Investigating Thermal Neutron and Gamma Ray Shielding Properties of Al Matrix Gd2O3-and W-Doped Composites Using Monte Carlo Simulations

Abstract

This study aimed to calculate the thermal neutron (0.0253 eV) total macroscopic cross-section and gamma-ray (1.25 MeV) linear absorption coefficient for (100-x)Al-xGd2O3 (x=5 to 50) and 100-(x+y)Al-xGd2O3+yW (x,y=5 to 50) composites using MCNP6.2 simulation code. The simulation consists of a mono-energy point neutron and gamma-ray source, target material, and detector. The F4 tally from the MCNP6.2 library was used as the detector. The results show the highest thermal neutron total macroscopic cross-section for the 50%Al-50%Gd2O3 composite and the highest linear absorption coefficient for the 50%Al-%5Gd2O3-45%W composite. The results of this study provide a good understanding of the thermal neutron and gamma ray the shielding capabilities of Al matrix Gd2O3 and W doped composites.

Keywords

• Al-Gd2O3-W composites
• Neutron shielding
• Gama shielding
• Monte Carlo simulations

References

1. E. G. Aydın, E. Tel, A. Kaplan, and A. Aydin, "Equilibrium and pre-equilibrium calculations of neutron production in medium-heavy targets irradiated by protons up to 100 MeV," Annals of Nuclear Energy, 35(12), 2306–2312, 2008.
2. M. M. Castellanos, A. McAuley, and J. E. Curtis, "Investigating Structure and Dynamics of Proteins in Amorphous Phases Using Neutron Scattering," Computational and Structural Biotechnology Journal, 15, 117–130, 2017.
3. A. Lombardi, D. Sediako, A. Machin, C. Ravindran, and R. MacKay, "Transient analysis of residual strain during heat treatment of multi-material engine blocks using in-situ neutron diffraction," Materials Letters, 157, 50–52, 2015.
4. F. Mireles, J. I. Davila, J. L. Pinedo, E. Reyes, R. J. Speakman, and M. D. Glascock, "Assessing urban soil pollution in the cities of Zacatecas and Guadalupe, Mexico by instrumental neutron activation analysis," Microchemical Journal, 103, 158–164, 2012.
5. T. Örs, F. Gouraud, R. Guinebretière, M. Huger, V. Michel, and O. Castelnau, "Neutron diffraction measurements of residual stress distribution in large zirconia based refractory bricks produced by electro-fusion and casting," Journal of the European Ceramic Society, 37(5), 2295–2302, 2017.
6. T. Seymour, P. Frankel, L. Balogh, T. Ungár, S. P. Thompson, D. Jädernäs, J. Romero, L. Hallstadius, M. R. Daymond, G. Ribárik, and M. Preuss, "Evolution of dislocation structure in neutron irradiated Zircaloy-2 studied by synchrotron x-ray diffraction peak profile analysis," Acta Materialia, 126, 102–113, 2017.
7. P. Schofield, B. Geiger, K. Sim, and A. J. Einstein, "ICRP Tahunan," 1–125, 2012.
8. ICRP, "Annals of the International Commission on Radiological Protection, ICRP Publication 103," Ann. ICRP, 37(3–4), 332, 2007.

9. R. C. Baumann and E. B. Smith, "Neutron-induced boron fission as a major source of soft errors in deep submicron SRAM devices," 2000 IEEE International Reliability Physics Symposium Proceedings, 152–157, 2000.
10. S. Normand, B. Mouanda, S. Haan, and M. Louvel, "Discrimination methods between neutron and gamma rays for boron loaded plastic scintillators," Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 484(1–3), 342–350, 2002.
11. M. Bastürk, J. Arztmann, W. Jerlich, N. Kardjilov, E. Lehmann, and M. Zawisky, "Analysis of neutron attenuation in boron-alloyed stainless steel with neutron radiography and JEN-3 gauge," Journal of Nuclear Materials, 341(2–3), 189–200, 2005.
12. A. Nishimura, Y. Izumi, M. Imaizumi, S. Nishijima, T. Hemmi, and T. Shikama, "Neutron and gamma ray irradiation effects on interlaminar shear strength of insulation materials with cyanate ester-epoxy blended resin," Fusion Engineering and Design, 86(6–8), 1558–1561, 2011.
13. Y. Tanabe, E. Yasuda, S. Kimura, T. Iseki, T. Maruyama, and T. Yano, "Neutron irradiation effects on dimension and mechanical properties of carbon fiber/carbon composite," Carbon, 29(7), 905–908, 1991.
14. R. Lo Frano, G. Pugliese, and G. Forasassi, "Thermal analysis of a spent fuel cask in different transport conditions," Energy, 36(4), 2285–2293, 2011.
15. F. Tang, X. Wu, S. Ge, J. Ye, H. Zhu, M. Hagiwara, and J. M. Schoenung, "Dry sliding friction and wear properties of B4C particulate-reinforced Al-5083 matrix composites," Wear, 264(7–8), 555–561, 2008.
16. M. Alizadeh, "Strengthening mechanisms in particulate Al/B4C composites produced by repeated roll bonding process," Journal of Alloys and Compounds, 509(5), 2243–2247, 2011.
17. M. Khakbiz and F. Akhlaghi, "Synthesis and structural characterization of Al-B4C nano-composite powders by mechanical alloying," Journal of Alloys and Compounds, 479(1–2), 334–341, 2009.
18. A. Yazdani and E. Salahinejad, "Evolution of reinforcement distribution in Al-B4C composites during accumulative roll bonding," Materials and Design, 32(6), 3137–3142, 2011.
19. K. Deng, J. Shi, C. Wang, X. Wang, Y. Wu, K. Nie, and K. Wu, "Composites : Part A Microstructure and strengthening mechanism of bimodal size particle reinforced magnesium matrix composite," Composites Part A, 43(8), 1280–1284, 2012.
20. G. Luo, J. Wu, S. Xiong, Q. Shen, and C. Wu, "Microstructure and mechanical behavior of AA2024 / B 4 C composites with a network reinforcement architecture," Journal of Alloys and Compounds, 701, 554–561, 2017.
21. I. Topcu, H. O. Gulsoy, N. Kadioglu, and A. N. Gulluoglu, "Processing and mechanical properties of B4C reinforced Al matrix composites," Journal of Alloys and Compounds, 482(1–2), 516–521, 2009.
22. H. S. Chen, W. X. Wang, Y. L. Li, P. Zhang, H. H. Nie, and Q. C. Wu, "The design, microstructure and tensile properties of B4C particulate reinforced 6061Al neutron absorber composites," Journal of Alloys and Compounds, 632, 23–29, 2015.
23. P. Zhang, Y. Li, W. Wang, Z. Gao, and B. Wang, "The design, fabrication and properties of B4C/Al neutron absorbers," Journal of Nuclear Materials, 437(1–3), 350–358, 2013.
24. H. S. Chen, W. X. Wang, Y. L. Li, J. Zhou, H. H. Nie, and Q. C. Wu, "The design, microstructure and mechanical properties of B4C/6061Al neutron absorber composites fabricated by SPS," Materials and Design, 94, 360–367, 2016.
25. Y. Gaylan, B. Avar, M. Panigrahi, B. Aygün, and A. Karabulut, "Effect of the B4C content on microstructure, microhardness, corrosion, and neutron shielding properties of Al–B4C composites," Ceramics International, 49(3), 5479–5488, 2023.
26. F. Zhang, X. Wang, J. B. Wierschke, and L. Wang, "Helium bubble evolution in ion irradiated Al/B4C metal metrix composite," Scripta Materialia, 109, 28–33, 2015.
27. R. G. Abrefah, R. B. M. Sogbadji, E. Ampomah-Amoako, S. A. Birikorang, H. C. Odoi, and B. J. B. Nyarko, "Comparison of the effects of cadmium-shielded and boron carbide-shielded irradiation channel of the Ghana Research Reactor-1," Nuclear Engineering and Design, 241(8), 3017–3020, 2011.
28. S. Wan, W. Wang, H. Chen, J. Zhou, Y. Zhang, R. Liu, and R. Feng, "155/157Gd areal density: A model for design and fabrication of Gd2O3/316L novel neutron shielding composites," Vacuum, 176, 2020.
29. R. Florez, H. A. Colorado, C. H. C. Giraldo, and A. Alajo, "Preparation and characterization of Portland cement pastes with Sm2O3 microparticle additions for neutron shielding applications," Construction and Building Materials, 191, 498–506, 2018.
30. Z. G. Xu, L. T. Jiang, Q. Zhang, J. Qiao, D. Gong, and G. H. Wu, "The design of a novel neutron shielding B4C/Al composite containing Gd," Materials and Design, 111, 375–381, 2016.
31. L. T. Jiang, Z. G. Xu, Y. K. Fei, Q. Zhang, J. Qiao, and G. H. Wu, "The design of novel neutron shielding (Gd+B4C)/6061Al composites and its properties after hot rolling," Composites Part B: Engineering, 168, 183–194, 2019.
32. Y. Li, W. Wang, J. Zhou, H. Chen, and P. Zhang, "10B areal density: A novel approach for design and fabrication of B4C/6061Al neutron absorbing materials," Journal of Nuclear Materials, 487, 238–246, 2017.
33. J. J. Park, S. M. Hong, M. K. Lee, C. K. Rhee, and W. H. Rhee, "Enhancement in the microstructure and neutron shielding efficiency of sandwich type of 6061Al-B4C composite material via hot isostatic pressing," Nuclear Engineering and Design, 282, 1–7, 2015.
34. P. Zhang, J. Li, W. xian Wang, X. yue Tan, L. Xie, and F. yun Guo, "The design, microstructure and mechanical properties of a novel Gd2O3/6061Al neutron shielding composite," Vacuum, 162(January), 92–100, 2019.
35. S. Cong, Y. Li, G. Ran, W. Zhou, and Q. Feng, "Microstructure and its effect on mechanical and thermal properties of Al-based Gd2O3 MMCs used as shielding materials in spent fuel storage," Ceramics International, 46(9), 12986–12995, 2020.
36. K. Karimi-Shahri, L. Rafat-Motavalli, and H. Miri-Hakimabad, "Finding a suitable shield for mixed neutron and photon fields based on an Am-Be source," Journal of Radioanalytical and Nuclear Chemistry, 298(1), 33–39, 2013.
37. H. Turkez, B. Cakmak, and K. Celik, "Evaluation of the Potential In Vivo Genotoxicity of Tungsten (VI) Oxide Nanopowder for Human Health," Key Engineering Materials, 543, 89–92, 2013.
38. S. M. Hulbert and K. A. Carlson, "Is lead dust within nuclear medicine departments a hazard to pediatric patients?," Journal of Nuclear Medicine Technology, 37(3), 170–172, 2009.
39. V. F. Sears, "Neutron News Neutron scattering lengths and cross sections," Neutron News, 1992.
40. S. Cong, G. Ran, Y. Li, and Y. Chen, "Ball-milling properties and sintering behavior of Al-based Gd2O3–W shielding materials used in spent-fuel storage," Powder Technology, 369, 127–136, 2020.
41. C. J. Werner, J. S. Bull, C. J. Solomon, F. B. Brown, G. W. McKinney, M. E. Rising, D. A. Dixon, R. L. Martz, H. G. Hughes, L. J. Cox, A. J. Zukaitis, J. C. Armstrong, R. A. Forster, and L. Casswell, "MCNP Version 6.2 Release Notes," 2018.
42. M. I. Sayyed, K. A. Mahmoud, S. Islam, O. L. Tashlykov, E. Lacomme, and K. M. Kaky, "Application of the MCNP 5 code to simulate the shielding features of concrete samples with different aggregates," Radiation Physics and Chemistry, 174(March), 108925, 2020.
43. R. El-Mallawany, M. I. Sayyed, M. G. Dong, and Y. S. Rammah, "Simulation of radiation shielding properties of glasses contain PbO," Radiation Physics and Chemistry, 151, 239–252, 2018.
44. R. B. Malidarre, H. O. Tekin, Gunuglu Kadir, and H. Akyıldırım, "Assessment of Gamma Ray Shielding Properties for Skin," International Journal of Computational and Experimental Science and Engineering, 9(1), 6–10, 2023.
45. B. Oruncak, "Computation of Neutron Coefficients for B2O3 reinforced Composite," International Journal of Computational and Experimental Science and Engineering, 9(2), 50–53, 2023.
46. Z. Aygun and M. Aygun, "An Analysis on Radiation Protection Abilities of Different Colored Obsidians," International Journal of Computational and Experimental Science and Engineering, 9(2), 170–176, 2023.
47. A. Coşkun, B. Cetin, İ. Yiğitoğlu, and H. Topakli, "Comparison of the Radiation Absorption Properties of PbO doped ZrB2 Glasses by using GATE-GEANT4 Monte Carlo Code and XCOM Programme," International Journal of Computational andExperimental Science and ENgineering (IJCESEN), 9(3), 274–279, 2023.
48. J. E. Martin, Physics for Radiation Protection, Third Edition (Wiley-VCH, 2013).
49. A. T. Boothroyd, Principles of Neutron Scattering from Condensed Matter (Oxford University Press, 2020).