Evaluation of Radiation Shielding Features of Co and Ni-Based Superalloys Using MCNP-5 Code: Potential Use in Nuclear Safety
Source abstract
Abstract
Due to their excellent heat resistance, superalloys are used predominantly in the manufacturing of engine parts and accessories for aircraft and aerospace equipment. The Monte Carlo simulation (MCNP-5) code was performed to estimate the mean track length of the incident photons inside six different alloys. Then, based on the simulated track length, other important γ-ray shielding parameters were calculated. In this study, the highest mass attenuation coefficient was obtained for alloys encoded MAR-302 and MAR-247 and varied in the range 0.035–72.94 and 0.035–71.98 cm2·g−1, respectively. The lowest mass attenuation coefficient was found for alloys coded Inconel-718 and Nimocast-75 with a range of 0.033–59.25 and 0.32–59.30 cm2·g−1, respectively. Use was made of a recently developed online program Phy-X/PD to calculate the effective atomic number, equivalent atomic number, and the buildup factors for the alloys of interest. The effective removal cross-section for the fast neutron was also calculated for the studied alloys: the highest value was found for the alloys coded with Inconel-718 (∑R = 0.01945 cm2·g−1) and Nimocast-75 (∑R = 0.01940 cm2·g−1), and the lowest value was obtained for alloy coded MAR-302 (∑R = 0.01841 cm2·g−1). Calculated data indicate that MAR-302 and MAR-247 are superior candidates for shielding of gamma-rays, while Inconel-718 and Nimocast-75 MAR-302 are suitable for the shielding of fast neutrons.
Source: crossref · Quality: baseline
Research context
OpenAlex topics: Radiation Shielding Materials Analysis · Graphite, nuclear technology, radiation studies · Nuclear Physics and Applications
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
Affiliations
Department of Physics, Faculty of Science, Isra University, Amman 11622, Jordan
Department of Nuclear Medicine Research, Institute for Research and Medical Consultations, Imam Abdulrahman bin Faisal University, Dammam 31441, Saudi Arabia
Nanotechnology and Advanced Materials Research Center, University of Technology, Baghdad 35010, Iraq
Ural Federal University, St. Mira, 19, 620002 Yekaterinburg, Russia
Nuclear Materials Authority, Maadi, Cairo 11381, Egypt
Advanced Science Research, Junior, Eastchester High School, Eastchester, NY 10709, USA
Directorate of Communication and Information Technology, Council of Representatives of Iraq, Conferences Palace, Baghdad 10001, Iraq
Center for Biomedical Physics, School of Healthcare and Medical Sciences, Sunway University, Bandar Sunway 47500, Selangor Darul Ehsan, Malaysia
Space Science Centre (ANGKASA), Universiti Kebangsaan Malaysia, Bangi 43600, Selangor, Malaysia
Funding
Universiti Kebangsaan Malaysia
References (35)
Show source-provided references
1. Mahmoud, K.A., Tashlykov, O.L., Wakil, A.F.E., Zakaly, H.M.H., and Aassy, I.E.E. (2019, January 23–25). Investigation of radiation shielding properties for some building materials reinforced by basalt powder. Proceedings of the AIP Conference Proceedings, Yekaterinburg, Russia.10.1063/1.5134187 ↗
2. Gamma ray shielding characteristics and exposure buildup factor for some natural rocks using MCNP-5 code10.1016/j.net.2019.05.013 ↗
3. Health Impacts of Low-Dose Ionizing Radiation: Current Scientific Debates and Regulatory Issues10.1177/1559325818796331 ↗
4. Choi, T.A., Costes, S.V., and Abergel, R.J. (2015). Understanding the health impacts and risks of exposure to radiation. Reflections on the Fukushima Daiichi Nuclear Accident: Toward Social-Scientific Literacy and Engineering Resilience, Springer International Publishing.10.1007/978-3-319-12090-4_13 ↗
5. Aggregates grain size and press rate dependence of the shielding parameters for some concretes10.1016/j.pnucene.2019.103092 ↗
6. Development of high-performance heavy density concrete using different aggregates for gamma-ray shielding10.1016/j.pnucene.2014.11.009 ↗
7. Comparative studies of different concretes on the basis of some photon interaction parameters10.1016/j.apradiso.2011.07.011 ↗
8. Comparative study of different concrete composition as gamma-ray shielding materials10.1016/j.anucene.2015.05.011 ↗
9. Gamma ray and neutron shielding properties of some concrete materials10.1016/j.anucene.2011.06.011 ↗
10. Determination and calculation of gamma and neutron shielding characteristics of concretes containing different hematite proportions10.1016/j.anucene.2011.08.010 ↗
11. Analysis of borosilicate glasses doped with heavy metal oxides for gamma radiation shielding application using Geant4 simulation code10.1016/j.ceramint.2019.08.234 ↗
12. A comprehensive study on the effect of TeO2 on the radiation shielding properties of TeO2–B2O3–Bi2O3–LiF–SrCl2 glass system using Phy-X/PSD software10.1016/j.ceramint.2019.11.078 ↗
13. X-ray photons attenuation characteristics for two tellurite based glass systems at dental diagnostic energies10.1016/j.ceramint.2019.08.258 ↗
14. Direct influence of mercury oxide on structural, optical and radiation shielding properties of a new borate glass system10.1016/j.ceramint.2020.04.112 ↗
15. Physical and structural effect of modifiers on dysprosium ions incorporated boro-tellurite glasses for radiation shielding purposes10.1016/j.ceramint.2020.04.102 ↗
16. Toxic effects of Pb2+ on growth of cowpea (Vigna unguiculata)10.1016/j.envpol.2007.01.011 ↗
17. Investigation of photon shielding performances of some selected alloys by experimental data, theoretical and MCNPX code in the energy range of 81 keV–1333 keV10.1016/j.jallcom.2018.09.177 ↗
18. An extensive investigation on gamma ray shielding features of Pd/Ag-based alloys10.1016/j.net.2018.12.014 ↗
19. Study of gamma radiation attenuation properties of some selected ternary alloys10.1016/j.jallcom.2018.12.221 ↗
20. Scope of Pb-Sn binary alloys as gamma rays shielding material10.1016/j.pnucene.2016.08.022 ↗
21. Fusible alloys: A potential candidate for gamma rays shield design10.1016/j.pnucene.2018.04.002 ↗
22. Gamma rays’ shielding parameters for some Pb-Cu binary alloys10.1016/j.jestch.2018.06.012 ↗
23. Fabrication of Ni, Cr, W reinforced new high alloyed stainless steels for radiation shielding applications10.1016/j.rinp.2018.11.038 ↗
24. Microstructure, electromagnetic shielding effectiveness and mechanical properties of Mg-Zn-Y-Zr alloys10.1016/j.matdes.2014.09.034 ↗
25. An investigation on gamma and neutron shielding efficiency of lead-free compounds and alloys
26. Mankins, W.L., and Lamb, S. (1990). Nickel and Nickel Alloys, in ASM Metals Handbook, VOL.2, Properties and Selection: Nonferrous Alloys and Special-Purpose Materials, ASM International.10.31399/asm.hb.v02.a0001072 ↗
27. X-5 Monte Carlo Team (2003). MCNP—A General Monte Carlo N-Particle Transport Code, Version 5, LA-CP-03-0245, University of California, Los Alamos National Laboratory.
28. Modified halloysite minerals for radiation shielding purposes
29. Mahmoud, K.A., Tashlykov, O.L., Sayyed, M.I., and Kavaz, E. (2020). The role of cadmium oxides in the enhancement of radiation shielding capacities for alkali borate glasses. Ceram. Int.10.1016/j.ceramint.2020.02.219 ↗
30. Phy-X/PSD: Development of a user friendly online software for calculation of parameters relevant to radiation shielding and dosimetry10.1016/j.radphyschem.2019.108496 ↗
31. SRIM—The stopping and range of ions in matter (2010)10.1016/j.nimb.2010.02.091 ↗
32. The role of PbO/Bi2O3 insertion on the shielding characteristics of novel borate glasses10.1016/j.ceramint.2020.04.018 ↗
33. The radiation-shielding properties of ternary SiO2–SnO–SnF2 glasses: Simulation and theoretical study10.1016/j.ceramint.2020.04.042 ↗
34. Evaluation of nuclear radiation shielding competence for ternary Ge–Sb–S chalcogenide glasses
35. A simple Method for Determining the Effective Removal Cross Section for Fast Neutrons10.18576/jrna/020203 ↗