Waste-polymer incorporated concrete mixes for neutron and gamma radiation shielding

Malkapur, Santhosh M.; Ghodke, Shobha; Sujatha, P.N.; Singh, Yashoda; Shivakumar, K.S.; Sen, Meghanath; Narasimhan, M. S.; Pulgur, Abhishek

doi:10.1016/j.pnucene.2021.103694

Cited by 30 publications

(8 citation statements)

References 14 publications

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“…In the previous equation, x (cm) is the thickness of the concrete sample, and 𝝆 (g/cm 3 ) is its density. The run of this simulation gave the spectrum using ROOT software [27,28] as shown in Figure 3.…”

Section: Geant4 Codementioning

confidence: 99%

“…In the previous equation, x (cm) is the thickness of the concrete sample, and 𝝆 (g/cm 3 ) is its density.…”

Section: Geant4 Codementioning

confidence: 99%

“…Additionally, the method used will vary depending upon the economic preparation of the materials and the resistance of the material to radiation damage [1,2]. Concrete is an effective shielding material that has gained much interest due to its low cost, eco-friendliness, suitable density for radiation attenuation, and simplicity to manufacture when comparing with other traditional shielding materials [3,4]. Furthermore, it is simple to incorporate high atomic number elements in the concrete in order to improve its attenuation capability [5].…”

Section: Introductionmentioning

confidence: 99%

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Understanding the Effect of Introducing Micro- and Nanoparticle Bismuth Oxide (Bi2O3) on the Gamma Ray Shielding Performance of Novel Concrete

et al. 2021

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The aim of this study is to investigate the radiation shielding properties of novel concrete samples with bulk Bi2O3 and Bi2O3 nanoparticles (Bi2O3 NP) incorporated into its composition. The mass attenuation coefficient of the concrete samples without Bi2O3 and with 5 and 7 wt% bulk Bi2O3 were experimentally determined and were compared against values obtained using the XCOM and Geant4 simulations. Both methods greatly agree with the experimental values. The linear attenuation coefficients (LAC) of blank concrete (C-0), concrete with 5% bulk Bi2O3 (C-B5), and concrete with 5% nanoparticle Bi2O3 (C-N5) were determined and compared at a wide energy range. We found that the LAC follows the trend of C-0 < C-B5 < C-N5 at all the tested energies. Since both C-B5 and C-N5 have a greater LAC than C-0, these results indicate that the addition of Bi2O3 improves the shielding ability of the concretes. In addition, we investigated the influence of nanoparticle Bi2O3 on the LAC of the concretes. The half-value layer (HVL) for the concretes with bulk Bi2O3 and Bi2O3 nanoparticles is also investigated. At all energies, the C-0 has the greatest HVL, while C-N15 has the least. Thus, C-N15 concrete is the most space efficient, while C-0 is the least space efficient. The radiation protection efficiency (RPE) of the prepared concretes was found to decrease with increasing energy for all five samples. For C-0, the RPE decreased from 63.3% at 0.060 MeV to 13.48% at 1.408 MeV, while for C-N15, the RPE decreased from 87.9 to 15.09% for the same respective energies. Additionally, C-N5 had a greater RPE than C-B5, this result demonstrates that Bi2O3 NP are more efficient at shielding radiation than bulk Bi2O3.

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Section: Geant4 Codementioning

confidence: 99%

“…In the previous equation, x (cm) is the thickness of the concrete sample, and 𝝆 (g/cm 3 ) is its density.…”

Section: Geant4 Codementioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Understanding the Effect of Introducing Micro- and Nanoparticle Bismuth Oxide (Bi2O3) on the Gamma Ray Shielding Performance of Novel Concrete

et al. 2021

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“…[14][15][16] Heavy metal shielding shell would increase the weight of equipment, which is irreconcilable with miniaturization, lightweight and long duration running. [17][18][19] In order to decrease the weight of nuclear shielding materials, various composites were prepared and investigated as shown in Table 1. The research result of the shielding ability of polymer/metal composites suggested that the incorporation of polymer could decrease the weight of shielding material.…”

Section: Introductionmentioning

confidence: 99%

Enhancement of nuclear radiation shielding properties of silicone rubber with γ‐ray irradiation induced graphene oxide modified carbonyl iron powder hybrid fillers

Meng

Chai

et al. 2023

J of Applied Polymer Sci

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In this study the graphene oxide modified carbonyl iron (GO‐CI) was prepared by γ‐ray irradiation, which was added to silicone rubber composites to enhance the nuclear radiation shielding performances. X‐ray diffraction (XRD) characterization result showed the structure and morphology of the obtained GO‐CI nanocomposites. The mixture of GO/CI and the hybrid GO‐CI were individually incorporated into the vinyl‐terminated polydimethylsiloxane (Vi‐PDMS) to prepare referenced SR/GO/CI and SR/GO‐CI composites. Compared with SR/GO/CI, the SR/GO‐CI exhibited better thermal conduction and mechanical recovery properties. Moreover, the γ‐ray radiation shielding ability of SR/GO‐CI is much higher than that of pristine SR/GO/CI. CI particles are coated by GO nanosheets to increase surface area to prevent sedimentation of CI. It implies that SR‐GO/CI composite would have potential application as the radiation hardening material with thermal conductive and nuclear radiation shielding function.

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“…This industrialization produces an enormous amount of solid waste that causes environmental problems due to the accumulation of waste and limited landfill sites. To solve these problems, researchers are focused on treating and converting solid waste into more valuable and environmentally friendly materials [26][27][28] . Glass is an example of solid waste that needs long periods of time to decompose.…”

Section: Introductionmentioning

confidence: 99%

The Effect of WO3-Doped Soda Lime Silica SLS Waste Glass to Develop Lead-Free Glass as a Shielding Material against Radiation

et al. 2022

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The current study aims to enhance the efficiency of lead-free glass as a shielding material against radiation, solve the problem of the dark brown of bismuth glass, and reduce the accumulation of waste glass disposed in landfills by using soda-lime-silica SLS glass waste. The melt-quenching method was utilized to fabricate (WO3)x[(Bi2O3)0.2(ZnO)0.3(B2O3)0.2(SLS)0.3]1−x at 1200 °C, where x= (0, 0.01, 0.02, 0.03, 0.04, and 0.05 mol). Soda lime silica SLS glass waste, which is mostly composed of 74.1 % SiO2, was used to obtain SiO2. Radiation Attenuation parameters were investigated using narrow-beam geometry and X-ray fluorescence (XRF). Furthermore, the parameters related to radiation shielding were calculated. The results showed that when WO3 concentration was increased, the half-value layer was reduced, whereas the μ increased. It could be concluded that WBiBZn-SLS glass is a good shielding material against radiation, nontoxic, and transparent to visible light.

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Waste-polymer incorporated concrete mixes for neutron and gamma radiation shielding

Cited by 30 publications

References 14 publications

Understanding the Effect of Introducing Micro- and Nanoparticle Bismuth Oxide (Bi2O3) on the Gamma Ray Shielding Performance of Novel Concrete

Understanding the Effect of Introducing Micro- and Nanoparticle Bismuth Oxide (Bi2O3) on the Gamma Ray Shielding Performance of Novel Concrete

Enhancement of nuclear radiation shielding properties of silicone rubber with γ‐ray irradiation induced graphene oxide modified carbonyl iron powder hybrid fillers

The Effect of WO3-Doped Soda Lime Silica SLS Waste Glass to Develop Lead-Free Glass as a Shielding Material against Radiation

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