Evaluation of Acrylonitrile Butadiene Styrene (ABS) polymer reinforced with Bi and TiO2 nanopowders for gamma and neutron shielding
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Batuhan Gultekin
Abstract
3D printer technology has recently become easily reachable technology and are used to create simple or complex structures with high-quality. Its superior advantages could also be useful on the production of effective radiation shielding materials. On this purpose, the presented work studies the gamma and neutron shielding effectiveness of Acrylonitrile Butadiene Styrene (ABS) sample, a 3D printing material, reinforced with Bi and TiO2 nanopowders at various gamma and neutron energies. The gamma shielding properties were evaluated using experimental (High Purity Germanium detector system), theoretical (WinXCOM computer program) and simulation techniques (GEANT4 and FLUKA) in a wide gamma energy region ranging from 59.5 to 1332.5 keV. The investigation on neutron attenuation capabilities of the printed composites were performed with help of simulation and theoretical approaches for various sample thickness and neutron energies. The half value layer of ABS-Bi10 sample is found to be as 4.9565 cm, which is much smaller than some commercial polymers: polyvinylidenechloride, polyamide, polyacrylonitrile, polyphenylenesulfide, and unsaturated polyester. With the usage of 3D printing technology, significant enhancements in neutron and gamma shielding were reported.
Acknowledgement
The numerical calculations reported in this paper were partially performed at TUBITAK ULAKBIM, High Performance and Grid Computing Center (TRUBA resources).
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Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Research funding: None declared.
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Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
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Articles in the same Issue
- Frontmatter
- Original Papers
- Cross sections and calculated yields of some radionuclides of yttrium, strontium and rubidium formed in proton-induced reactions on enriched strontium-86: possibility of production of 85gSr, 83Rb and 82mRb in no-carrier-added form
- Kaolinite/thiourea-formaldehyde composite for efficient U(VI) sorption from commercial phosphoric acid
- Soya bean derived activated carbon as an efficient adsorbent for capture of valuable heavy metals from waste aqueous solution
- Synthesis and characterization of graphene oxide/alginate and application of central composite design in the adsorption of Th(IV) on the nanobiocomposites
- Characterization of toothpastes for fluorine and other elements by INAA and ICP-OES
- Evaluation of Acrylonitrile Butadiene Styrene (ABS) polymer reinforced with Bi and TiO2 nanopowders for gamma and neutron shielding
- Natural and anthropogenic radionuclides in karstic coastal area (Kaštela Bay, Adriatic Sea, Croatia) exposed to anthropogenic activities: distribution, sources, and influencing factors
Articles in the same Issue
- Frontmatter
- Original Papers
- Cross sections and calculated yields of some radionuclides of yttrium, strontium and rubidium formed in proton-induced reactions on enriched strontium-86: possibility of production of 85gSr, 83Rb and 82mRb in no-carrier-added form
- Kaolinite/thiourea-formaldehyde composite for efficient U(VI) sorption from commercial phosphoric acid
- Soya bean derived activated carbon as an efficient adsorbent for capture of valuable heavy metals from waste aqueous solution
- Synthesis and characterization of graphene oxide/alginate and application of central composite design in the adsorption of Th(IV) on the nanobiocomposites
- Characterization of toothpastes for fluorine and other elements by INAA and ICP-OES
- Evaluation of Acrylonitrile Butadiene Styrene (ABS) polymer reinforced with Bi and TiO2 nanopowders for gamma and neutron shielding
- Natural and anthropogenic radionuclides in karstic coastal area (Kaštela Bay, Adriatic Sea, Croatia) exposed to anthropogenic activities: distribution, sources, and influencing factors
