Micro‐hardness and gamma‐ray attenuation properties of lead iron phosphate glasses

Al-Buriahi, M.S.; Eke, Canel; Alomairy, Sultan; Mutuwong, Chalermpon; Sfina, N.

doi:10.1007/s10854-021-05966-8

Cited by 57 publications

(6 citation statements)

References 44 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The mass attenuation coefficient (MAC) measures the interaction of incident photons with the target material and calculated using Eq. (3) [ 54 , 55 ].

where w i is the weight fraction and (μ/ρ) i is the mass attenuation coefficient of i th constituent element from Eq.…”

Section: Theoretical Backgroundmentioning

confidence: 99%

Investigation of gamma-ray shielding parameters of bismuth phospho-tellurite glasses doped with varying Sm2O3

Kolavekar

Hiremath

Patil

et al. 2022

Heliyon

View full text Add to dashboard Cite

“…The mass attenuation coefficient (MAC) measures the interaction of incident photons with the target material and calculated using Eq. (3) [ 54 , 55 ].

where w i is the weight fraction and (μ/ρ) i is the mass attenuation coefficient of i th constituent element from Eq.…”

Section: Theoretical Backgroundmentioning

confidence: 99%

Investigation of gamma-ray shielding parameters of bismuth phospho-tellurite glasses doped with varying Sm2O3

Kolavekar

Hiremath

Patil

et al. 2022

Heliyon

View full text Add to dashboard Cite

“…The evaluation also includes an investigation of the nuclear shield properties and calculation of the fast neutrons' effective cross-section removal. Several researchers conducted experiments on the synthesis of borate glasses containing bismuth, lead, and other elements, which have yielded encouraging results [6, [19][20][21][22][23][24]. However, it is essential to emphasize that a signi cant portion of this research uses theoretical simulations and computer programs to assess effectiveness in the eld of radiation protection.…”

Section: Introductionmentioning

confidence: 99%

Synthesis and gamma-ray shielding efficiency of borosilicate glasses doped with Zinc oxide: Comparative study

Saleh,

Sayyed,

Kumar

et al. 2024

Preprint

View full text Add to dashboard Cite

This study examined the suitability of several glass compositions as a gamma-ray shielding substance. The compositions tested were of varying ZnO concentrations, specifically (60-x) B2O3 − 10Na2O − 15SiO2 − 5Al2O3 - (x + 10 )ZnO (where X = 5, 10, 15 and 20 mol%). Measurements were performed at energy levels of 0.6642, 1.1776, and 1.3343 MeV radiated from Cs137 and Co60 point sources along with a scintillation detector [NaI(TL)]. We investigated the critical properties related to gamma radiation shielding, determining the effective atomic number (Zeff), electron density (Nel), half-value layer (HVL), linear attenuation (µ) and mass attenuation (µm) coefficients, and mean free path (λ). Our results show that all glass compositions provide adequate protection against gamma radiation at the specified energy levels. The values of µ went up from 0.157 to 0.214 cm− 1 (0.6642 MeV), from 0.119 to 0.160 cm− 1 (1.1776 MeV), and from 0.114 to 0.151 (1.3343 MeV). For samples B1 and B4, the observed HVL values dropped from 4.41, 5.84, and 6.12 cm to 3.21, 4.31, and 4.61 cm at 0.6642, 1.1736, and 1.3343 MeV, respectively. Among the materials tested, prepared glasses show higher shielding capacity compared to regularly used glass and concrete samples. The study highlights these glass compositions' potential as practical materials that can shield gamma radiation.

show abstract

“…While several studies on radiation shielding materials have been carried out [19][20][21][22][23], these investigations were not dedicated to the evaluation of the radiation damage induced by secondary energetic ions. Therefore, follow-up accelerated corrosion experiments on B 4 C neutron absorbers need to be conducted to investigate and address the discrepancies between the current qualification test results and the new observations.…”

Section: Introductionmentioning

confidence: 99%

Simulation of Radiation Damage and He Accumulation Induced by 10B(n, α)7Li Reactions in Al-B4C Neutron Absorbers Used in Spent Fuel Pools

Kim,

Lee,

Jung

et al. 2024

International Journal of Energy Research

View full text Add to dashboard Cite

Faster than expected surface corrosion and a considerable decrease in the 10B areal density of a non-clad Al-B4C neutron absorber were recently reported from surveillance coupons used in a spent fuel pool for about 8 years, which is only approximately one-fifth of the guaranteed service life of the absorber. Such premature degradation was largely attributed to irradiation-assisted corrosion since numerous gas bubbles filled with He and H were discovered in the Al alloy matrix near B4C particles, and naturally 10B(n, α)7Li reactions were designated as the underlying mechanism for the porosification that may have expedited the absorber corrosion. In this study, the levels of radiation damage and He concentration in the micrographs published in recent experimental studies were estimated to design ion beam irradiation experiments having appropriate parameters to emulate the status of neutron-irradiated non-clad Al-B4C absorbers. TRITON, CSAS6, and SDTrimSP were coupled with modifications for the calculation of dpa and He concentration in irradiated neutron absorbers. The simulations yielded 3.74–6.71 dpa and 0.71–1.64 at% of He after 99 months of use and 3.82–8.39 dpa and 0.73–2.08 at% of He after 40 years of use. The simulations also demonstrated that the radiation damage and He concentration have a weak correlation with the particle diameter. In terms of radiation damage, these results are in good agreement with the reported experimental data, indicating that they can be referred to in the experimental design. The calculated He concentrations, however, may warrant modification to include leakage of implanted He atoms through irradiation-induced microcracks in the B4C particles. Because of the high diffusivity of He, full leakage of He from B4C particles to their boundaries with the Al alloy matrix was assumed for further estimations, which revealed that He concentration could be significantly elevated in the Al matrix near B4C particles.

show abstract

Micro‐hardness and gamma‐ray attenuation properties of lead iron phosphate glasses

Cited by 57 publications

References 44 publications

Investigation of gamma-ray shielding parameters of bismuth phospho-tellurite glasses doped with varying Sm2O3

Investigation of gamma-ray shielding parameters of bismuth phospho-tellurite glasses doped with varying Sm2O3

Synthesis and gamma-ray shielding efficiency of borosilicate glasses doped with Zinc oxide: Comparative study

Simulation of Radiation Damage and He Accumulation Induced by 10B(n, α)7Li Reactions in Al-B4C Neutron Absorbers Used in Spent Fuel Pools

Contact Info

Product

Resources

About