Research Article
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Year 2024, Volume: 10 Issue: 2, 20 - 26, 31.12.2024

Abstract

Project Number

MYO.23.003

References

  • ALAYLAR, B., AYGÜN, B., TURHAN, K., KARADAYİ, G., ERDEM, Ş., SİNGH, V.P., SAYYED, M.I., PELİT, EMEL., KARABULUT, A., GÜLLÜCE, M., TURGUT, Z., ISAOGLU, M. (2021). Characterization of gamma-ray and neutron radiation absorption properties of synthesized quinoline derivatives and their genotoxic potential. Radiation Physics and Chemistry.184, 109471.
  • AYGÜN, B. (2020). Developed and Produced New Laterite Refractory Brick Samples Protective for Gamma and Neutron Radiation Using GEANT4 Code. Gümüşhane Üniversitesi Fen Bilimleri Dergisi, 10(1), 1-6.
  • AYGÜN, B., & KARABULUT, A. (2018). Development and Production of High Heat Resistant Heavy Concrete Shielding Materials for Neutron and Gamma Radiation. Eastern Anatolian Journal of Science, 4(2), 24-30.
  • AYGÜN, B., & KARABULUT, A. (2022). Investigation of epithermal and fast neutron shielding properties of Some High Entropy Alloys Containing Ti, Hf, Nb, and Zr. Eastern Anatolian Journal of Science, 8(2), 37-44.
  • AYGÜN, B., ALAYLAR, B., TURHAN, K., KARADAYI, M., CINAN, E., TURGUT, Z., … KARABULUT, A. (2024). Evaluation of the protective properties and genotoxic potential of pyrazolo pyridine derivatives against neutron and gamma radiation using the Ames/Salmonella test system. International Journal of Radiation Biology, 100(8), 1213–1225.
  • AYGÜN, B., ALAYLAR, B., TURHAN, K., ŞAKAR, E., KARADAYI, M., AL-SAYYED, M. I. A., ALIM, B. (2020). Investigation of neutron and gamma radiation protective characteristics of synthesizedquinoline derivatives. International Journal of Radiation Biology, 96(11), 1423–1434.
  • AYGÜN, B., ŞAKAR, E., SINGH, V. P., SAYYED, M. I., KORKUT, T., & KARABULUT, A. (2020). Experimental and Monte Carlo simulation study on potential new composite materials to moderate neutron-gamma radiation. Progress in Nuclear Energy, 130.
  • BILICI, İ., AYGÜN, B., DENIZ, C. U., ÖZ, B., SAYYED, M. I., & KARABULUT, A. (2021). Fabrication of novel neutron shieldingmaterials: Polypropylene composites containing colemanite, tincal and ulexite. Progress in Nuclear Energy, 141.
  • EL-KHAYATT, A.M. (2010). Calculation of fast neutron removal cross-sections for some compounds and materials. Annals of Nuclear Energy. 37,2, 218-222.
  • EL-SAMRAH, M.G., NABIL, I.M., SHAMEKH, M.E. (2024). Microstructure and radiation shielding capabilities of Al-Cu and Al-Mn alloys. Scientific Reports. 14, 26721.
  • GAYLAN, Y., AVAR, B., PANIGRAHI, M., AYGÜN, B., & KARABULUT, A. (2023). Effect of the B4C content on microstructure, microhardness, corrosion, and neutron shielding properties of Al–B4C composites. Ceramics International, 49(3), 5479–5488.
  • HERIYANTO, K., SUDJADI, U., ARTIANI, P. A., RACHMADETIN, J., & SETYAWAN, D. (2023). Simulation of neutron shielding performance of Al-Cd alloy for radioactive waste container. In IOP Conference Series: Earth and Environmental Science (Vol. 1201). Institute of Physics.
  • KAEWKHAO, J., KORKUT, T., KORKUT, H., AYGÜN,B., YASAKA,P.,TUSCHAROEN, S., INSİRİPONG, S., KARABULUT, A. (2017). Monte Carlo Design and Experiments on the Neutron Shielding Performances of B2O3–ZnO–Bi2O3 Glass System. Glass Phys Chem 43, 560–563.
  • KURT, G., YAŞAR, NAFIZ. (2020). Comparison of experimental, analytical and simulation results for hot rolling of S275JR quality steel, Journal of Materials Research and Technology, 9(3), 5204-5215.
  • MAKKIABADI, N., & GHIASI, H. (2024). Monte Carlo Simulation and N-XCOM Software Calculation of the Neutron Shielding Parameters for the NCRP Report 144 Recommended Conventional Concretes. Frontiersin Biomedical Technologies, 11(1), 22–30.
  • MANJUNATHA, H. C., SATHISH, K. V., SEENAPPA, L., GUPTA, D., & CECIL RAJ, S. A. (2019). A study of X-ray, gamma and neutron shielding parameters in Si- alloys. Radiation Physics and Chemistry, 165.
  • MİSNED, G.A.L., SUSOY, G., BAYKAL, D.S., ALKARRANİ, H., GÜLER, Ö., TEKİN, H.O. (2024). A closer-look on W and Pb alloys: In-depth evaluation in elastic modulus, gamma-ray, and neutron attenuation for critical applications. Nuclear Engineering and Design. 420, 113063.
  • NOURADDINI-SHAHABADI, A., REZAIE, M.R., HIEDARIZADEH, Y. SAEED, M. (2024). Monte Carlo simulation and practical investigation of body organs activation by Am–Be neutron source. J. Korean Phys. Soc. 84, 672–680.
  • ONAIZI, A.M., AMRAN, M., TANG, W., BETOUSH, N., ALHASSAN, M.; RASHID, R.S., YASIN, M.F., BAYAGOOB, K.H., ONAIZI, S.A. (2024). Radiation-shielding concrete: A review of materials, performance, and the impact of radiation on concrete properties. J. Build. Eng. 97, 110800.
  • QI Z, YANG Z, LI J, GUO Y, YANG G, YU Y, ZHANG J (2022). The Advancement of Neutron-Shielding Materials for the Transportation and Storage of Spent Nuclear Fuel. Materials. 15(9),3255.
  • SABHADIYA, J. (2021). What Is Composite Material?- Definition And Types. Engineering Choice. SAKAR, E., GULER, O., ALIM, B., SAY, Y., & DIKICI, B. (2023). A comprehensive study on structural properties, photon and particle attenuation competence of CoNiFeCr-Ti/Al high entropy alloys (HEAs). Journal of Alloys and Compounds, 931.
  • SATHISH, K. V., SOWMYA, N., MUNIRATHNAM, R., MANJUNATHA, H. C., SEENAPPA, L., & SRIDHAR, K. N. (2023). Radiation shielding properties of aluminium alloys. Radiation Effects and Defects in Solids, 178(9–10), 1301–1320.
  • SAYYED, M.I., AKMAN, F., KAÇAL, M.R., KUMAR, A. (2019). Radiation protective qualities of some selected lead and bismuth salts in the wide gamma energy region. Nuclear Engineering and Technology 51, 860–866.
  • SUKUMARAN, A. K., ZHANG, C., RENGIFO, S., RENFRO, M., GARINO, G., SCOTT, W., … AGARWAL, A. (2024). Tribological and radiation shielding response of novel titanium-boron nitride coatings for lunar structural components. Surface and Coatings Technology, 476.
  • SUN, Y., ZHANG, K., & GONG, G. (2023). Material properties of structural aluminum alloys after exposure to fire. Structures, 55, 2105–2111.
  • WELLİSCH, J.P. (2005). GEANT4, in: Monte Carlo Topical Meeting.
  • YUE, A. T., DEWEY, M. S., GILLIAM, D. M., GREENE, G. L., LAPTEV, A. B., NICO, J. S., SNOW, W. M., WIETFELDT, F. E. (2013). Improved Determination of the Neutron Lifetime. American Physical Society, 111(22), 222501.

Development of New Al-Ni-Cr-W Alloys for Enhanced Neutron Radiation Protection

Year 2024, Volume: 10 Issue: 2, 20 - 26, 31.12.2024

Abstract

Neutron radiation is utilized in many applications such as nuclear therapy, nuclear power plants, material analysis, space research, and more. Neutron leaks can occur in these applications, posing hazards to staff, operators, and therapy patients. Therefore, effective neutron shielding materials are always needed. In this study, two new types of neutron shielding alloy materials were developed, consisting of aluminum, nickel, chromium, tungsten, boron carbide, manganese, molybdenum, and silicium. The chemical composition and weight ratios of the composites were determined using the Monte Carlo Simulation’s GEANT4 code. Mixing and molding methods were employed in the production of the alloys. Important neutron shielding parameters, such as the effective removal cross-section, half-value layer, mean free path, and radiation protection efficiency, were theoretically determined using the GEANT4 code. Additionally, fast neutron absorption capacities were measured using an Am-Be fast neutron source and a BF3 portable neutron detector. The results were compared with 316 LN stainless steel. All new alloy samples were determined to have better fast neutron shielding capabilities than these reference samples. It was also observed that the new alloy samples exhibit both high-temperature resistance and mechanical durability. It is suggested that these new alloy samples can be used in neutron radiation shielding applications such as nuclear reactors, radioactive waste storage, and nuclear shelters.

Ethical Statement

auto_awesome Bunu mu demek istediniz? Tüm yazarlar olarak bu makalenin bir dergide yayınlanmasını kabul ediyoruz 73 / 5.000 All authors agree to have this article published in this journal.

Supporting Institution

Scientific and Technological Research Council of Ağrı İbrahim Çeçen University (BAP)

Project Number

MYO.23.003

Thanks

Thank you very much for supporting Scientific and Technological Research Council of Ağrı İbrahim Çeçen University (BAP)

References

  • ALAYLAR, B., AYGÜN, B., TURHAN, K., KARADAYİ, G., ERDEM, Ş., SİNGH, V.P., SAYYED, M.I., PELİT, EMEL., KARABULUT, A., GÜLLÜCE, M., TURGUT, Z., ISAOGLU, M. (2021). Characterization of gamma-ray and neutron radiation absorption properties of synthesized quinoline derivatives and their genotoxic potential. Radiation Physics and Chemistry.184, 109471.
  • AYGÜN, B. (2020). Developed and Produced New Laterite Refractory Brick Samples Protective for Gamma and Neutron Radiation Using GEANT4 Code. Gümüşhane Üniversitesi Fen Bilimleri Dergisi, 10(1), 1-6.
  • AYGÜN, B., & KARABULUT, A. (2018). Development and Production of High Heat Resistant Heavy Concrete Shielding Materials for Neutron and Gamma Radiation. Eastern Anatolian Journal of Science, 4(2), 24-30.
  • AYGÜN, B., & KARABULUT, A. (2022). Investigation of epithermal and fast neutron shielding properties of Some High Entropy Alloys Containing Ti, Hf, Nb, and Zr. Eastern Anatolian Journal of Science, 8(2), 37-44.
  • AYGÜN, B., ALAYLAR, B., TURHAN, K., KARADAYI, M., CINAN, E., TURGUT, Z., … KARABULUT, A. (2024). Evaluation of the protective properties and genotoxic potential of pyrazolo pyridine derivatives against neutron and gamma radiation using the Ames/Salmonella test system. International Journal of Radiation Biology, 100(8), 1213–1225.
  • AYGÜN, B., ALAYLAR, B., TURHAN, K., ŞAKAR, E., KARADAYI, M., AL-SAYYED, M. I. A., ALIM, B. (2020). Investigation of neutron and gamma radiation protective characteristics of synthesizedquinoline derivatives. International Journal of Radiation Biology, 96(11), 1423–1434.
  • AYGÜN, B., ŞAKAR, E., SINGH, V. P., SAYYED, M. I., KORKUT, T., & KARABULUT, A. (2020). Experimental and Monte Carlo simulation study on potential new composite materials to moderate neutron-gamma radiation. Progress in Nuclear Energy, 130.
  • BILICI, İ., AYGÜN, B., DENIZ, C. U., ÖZ, B., SAYYED, M. I., & KARABULUT, A. (2021). Fabrication of novel neutron shieldingmaterials: Polypropylene composites containing colemanite, tincal and ulexite. Progress in Nuclear Energy, 141.
  • EL-KHAYATT, A.M. (2010). Calculation of fast neutron removal cross-sections for some compounds and materials. Annals of Nuclear Energy. 37,2, 218-222.
  • EL-SAMRAH, M.G., NABIL, I.M., SHAMEKH, M.E. (2024). Microstructure and radiation shielding capabilities of Al-Cu and Al-Mn alloys. Scientific Reports. 14, 26721.
  • GAYLAN, Y., AVAR, B., PANIGRAHI, M., AYGÜN, B., & KARABULUT, A. (2023). Effect of the B4C content on microstructure, microhardness, corrosion, and neutron shielding properties of Al–B4C composites. Ceramics International, 49(3), 5479–5488.
  • HERIYANTO, K., SUDJADI, U., ARTIANI, P. A., RACHMADETIN, J., & SETYAWAN, D. (2023). Simulation of neutron shielding performance of Al-Cd alloy for radioactive waste container. In IOP Conference Series: Earth and Environmental Science (Vol. 1201). Institute of Physics.
  • KAEWKHAO, J., KORKUT, T., KORKUT, H., AYGÜN,B., YASAKA,P.,TUSCHAROEN, S., INSİRİPONG, S., KARABULUT, A. (2017). Monte Carlo Design and Experiments on the Neutron Shielding Performances of B2O3–ZnO–Bi2O3 Glass System. Glass Phys Chem 43, 560–563.
  • KURT, G., YAŞAR, NAFIZ. (2020). Comparison of experimental, analytical and simulation results for hot rolling of S275JR quality steel, Journal of Materials Research and Technology, 9(3), 5204-5215.
  • MAKKIABADI, N., & GHIASI, H. (2024). Monte Carlo Simulation and N-XCOM Software Calculation of the Neutron Shielding Parameters for the NCRP Report 144 Recommended Conventional Concretes. Frontiersin Biomedical Technologies, 11(1), 22–30.
  • MANJUNATHA, H. C., SATHISH, K. V., SEENAPPA, L., GUPTA, D., & CECIL RAJ, S. A. (2019). A study of X-ray, gamma and neutron shielding parameters in Si- alloys. Radiation Physics and Chemistry, 165.
  • MİSNED, G.A.L., SUSOY, G., BAYKAL, D.S., ALKARRANİ, H., GÜLER, Ö., TEKİN, H.O. (2024). A closer-look on W and Pb alloys: In-depth evaluation in elastic modulus, gamma-ray, and neutron attenuation for critical applications. Nuclear Engineering and Design. 420, 113063.
  • NOURADDINI-SHAHABADI, A., REZAIE, M.R., HIEDARIZADEH, Y. SAEED, M. (2024). Monte Carlo simulation and practical investigation of body organs activation by Am–Be neutron source. J. Korean Phys. Soc. 84, 672–680.
  • ONAIZI, A.M., AMRAN, M., TANG, W., BETOUSH, N., ALHASSAN, M.; RASHID, R.S., YASIN, M.F., BAYAGOOB, K.H., ONAIZI, S.A. (2024). Radiation-shielding concrete: A review of materials, performance, and the impact of radiation on concrete properties. J. Build. Eng. 97, 110800.
  • QI Z, YANG Z, LI J, GUO Y, YANG G, YU Y, ZHANG J (2022). The Advancement of Neutron-Shielding Materials for the Transportation and Storage of Spent Nuclear Fuel. Materials. 15(9),3255.
  • SABHADIYA, J. (2021). What Is Composite Material?- Definition And Types. Engineering Choice. SAKAR, E., GULER, O., ALIM, B., SAY, Y., & DIKICI, B. (2023). A comprehensive study on structural properties, photon and particle attenuation competence of CoNiFeCr-Ti/Al high entropy alloys (HEAs). Journal of Alloys and Compounds, 931.
  • SATHISH, K. V., SOWMYA, N., MUNIRATHNAM, R., MANJUNATHA, H. C., SEENAPPA, L., & SRIDHAR, K. N. (2023). Radiation shielding properties of aluminium alloys. Radiation Effects and Defects in Solids, 178(9–10), 1301–1320.
  • SAYYED, M.I., AKMAN, F., KAÇAL, M.R., KUMAR, A. (2019). Radiation protective qualities of some selected lead and bismuth salts in the wide gamma energy region. Nuclear Engineering and Technology 51, 860–866.
  • SUKUMARAN, A. K., ZHANG, C., RENGIFO, S., RENFRO, M., GARINO, G., SCOTT, W., … AGARWAL, A. (2024). Tribological and radiation shielding response of novel titanium-boron nitride coatings for lunar structural components. Surface and Coatings Technology, 476.
  • SUN, Y., ZHANG, K., & GONG, G. (2023). Material properties of structural aluminum alloys after exposure to fire. Structures, 55, 2105–2111.
  • WELLİSCH, J.P. (2005). GEANT4, in: Monte Carlo Topical Meeting.
  • YUE, A. T., DEWEY, M. S., GILLIAM, D. M., GREENE, G. L., LAPTEV, A. B., NICO, J. S., SNOW, W. M., WIETFELDT, F. E. (2013). Improved Determination of the Neutron Lifetime. American Physical Society, 111(22), 222501.
There are 27 citations in total.

Details

Primary Language English
Subjects Material Physics, Nuclear Physics
Journal Section makaleler
Authors

Bünyamin Aygün 0000-0002-9384-1540

Ebru Akdemir

Mansur Albayrak

Yüksel Özdemir

Abdulhalik Karabulut

Project Number MYO.23.003
Early Pub Date December 28, 2024
Publication Date December 31, 2024
Submission Date November 6, 2024
Acceptance Date December 23, 2024
Published in Issue Year 2024 Volume: 10 Issue: 2

Cite

APA Aygün, B., Akdemir, E., Albayrak, M., Özdemir, Y., et al. (2024). Development of New Al-Ni-Cr-W Alloys for Enhanced Neutron Radiation Protection. Eastern Anatolian Journal of Science, 10(2), 20-26.
AMA Aygün B, Akdemir E, Albayrak M, Özdemir Y, Karabulut A. Development of New Al-Ni-Cr-W Alloys for Enhanced Neutron Radiation Protection. Eastern Anatolian Journal of Science. December 2024;10(2):20-26.
Chicago Aygün, Bünyamin, Ebru Akdemir, Mansur Albayrak, Yüksel Özdemir, and Abdulhalik Karabulut. “Development of New Al-Ni-Cr-W Alloys for Enhanced Neutron Radiation Protection”. Eastern Anatolian Journal of Science 10, no. 2 (December 2024): 20-26.
EndNote Aygün B, Akdemir E, Albayrak M, Özdemir Y, Karabulut A (December 1, 2024) Development of New Al-Ni-Cr-W Alloys for Enhanced Neutron Radiation Protection. Eastern Anatolian Journal of Science 10 2 20–26.
IEEE B. Aygün, E. Akdemir, M. Albayrak, Y. Özdemir, and A. Karabulut, “Development of New Al-Ni-Cr-W Alloys for Enhanced Neutron Radiation Protection”, Eastern Anatolian Journal of Science, vol. 10, no. 2, pp. 20–26, 2024.
ISNAD Aygün, Bünyamin et al. “Development of New Al-Ni-Cr-W Alloys for Enhanced Neutron Radiation Protection”. Eastern Anatolian Journal of Science 10/2 (December 2024), 20-26.
JAMA Aygün B, Akdemir E, Albayrak M, Özdemir Y, Karabulut A. Development of New Al-Ni-Cr-W Alloys for Enhanced Neutron Radiation Protection. Eastern Anatolian Journal of Science. 2024;10:20–26.
MLA Aygün, Bünyamin et al. “Development of New Al-Ni-Cr-W Alloys for Enhanced Neutron Radiation Protection”. Eastern Anatolian Journal of Science, vol. 10, no. 2, 2024, pp. 20-26.
Vancouver Aygün B, Akdemir E, Albayrak M, Özdemir Y, Karabulut A. Development of New Al-Ni-Cr-W Alloys for Enhanced Neutron Radiation Protection. Eastern Anatolian Journal of Science. 2024;10(2):20-6.