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Investigation of W, Pb, and Bi elements from neutron shielding point of view

Year 2024, Volume: 13 Issue: 3, 214 - 220, 31.12.2024
https://doi.org/10.54187/jnrs.1568210

Abstract

This study investigates the performances of tungsten, lead, and bismuth elements, which are widely used for shielding gamma-ray, from the neutron shielding point of view using the Monte Carlo N-Particle (MCNP6.2) simulation code. The study analyzed the neutron shielding capacities of Al matrix composites containing 30% W, Pb, and Bi. In addition, the shielding properties of secondary gamma-ray with an energy of 0.478 MeV resulting from neutron-boron interaction were also investigated. The results show that for thermal and intermediate energy neutrons, Al-30%W composite gives very good results by separating from Al-30%Pb and Al-30%Bi composites. However, Al-%30Pb and Al-%30Bi composites are also effective for fast neutrons. Regarding the gamma-ray, it was calculated that the Al-30%Pb composite exhibited the highest shielding performance. These findings provide important data on the contribution of W, Pb, and Bi elements used as gamma-ray shielding to neutron shielding in different neutron energy ranges and reveal that these elements should be used strategically with appropriate combinations depending on the neutron energy in neutron shielding designs.

References

  • S. Cong, G. Ran, Y. Li, Y. Chen, Ball-milling properties and sintering behavior of Al-based Gd2O3–W shielding materials used in spent-fuel storage, Powder Technology 369 (2020) 127–136.
  • J. Dumazert, R. Coulon, Q. Lecomte, G. H. V. Bertrand, M. Hamel, Gadolinium for neutron detection in current nuclear instrumentation research: A review, Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 882 (2018) 53–68.
  • Y. S. Rammah, I. O. Olarinoye, F. I. El-Agawany, A. El-Adawy, E. S. Yousef, The f-factor, neutron, gamma radiation and proton shielding competences of glasses with Pb or Pb/Bi heavy elements for nuclear protection applications, Ceramics International 46 (2020) 27163–27174.
  • N. Ekinci, K. A. Mahmoud, S. Sarıtaş, B. Aygün, M. M. Hessien, I. Bilici, Y. S. Rammah, Development of Tincal based polypropylene polymeric materials for radiation shielding applications: Experimental, theoretical, and Monte Carlo investigations, Materials Science in Semiconductor Processing 146 (2022) 106696.
  • Y. Wang, W. Xiao, J. Huang, S. Zou, J. Liu, Z. Ren, S. Liu, Y. Liu, Y. Huang, Microstructure, mechanical and corrosion property of neutron and γ-ray shielding (Gd2O3+W)/Al composites, Ceramics International 50 (2024) 41448–41460.
  • Y. Gaylan, A. Bozkurt, Investigating Thermal Neutron and Gamma Ray Shielding Properties of Al Matrix Gd2O3-and W-Doped Composites Using Monte Carlo Simulations, Süleyman Demirel University Faculty of Arts and Science Journal of Science 19 (2024) 75–85.
  • E. Salama, A. Maher, G. M. Youssef, Gamma radiation and neutron shielding properties of transparent alkali borosilicate glass containing lead, Journal of Physics and Chemistry of Solids 131 (2019) 139–147.
  • F. Akman, H. Ozdogan, O. Kilicoglu, H. Ogul, O. Agar, M. R. Kacal, H. Polat, A. Tursucu, Gamma, charged particle and neutron radiation shielding capacities of ternary composites having polyester/barite/tungsten boride, Radiation Physics and Chemistry 212 (2023) 111120.
  • Q. Shao, Q. Zhu, Y. Wang, S. Kuang, J. Bao, S. Liu, Development and application analysis of high-energy neutron radiation shielding materials from tungsten boron polyethylene, Nuclear Engineering and Technology 56 (2024) 2153–2162.
  • K. Schweda, D. Schmidt, Improved response function calculations for scintillation detectors using an extended version of the MCNP code, Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 476 (2002) 155–159.
  • R. Taghavi, H. R. Mirzaei, S. M. R. Aghamiri, P. Hajian, Calculating the absorbed dose by thyroid in breast cancer radiotherapy using MCNP-4C code, Radiation Physics and Chemistry 130 (2017) 12–14.
  • R. G. Abrefah, R. B. M. Sogbadji, E. Ampomah-Amoako, S. A. Birikorang, H. C. Odoi, B. J. B. Nyarko, Design of boron carbide-shielded irradiation channel of the outer irradiation channel of the Ghana Research Reactor-1 using MCNP, Applied Radiation and Isotopes 69 (2011) 85–89.
  • M. H. A. Mhareb, Y. S. M. Alajerami, M. I. Sayyed, K. A. Mahmoud, T. Ghrib, M. K. Hamad, Q. A. Drmosh, N. Sfina, M. A. Almessiere, Morphological, optical, structural, mechanical, and radiation-shielding properties of borosilicate glass–ceramic system, Ceramics International 48 (2022) 35227–35236.
  • C. Kursun, M. Gao, A. O. Yalcin, K. A. Parrey, Y. Gaylan, Structure, mechanical, and neutron radiation shielding characteristics of mechanically milled nanostructured (100-x)Al-xGd2O3 metal composites, Ceramics International 50 (2024) 27154–27164.
  • X. Lian, W. Xu, P. Zhang, W. Wang, L. Xie, X. Chen, Design and mechanical properties of SiC reinforced Gd2O3/6061Al neutron shielding composites, Ceramics International 49 (2023) 27707–27715.
  • H. Ghninou, A. Gruel, A. Lyoussi, C. Reynard-Carette, C. El Younoussi, B. El Bakkari, Y. Boulaich, Evaluation of the CNESTEN’s TRIGA Mark II research reactor physical parameters with TRIPOLI-4® and MCNP, Nuclear Engineering and Technology 55 (2023) 4447–4464.
  • M. F. L’Annunziata, Radioactivity: Introduction and History, From the Quantum to Quarks: Second Edition, Elsevier Inc., 2016.
  • Nuclear Data Center at KAERI, https://atom.kaeri.re.kr/, Accessed 9 Dec 2024
Year 2024, Volume: 13 Issue: 3, 214 - 220, 31.12.2024
https://doi.org/10.54187/jnrs.1568210

Abstract

References

  • S. Cong, G. Ran, Y. Li, Y. Chen, Ball-milling properties and sintering behavior of Al-based Gd2O3–W shielding materials used in spent-fuel storage, Powder Technology 369 (2020) 127–136.
  • J. Dumazert, R. Coulon, Q. Lecomte, G. H. V. Bertrand, M. Hamel, Gadolinium for neutron detection in current nuclear instrumentation research: A review, Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 882 (2018) 53–68.
  • Y. S. Rammah, I. O. Olarinoye, F. I. El-Agawany, A. El-Adawy, E. S. Yousef, The f-factor, neutron, gamma radiation and proton shielding competences of glasses with Pb or Pb/Bi heavy elements for nuclear protection applications, Ceramics International 46 (2020) 27163–27174.
  • N. Ekinci, K. A. Mahmoud, S. Sarıtaş, B. Aygün, M. M. Hessien, I. Bilici, Y. S. Rammah, Development of Tincal based polypropylene polymeric materials for radiation shielding applications: Experimental, theoretical, and Monte Carlo investigations, Materials Science in Semiconductor Processing 146 (2022) 106696.
  • Y. Wang, W. Xiao, J. Huang, S. Zou, J. Liu, Z. Ren, S. Liu, Y. Liu, Y. Huang, Microstructure, mechanical and corrosion property of neutron and γ-ray shielding (Gd2O3+W)/Al composites, Ceramics International 50 (2024) 41448–41460.
  • Y. Gaylan, A. Bozkurt, Investigating Thermal Neutron and Gamma Ray Shielding Properties of Al Matrix Gd2O3-and W-Doped Composites Using Monte Carlo Simulations, Süleyman Demirel University Faculty of Arts and Science Journal of Science 19 (2024) 75–85.
  • E. Salama, A. Maher, G. M. Youssef, Gamma radiation and neutron shielding properties of transparent alkali borosilicate glass containing lead, Journal of Physics and Chemistry of Solids 131 (2019) 139–147.
  • F. Akman, H. Ozdogan, O. Kilicoglu, H. Ogul, O. Agar, M. R. Kacal, H. Polat, A. Tursucu, Gamma, charged particle and neutron radiation shielding capacities of ternary composites having polyester/barite/tungsten boride, Radiation Physics and Chemistry 212 (2023) 111120.
  • Q. Shao, Q. Zhu, Y. Wang, S. Kuang, J. Bao, S. Liu, Development and application analysis of high-energy neutron radiation shielding materials from tungsten boron polyethylene, Nuclear Engineering and Technology 56 (2024) 2153–2162.
  • K. Schweda, D. Schmidt, Improved response function calculations for scintillation detectors using an extended version of the MCNP code, Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 476 (2002) 155–159.
  • R. Taghavi, H. R. Mirzaei, S. M. R. Aghamiri, P. Hajian, Calculating the absorbed dose by thyroid in breast cancer radiotherapy using MCNP-4C code, Radiation Physics and Chemistry 130 (2017) 12–14.
  • R. G. Abrefah, R. B. M. Sogbadji, E. Ampomah-Amoako, S. A. Birikorang, H. C. Odoi, B. J. B. Nyarko, Design of boron carbide-shielded irradiation channel of the outer irradiation channel of the Ghana Research Reactor-1 using MCNP, Applied Radiation and Isotopes 69 (2011) 85–89.
  • M. H. A. Mhareb, Y. S. M. Alajerami, M. I. Sayyed, K. A. Mahmoud, T. Ghrib, M. K. Hamad, Q. A. Drmosh, N. Sfina, M. A. Almessiere, Morphological, optical, structural, mechanical, and radiation-shielding properties of borosilicate glass–ceramic system, Ceramics International 48 (2022) 35227–35236.
  • C. Kursun, M. Gao, A. O. Yalcin, K. A. Parrey, Y. Gaylan, Structure, mechanical, and neutron radiation shielding characteristics of mechanically milled nanostructured (100-x)Al-xGd2O3 metal composites, Ceramics International 50 (2024) 27154–27164.
  • X. Lian, W. Xu, P. Zhang, W. Wang, L. Xie, X. Chen, Design and mechanical properties of SiC reinforced Gd2O3/6061Al neutron shielding composites, Ceramics International 49 (2023) 27707–27715.
  • H. Ghninou, A. Gruel, A. Lyoussi, C. Reynard-Carette, C. El Younoussi, B. El Bakkari, Y. Boulaich, Evaluation of the CNESTEN’s TRIGA Mark II research reactor physical parameters with TRIPOLI-4® and MCNP, Nuclear Engineering and Technology 55 (2023) 4447–4464.
  • M. F. L’Annunziata, Radioactivity: Introduction and History, From the Quantum to Quarks: Second Edition, Elsevier Inc., 2016.
  • Nuclear Data Center at KAERI, https://atom.kaeri.re.kr/, Accessed 9 Dec 2024
There are 18 citations in total.

Details

Primary Language English
Subjects Material Physics, Nuclear Physics, Radiation and Matter
Journal Section Articles
Authors

Yasin Gaylan 0000-0003-1354-7593

Publication Date December 31, 2024
Submission Date October 16, 2024
Acceptance Date December 19, 2024
Published in Issue Year 2024 Volume: 13 Issue: 3

Cite

APA Gaylan, Y. (2024). Investigation of W, Pb, and Bi elements from neutron shielding point of view. Journal of New Results in Science, 13(3), 214-220. https://doi.org/10.54187/jnrs.1568210
AMA Gaylan Y. Investigation of W, Pb, and Bi elements from neutron shielding point of view. JNRS. December 2024;13(3):214-220. doi:10.54187/jnrs.1568210
Chicago Gaylan, Yasin. “Investigation of W, Pb, and Bi Elements from Neutron Shielding Point of View”. Journal of New Results in Science 13, no. 3 (December 2024): 214-20. https://doi.org/10.54187/jnrs.1568210.
EndNote Gaylan Y (December 1, 2024) Investigation of W, Pb, and Bi elements from neutron shielding point of view. Journal of New Results in Science 13 3 214–220.
IEEE Y. Gaylan, “Investigation of W, Pb, and Bi elements from neutron shielding point of view”, JNRS, vol. 13, no. 3, pp. 214–220, 2024, doi: 10.54187/jnrs.1568210.
ISNAD Gaylan, Yasin. “Investigation of W, Pb, and Bi Elements from Neutron Shielding Point of View”. Journal of New Results in Science 13/3 (December 2024), 214-220. https://doi.org/10.54187/jnrs.1568210.
JAMA Gaylan Y. Investigation of W, Pb, and Bi elements from neutron shielding point of view. JNRS. 2024;13:214–220.
MLA Gaylan, Yasin. “Investigation of W, Pb, and Bi Elements from Neutron Shielding Point of View”. Journal of New Results in Science, vol. 13, no. 3, 2024, pp. 214-20, doi:10.54187/jnrs.1568210.
Vancouver Gaylan Y. Investigation of W, Pb, and Bi elements from neutron shielding point of view. JNRS. 2024;13(3):214-20.


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