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Enhancing Gamma-Neutron Shielding Effectiveness of Polyvinylidene Fluoride for Potent Applications in Nuclear Industries: A Study on the Impact of Tungsten Carbide, Trioxide, and Disulfide Using EpiXS, Phy-X/PSD, and MCNP5 Code

  • Received : 2023.07.01
  • Accepted : 2023.12.10
  • Published : 2023.12.31

Abstract

Background: Radiation protection is crucial in various fields due to the harmful effects of radiation. Shielding is used to reduce radiation exposure, but gamma radiation poses challenges due to its high energy and penetration capabilities. Materials and Methods: This work investigates the radiation shielding properties of polyvinylidene fluoride (PVDF) samples containing different weight fraction of tungsten carbide (WC), tungsten trioxide (WO3), and tungsten disulfide (WS2). Parameters such as the mass attenuation coefficient (MAC), half-value layer (HVL), mean free path (MFP), effective atomic number (Zeff), and macroscopic effective removal cross-section for fast neutrons (ΣR) were calculated using the Phy-X/PSD software. EpiXS simulations were conducted for MAC validation. Results and Discussion: Increasing the weight fraction of the additives resulted in higher MAC values, indicating improved radiation shielding. PVDF-xWC showed the highest percentage increase in MAC values. MFP results indicated that PVDF-0.20WC has the lowest values, suggesting superior shielding properties compared to PVDF-0.20WO3 and PVDF-0.20WS2. PVDF-0.20WC also exhibited the highest Zeff values, while PVDF-0.20WS2 showed a slightly higher increase in Zeff at energies of 0.662 and 1.333 MeV. PVDF-0.20WC has demonstrated the highest ΣR value, indicating effective shielding against fast neutrons, while PVDF-0.20WS2 had the lowest ΣR value. The Monte Carlo N-Particle Transport version 5 (MCNP5) simulations showed that PVDF-xWC attenuates gamma radiation more than pure PVDF, significantly decreasing the dose equivalent rate. Conclusion: Overall, this research provides insights into the radiation shielding properties of PVDF mixtures, with PVDF-xWC showing the most promising results.

Keywords

Acknowledgement

We would like to express our sincere gratitude and appreciation to all those who have contributed to the completion of this paper. Their support, guidance, and assistance have been invaluable throughout the research process.

References

  1. Burns KM, Shoag JM, Kahlon SS, Parsons PJ, Bijur PE, Taragin BH, et al. Lead aprons are a lead exposure hazard. J Am Coll Radiol. 2017;14(5):641-647. https://doi.org/10.1016/j.jacr.2016.10.024
  2. International Atomic Energy Agency. Radiation protection aspects of design for nuclear power plants: IAEA Safety Standards Series No. NS-G-1.13. IAEA; 2005.
  3. Nivedhitha DM, Jeyanthi S. Polyvinylidene fluoride, an advanced futuristic smart polymer material: a comprehensive review. Polym Adv Technol. 2023;34(2):474-505.
  4. Saxena P, Shukla P. A comprehensive review on fundamental properties and applications of poly(vinylidene fluoride) (PVDF). Adv Compos Hybrid Mater. 2021;4:8-26. https://doi.org/10.1007/s42114-021-00217-0
  5. Nazir A. A review of polyvinylidene fluoride (PVDF), polyurethane (PU), and polyaniline (PANI) composites-based materials for electromagnetic interference shielding. J Thermoplast Compos Mater. 2022;35(10):1790-1810. https://doi.org/10.1177/0892705720925120
  6. Zakaly HMH, Abulyazied DE, Issa SAM, Alrowaily AW, Saudi HA, Abomostafa HM. Optical, microhardness, and radiation shielding properties of rare earth doped strontium barium titanate polyvinylidene fluoride nanocomposites. J Inorg Organomet Polym Mater. 2023;33:1177-1190. https://doi.org/10.1007/s10904-023-02564-5
  7. Alabsy MT, Alzahrani JS, Sayyed MI, Abbas MI, Tishkevich DI, El-Khatib AM, et al. Gamma-ray attenuation and exposure buildup factor of novel polymers in shielding using Geant4 simulation. Materials (Basel). 2021;14(17):5051.
  8. Sayyed MI, AlZaatreh MY, Matori KA, Sidek HAA, Zaid MHM. Comprehensive study on estimation of gamma-ray exposure buildup factors for smart polymers as a potent application in nuclear industries. Results Phys. 2018;9:585-592. https://doi.org/10.1016/j.rinp.2018.01.057
  9. Silva LA, Batista AMS, Serodre T, Neto ATB, Furtado CA, Faria LO. Enhancement of X-ray shielding properties of PVDF/BaSO4 nanocomposites filled with graphene oxide. MRS Adv. 2019;4:169-175. https://doi.org/10.1557/adv.2018.651
  10. National Institute of Standards and Technology. XCOM: Photon Cross Sections Database [Internet]. NIST; 2023 [cited 2023 Dec 16]. Available from: http://physics.nist.gov/xcom
  11. Sweezy JE, Booth TE, Brown FB, Bull JS, Forster RA III, Goorley JT, et al. MCNP: a general Monte Carlo N-Particle Transport Code, version 5. Volume 2: User's guide (Report No. LA-CP-03-0245). Los Alamos National Laboratory; 2003.
  12. Sayyed MI, Mahmoud KA, Islam S, Tashlykov OL, Lacomme E, Kaky KM. Application of the MCNP 5 code to simulate the shielding features of concrete samples with different aggregates. Radiat Phys Chem. 2020;174:108925.
  13. Sakar E, Ozpolat OF, Alim B, Sayyed MI, Kurudirek M. Phy-X / PSD: development of user-friendly online software for calculation of parameters relevant to radiation shielding and dosimetry. Radiat Phys Chem. 2020;166:108496.
  14. Gokce HS, Gungor O, Yilmaz H. An online software to simulate the shielding properties of materials for neutrons and photons: NGCal. Radiat Phys Chem. 2021;185:109519.
  15. El-Samrah MG, El-Mohandes AM, El-Khayatt AM, Chidiac SE. MRCsC: a user-friendly software for predicting shielding effectiveness against fast neutrons. Radiat Phys Chem. 2021;182:109356.
  16. Aladailah MW, Marashdeh MW, Akhdar H, Tashlykov OL, AlTamimi W, Abu Ghazal A. Investigation of the gamma and neutron radiation properties of strontium bismuth borate glasses doped with neodymium ions using the Geant4 simulation toolkit and EpiXS software. Radiat Eff Defects Solids. 2023;178(3-4):485-499. https://doi.org/10.1080/10420150.2022.2153250
  17. Hila FC, Asuncion-Astronomo A, Dingle CAM, Jecong JFM, Javier-Hila AMV, Gili MBZ, et al. EpiXS: a Windows-based program for photon attenuation, dosimetry and shielding based on EPICS2017 (ENDF/B-VIII) and EPDL97 (ENDF/B-VI.8). Radiat Phys Chem. 2021;182:109331.
  18. Zoller LK. Fast-neutron removal cross sections. Nucleonics. 1964;22(8):128.
  19. Wood J. Computational methods in reactor shielding. Pergamon Press; 1982.
  20. El-Khayatt AM, Abdo AES. MERCSF-N: a program for the calculation of fast neutron removal cross sections in composite shields. Ann Nucl Energy. 2009;36(6):832-836. https://doi.org/10.1016/j.anucene.2009.01.013
  21. Hila FC, Jecong JFM, Dingle CAM, Geraldino GC, Hila AMJ, Guillermo NRD. Generation of fast neutron removal cross sections using a multi-layered spherical shell model. Radiat Phys Chem. 2021;189:109735.
  22. Martin JE. Physics for radiation protection. Wiley; 2000.
  23. Chapman GT, Storrs CL. Effective neutron removal cross sections for shielding. U.S. Atomic Energy Commission, Technical Information Service; 1955.
  24. Singh VP, Badiger NM, Korkut T. Gamma exposure buildup factors and neutron total cross section of ceramic hosts for high level radioactive wastes. Prog Nucl Energy. 2018;104:1-7. https://doi.org/10.1016/j.pnucene.2014.10.007