On the other hand, there is no literature that presents actual values and methods for determining skin dose contamination and its coefficients for 252Cf source. Thus, this paper is concerned with quantifying the received dose rate and its coefficients in the skin as a result of a contamination scenario. The equivalent and absorbed dose rates, as well as SDCC, are estimated using MCNPX Monte-Carlo simulation’s well-established calculation code in the skin. Two methods i.e. watt fission and doppler effect are proposed for calculating particles’ spectra, and consequently, with the help of flux–to–dose conversion function Equivalent dose rates are derived. Also, the SDCC on the skin surface for different particles is obtained and these values are reported for 252Cf radionuclide. The particles of interest in this study are neutrons and gamma photons. The new dose coefficients allow the estimation of the skin dose contamination in radionuclides of interest.

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“…The lead is the most used material to protect from X-rays and γ-rays in the past but due to its toxicity, heaviness, rigidity, and poor portability character, researchers focused on the radiation protection topic to find new alternative materials for radiation shielding. Thus there are many different types materials such as glasses and composites that can be the best replacement of the conventional material have recently been studied either experimentally or simulation code [18][19][20][21][22][23][24][25][26][27][28][29][30][31][32][33][34][35][36].…”

Section: Introductionmentioning

confidence: 99%

Effective Atomic Numbers of Glass Samples

Karpuz

2024

IJCESEN

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Effective atomic numbers are a term used to understand the interaction of a compound or material with radiation. In particular, this term is often used for materials with complex structures that can be expressed by a single fixed atomic number. If different elements in a material are present in different concentrations, the effective atomic number of the material can be calculated by considering the contribution of each element. This is a useful method to better understand the response of the material to radiation or the effect of radiation within the material. In particular, when radiation passes through or acts on the material, the effective atomic number plays an important role in determining factors such as the material's radiation exposure properties, absorption or scattering. Effective atomic numbers are used in radiation interaction analyses in various fields such as materials science, medicine, geophysics and industry. This concept is used to express in a simpler way the radiation properties of compounds in which different elements are combined. In this study, the effective atomic numbers of magnesium borosilicate glasses were investigated. Such studies are important in the field of materials science and glass technology because the chemical constituents of glass and their interactions play a decisive role in the properties of glass. Magnesium borosilicate glasses are often used in industrial applications. The properties of these glasses depend on the amount of elements they contain and their chemical structure. Effective atomic numbers can be used to understand the specific properties of a material. By determining the effective atomic numbers of the elements contained in the glass, this study aims to provide an important basis for understanding the properties of the material, such as radiation exposure, electrical properties or optical properties.

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An extensive study on the neutron-gamma shielding and mass stopping power of (70-x) CRT–30K₂O–xBaO glass system for ²⁵²Cf neutron source

Cited by 24 publications

References 29 publications

Efficacy of barium and calcium additives in lithium silicate glasses for nuclear shielding applications

Efficacy of barium and calcium additives in lithium silicate glasses for nuclear shielding applications

A Monte Carlo Study on Skin Dose Contamination Coefficients of 252Cf Radionuclide

Effective Atomic Numbers of Glass Samples

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An extensive study on the neutron-gamma shielding and mass stopping power of (70-x) CRT–30K2O–xBaO glass system for 252Cf neutron source

Cited by 24 publications

References 29 publications

Efficacy of barium and calcium additives in lithium silicate glasses for nuclear shielding applications

Efficacy of barium and calcium additives in lithium silicate glasses for nuclear shielding applications

A Monte Carlo Study on Skin Dose Contamination Coefficients of 252Cf Radionuclide

Effective Atomic Numbers of Glass Samples

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Product

Resources

About

An extensive study on the neutron-gamma shielding and mass stopping power of (70-x) CRT–30K₂O–xBaO glass system for ²⁵²Cf neutron source