Calculation of fast neutron removal cross-sections for some compounds and materials

El-Khayatt, A.M.

doi:10.1016/j.anucene.2009.10.022

Cited by 167 publications

(24 citation statements)

References 3 publications

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“…Macroscopic effective neutron cross‐section ∑ R (cm −1 ) was determined with the help of measured neutron transmission factor. The term of macroscopic effective neutron cross sections is defined as the probability of neutron interaction per unit length with in the shielding medium 43 . ∑ R of the developed samples were derived by the slope of the fitted line using the relationship between ln(I (0) /I (x) ) versus sample thickness 'x' 44 .…”

Section: Resultsmentioning

confidence: 99%

Ethylene‐propylene diene monomer‐based polymer composite for attenuation of high energy radiations

Barala

Manda

Jodha

et al. 2020

J of Applied Polymer Sci

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Radiation shielding composites of ethylene‐propylene diene monomer (EPDM), reinforced with tungsten (W) and barium sulphate (BaSO4) in different filler weight (wt%) were synthesized. The effects of W and BaSO4 on gamma and neutron attenuation properties of the composites were studied by experimental methods using 137Cs, 60Co and 252Cf radioactive sources. EPDM composites with W and BaSO4 fillers were also investigated for filler dispersion using scanning electron microscopy and X‐ray radiograph. The experimental results revealed that the incorporation of W and BaSO4 significantly improved the radiation attenuation properties of the EPDM composites. It was observed that the attenuation properties of the composite material increases with higher concentration of the filler. The half‐value layer (HVL), tenth value layer thickness and relaxation length of the composites were found to decrease with increasing concentration of the filler. The results also showed that the attenuation behaviour of 50 wt% BaSO4 filled polymer composite is comparable to that of the composite with 25 wt% W. The developed composite with 75 wt% W filler exhibited the maximum radiation attenuation with lowest HVL thicknesses.

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Section: Resultsmentioning

confidence: 99%

Ethylene‐propylene diene monomer‐based polymer composite for attenuation of high energy radiations

Barala

Manda

Jodha

et al. 2020

J of Applied Polymer Sci

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“…The results of the MERCSF-N program were validated with previously published results and confirmed a good agreement. El-Khayatt has developed an NXcom program for the determination of the removal and attenuation coefficients of transmitted fast neutrons and γ -rays, respectively (El-Khayatt 2011 ). Mass attenuation coefficient values calculated using the NXcom program have been confirmed by comparing them with the results of the WinXCom program.…”

Section: Polymer Composites For Gamma-radiation Shieldingmentioning

confidence: 99%

Polymeric composite materials for radiation shielding: a review

et al. 2021

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The rising use of radioactive elements is increasing radioactive pollution and calling for advanced materials to protect individuals. For instance, polymers are promising due to their mechanical, electrical, thermal, and multifunctional properties. Moreover, composites made of polymers and high atomic number fillers should allow to obtain material with low-weight, good flexibility, and good processability. Here we review the synthesis of polymer materials for radiation protection, with focus on the role of the nanofillers. We discuss the effectivness of polymeric materials for the absorption of fast neutrons. We also present the recycling of polymers into composites.

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“…Also, El-Khayatt et al and Tellili et al assessed different materials for shielding fast neutrons. Among these materials, iron oxide has an acceptable crosssection against fast neutrons [40,41]. Nevertheless, before the present study, there was no study on the combined effect of double-layer nanocomposites in eliminating photoneutrons from the linac.…”

Section: Discussionmentioning

confidence: 83%

Design and fabrication of a Nano-based neutron shield for fast neutrons from medical linear accelerators in radiation therapy

et al. 2020

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Background: Photo-neutrons are produced at the head of the medical linear accelerators (linac) by the interaction of high-energy photons, and patients receive a whole-body-absorbed dose from these neutrons. The current study aimed to find an efficient shielding material for fast neutrons. Methods: Nanoparticles (NPs) of Fe 3 O 4 and B 4 C were applied in a matrix of silicone resin to design a proper shield against fast neutrons produced by the 18 MeV photon beam of a Varian 2100 C/D linac. Neutron macroscopic cross-sections for three types of samples were calculated by the Monte Carlo (MC) method and experimentally measured for neutrons of an Am-Be source. The designed shields in different concentrations were tested by MCNPX MC code, and the proper concentration was chosen for the experimental test. A shield was designed with two layers, including nano-iron oxide and a layer of nano-boron carbide for eliminating fast neutrons. Results: MC simulation results with uncertainty less than 1% showed that for discrete energies and 50% nanomaterial concentration, the macroscopic cross-sections for iron oxide and boron carbide at the energy of 1 MeV were 0.36 cm − 1 and 0.32 cm − 1 , respectively. For 30% nanomaterial concentration, the calculated macroscopic cross-sections for iron oxide and boron carbide shields for Am-Be spectrum equaled 0.12 cm − 1 and 0.15 cm − 1 , respectively, while they are 0.15 cm − 1 and 0.18 cm − 1 for the linac spectrum. In the experiment with the Am-Be spectrum, the macroscopic cross-sections for 30% nanomaterial concentration were 0.17 ± 0.01 cm − 1 for iron oxide and 0.21 ± 0.02 cm − 1 for boron carbide. The measured transmission factors for 30% nanomaterial concentration with the Am-Be spectrum were 0.71 ± 0.01, 0.66 ± 0.02, and 0.62 ± 0.01 for the iron oxide, boron carbide, and double-layer shields, respectively. In addition, these values were 0.74, 0.69, and 0.67, respectively, for MC simulation for the linac spectrum at the same concentration and thickness of 2 cm. Conclusion: Results achieved from MC simulation and experimental tests were in a satisfactory agreement. The difference between MC and measurements was in the range of 10%. Our results demonstrated that the designed double-layer shield has a superior macroscopic cross-section compared with two single-layer nanoshields and more efficiently eliminates fast photo-neutrons.

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Calculation of fast neutron removal cross-sections for some compounds and materials

Cited by 167 publications

References 3 publications

Ethylene‐propylene diene monomer‐based polymer composite for attenuation of high energy radiations

Ethylene‐propylene diene monomer‐based polymer composite for attenuation of high energy radiations

Polymeric composite materials for radiation shielding: a review

Design and fabrication of a Nano-based neutron shield for fast neutrons from medical linear accelerators in radiation therapy

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