Preparation and properties of flame-retardant neutron shielding material based on EVA polymer reinforced by radiation modification

Fan-chao, Chai; Wang, Guohui; Liu, Feng; Jiang, Danfeng; Yao, Chuqing; Xu, Tao; Dai, Yaodong

doi:10.1016/j.radphyschem.2020.108984

Cited by 12 publications

(4 citation statements)

References 20 publications

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“…In this study, silicon, in the form of pure Si and silicon carbide (SiC), was embedded in a 70% EVA polymer to improve the polymer’s shielding properties. In addition, study samples containing 15% and 30% of high capture cross section material, for neutrons such as boron, in the form of B 4 C were incorporated into an 70% EVA polymer and investigated for the attenuation of photon radiation [ 5 , 12 , 13 ]. The attenuation efficiency for the composite materials was evaluated by analyzing their effects on the attenuation coefficient ( µ ), mass attenuation coefficient ( µ m ), half value layer (HVL), and mean free path (MFP).…”

Section: Introductionmentioning

confidence: 99%

Development of New Lead-Free Composite Materials as Potential Radiation Shields

et al. 2021

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Utilizing a polymer-based radiation shield offers lightweight, low cost, non-toxic compared to lead and solution for eliminating generated secondary neutrons. Incorporating silicon (i.e., one of the most abundant elements) in new applications, such as shielding, would have an impact on the economy and industry. In this study, seven potential shielding materials, composed of silicon, silicon carbide, and boron carbide embedded ethylene vinyl acetate (EVA) copolymers, are proposed. The shielding performance of these composite materials, including the attenuation coefficients (µ), the mass attenuation coefficients (µm), the half value layer (HVL), the mean free path (MFP), and the radiation protection efficiency (RPE) were examined using photon beams. Measured µm were verified against the calculated values. The averaged agreement was within ±7.4% between the experimental measurements and the theoretical calculation results. The HVL and MFP measured values for the polymer composites were lower than that for the pure EVA polymer, indicating the fillers in the polymers enhanced the shielding performance. The EVA + SiC (30%) and EVA + Si (15%) + B4C (15%) composites required the lowest thickness to stop 50% of the incident photons. The evaluation of experimental results of the RPE revealed that the polymer composites containing SiC (30%), Si (15%) + B4C (15%), or SiC (15%) + B4C (15%) succeeded in blocking 90–91% of X-rays at nearly 80 keV. However, a thicker shield of the proposed composite materials or combined layers with other high-Z materials could be used for higher energies.

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Section: Introductionmentioning

confidence: 99%

Development of New Lead-Free Composite Materials as Potential Radiation Shields

et al. 2021

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“…In another study, boron-filled plastic based composite samples were produced and neutron shielding capabilities were investigated as experimental [10]. In another composite designed as a shielding material against neutron particles, ethylene-vinyl acetate (EVA) was used as the base material and multi-walled carbon nanotubes (CNTs), boron carbide (B 4 C), and zinc borate (ZB) were used as fillers [11]. The most important disadvantage of all these studies is that the secondary radiations released as a result of the interactions between neutron particles and polymer-based armor materials and the precautions to be taken against them are not mentioned.…”

Section: Introductionmentioning

confidence: 99%

Detailed Monte Carlo simulations on secondary radiation emissions of polymer based neutron shielding materials

Korkut,

Korkut

2024

Phys. Scr.

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Since radiation safety is a sensitive issue in terms of health, this situation poses a significant problem. In order to raise awareness among researchers while preparing future studies on this problem, in this study, the interactions between fast neutrons and 10 different polymer-based shielding materials determined from the literature were modeled with the GEANT4 Monte Carlo code. The fast neutron shielding performances of the samples and the emitted secondary radiation and radioactivity have been reported. When evaluated number and mean energies of created particles, in order to solve this problem, the sum of the risk factors obtained by multiplying these values for each sample can provide us with the opportunity to make a more accurate evaluation. When these values are examined, sample P9 is at the top of the risk ranking with a value of 1823472, while sample P6 is at the bottom with a value of 146246. As a result, it has been revealed that these samples, which have good fast neutron shielding properties, also produce high levels of radiation and radioactive nuclei.

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“…The research result of the shielding ability of polymer/metal composites suggested that the incorporation of polymer could decrease the weight of shielding material. [20][21][22] Meanwhile, the sediment of the heavy metal powder is prominent problem during the process of polymer curing. In other words the heavy metal powder could not be dispersed in polymer mixture uniformly, which lead the shielding performance degradation.…”

Section: Introductionmentioning

confidence: 99%

“…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 20–22 . Meanwhile, the sediment of the heavy metal powder is prominent problem during the process of polymer curing.…”

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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Preparation and properties of flame-retardant neutron shielding material based on EVA polymer reinforced by radiation modification

Cited by 12 publications

References 20 publications

Development of New Lead-Free Composite Materials as Potential Radiation Shields

Development of New Lead-Free Composite Materials as Potential Radiation Shields

Detailed Monte Carlo simulations on secondary radiation emissions of polymer based neutron shielding materials

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

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