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Original Research

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

원문정보

초록

영어

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.

목차

ABSTRACT
Introduction
Materials and Methods
Results and Discussion
1. Mass Attenuation Coefficient
2. Mean Free Path
3. Effective Atomic Number
4. The Fast Neutrons Macroscopic Effective Removal Cross-Section
5. The Dose Equivalent Rate and Gamma Transmission Factor
Conclusion
Conflict of Interest
Acknowledgements
Ethical Statement
Author Contribution
References

저자정보

  • Ayman Abu Ghazal Jordan Atomic Energy Commission, Amman, Jordan
  • Rawand Alakash Jordan Atomic Energy Commission, Amman, Jordan
  • Zainab Aljumaili Physics Department, Hashemite University, Zarqa, Jordan
  • Ahmed El-Sayed Department of Nuclear Engineering, Alexandria University, Alexandria, Egypt
  • Hamza Abdel-Rahman Jordan Atomic Energy Commission, Amman, Jordan

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