Low and free nickel austenitic stainless steel alloys were developed successfully and proposed to be used as a liquid sodium coolant fast reactor pressure vessel cladding. A standard austenitic stainless steel SS316L (AISI 316L) was produced as a reference sample. The nickel content was partially or totally replaced by manganese and nitrogen. The microstructure of the produced stainless steel alloys was investigated using Schaeffler diagram, optical microscopy and X-ray diffraction patterns (XRD). Mechanical properties of the developed stainless steel grads were investigated using Vickers hardness, impact and tensile tests at room temperature. Sodium chloride was used to study the corrosion rate of the investigated alloys by open circuit potential technique. Slow and total slow neutrons removal cross sections were measured using 241Am-Be neutron source and highly calibrated He-3 detector. Eight gamma ray lines which emitted from 60Co and 232Th radioactive sources and HPGe detector were used to study the attenuation parameters of the produced alloys. Metallography, Schaeffler diagram and XRD results showed that all the produced stainless steels are mainly of austenite phase with a small ferrite phase. The developed manganese-nitrogen stainless steels showed higher hardness, yield and ultimate tensile strength than SS316L. The elongation of developed stainless steels is relatively lower than the standard SS316L. The impact toughness was reduced with replacement of Ni by Mn. The developed manganese stainless steels have a higher total slow removal cross section than SS316L. On the other hand, the slow neutron and gamma rays have nearly the same behavior for all studied stainless steels.
| Published in | Nuclear Science (Volume 3, Issue 3) |
| DOI | 10.11648/j.ns.20180303.14 |
| Page(s) | 45-51 |
| Creative Commons |
This is an Open Access article, distributed under the terms of the Creative Commons Attribution 4.0 International License (http://creativecommons.org/licenses/by/4.0/), which permits unrestricted use, distribution and reproduction in any medium or format, provided the original work is properly cited. |
| Copyright |
Copyright © The Author(s), 2018. Published by Science Publishing Group |
Reactor Materials, Mn-N Stainless Steel, Structural and Mechanical Properties
| [1] | Mladen Pajnić, Krunoslav Markulin, Alojzije Matokovic and Hrvoje Franjić, “Advanced Approach of Reactor Pressure Vessel In-Service Inspection” 10th European Conference on Non-Destructive Testing, Moscow Russia, PP. 1-15, 2010. |
| [2] | Changheui Jang, III-Seok Jeon, and Sung Yull Hong, “Treatment of Stainless Steel Cladding in Pressurized Thermal Shock Evaluation: Deterministic Analysis”, Journal of the Korean Nuclear Socity, Vol. 23, No. 2, PP, 132-144, 2001. |
| [3] | Hiroyuki Kaneko, Tokiko Nakagawa, Kousei Hiraizumi, and Ryo Sakai, “Accelerated Corrosion Tests of Nuclear Reactor Pressure Vessel Materials in NaC-H3BO3 Solutions”, Materials Transactions, Vol. 54, No. 5, PP. 755-764, 2013. |
| [4] | E. V. Demina, L. I. Ivanov, Yu. M. Platov, M. D. Prusakova, S. R. Eikholtser, M. B. Tolochko, and F. A. Garner, “Radiation Creep and Phase Instability of Low-Activation Austenitic Steel 12 Cr–20 Mn–W under Neutron Irradiation in the FFTF Fast Reactor”, Inorganic Materials: Applied Research, Vol. 2, No. 5, pp. 457–460, 2011. |
| [5] | A. Fattah-alhosseini, F. Shirsalimi, M. Yousefi and A. Abedi, “Electrochemical Behaviour Investigation of Two Low Activation Austenitic Stainless Steels in An Acidic Solution”, Journal of Materials and Environmental Science, Vol. 5, No. 6, PP. 1847-1853, 2014. |
| [6] | E. V. Demina, M. D. Prusakova, V. V. Roshchin, N. A. Vinogradova, G. D. Orlova, “Reduced Activation Fe-Cr-Mn Austenitic Steels for Nuclear Power Plants”, Inorganic Materials: Applied Research, April 2010, Volume 1, Issue 2, pp 115-124. |
| [7] | A. Grajcar, S. Ko³odziej, W. Krukiewicz, “Corrosion resistance of High-Manganese Austenitic Steels”, Archives of Materials Science and Engineering, Vol. 41, No. 2, PP. 77-84, 2010. |
| [8] | M. Opiela, A. Grajcar, W. Krukiewicz, “Corrosion Behaviour of Fe-Mn-Si-Al Austenitic Steel in Chloride Solution” Journal of Achievements in Materials and Manufacturing Engineering, Vol. 33, No. 2, PP. 159-165, 2009. |
| [9] | Linda Mosecker and Alireza Saeed-Akbari, “Nitrogen in Chromium–Manganese Stainless Steels: A Review on The Evaluation of Stacking Fault Energy by Computational Thermodynamic”, Sci. Technol. Adv. Mater, Vol. 14, PP. 1-14, 2013. |
| [10] | V. Muthukumaran, V. Selladurai, S. Nandhakumar, M. Senthilkumar, "Experimental Investigation on Corrosion and Hardness of Ion Implanted AISI 316L Stainless Steel", Materials and Design, Vol. 31, PP.2813–2817, 2010. |
| [11] | Azza Ahmed, Saeed Ghali, Mamdouh Eissa and Salah El-badry, “Influence of Partial Replacement of Nickel by Nitrogen on Microstructure and Mechanical Properties of Austenitic Stainless Steel", Journal of Metallurgy, Vol. 2011, PP.1-6, 2011. |
| [12] | LI Hua-bing , Jiang Zhou-hua, Shen Ming-hui, and You Xiang-mi, International, "High Nitrogen Austenitic Stainless Steels Manufactured by Nitrogen Gas Alloying and Adding Nitrided Ferroalloys", Journal of iron and steel research, Vol. 14, No. 3, PP. 63-68, 2007. |
| [13] | Jan-Åke Persson, Mårten Wennerholm and Stephen O’Halloran, “Handbook for Kjeldahl Digestion”, FOSS, DK-3400 Hilleroed, Denmark, 4th edition, 2008. |
| [14] | ASTM E8 / E8M-15a, “Standard Test Methods for Tension Testing of Metallic Materials”, ASTM International, West Conshohocken, PA, 2015, www.astm.org. |
| [15] | Aly Saeed, Y. H. Elbashar and R. M. El shazly, “Optical Properties of High Density Barium Borate Glass for Gamma Ray Shielding Applications”, Optical and Quantum Electronics, Vol. 48, No.1, PP. 1-10, 2016. |
| [16] | L. Gerward, N. Guilbert, K. B. Jensen, and H. Leving, “'WinXCom – A Program for Calculating X-Ray Attenuation Coefficients”, Radiation Physics and Chemistry, 2004, Vol. 71, PP. 653-654. |
| [17] | A. Fattah-alhosseinia, B. Izadia and M. Asadi Asadabad, “Evaluation of Corrosion Behavior on Mn-Cr Austenitic Steels Using 0.1 M HCl Solution”, Journal of Advanced Materials and Processing, Vol.2, No. 1, 2014, 55-63. |
APA Style
Aly Saeed, Raed Mohmed El-Shazly, Saeed Nabil Ghali, Samir Yousha El-khamisy, Soad Abd El-Moneem El-fiki, et al. (2018). Low Activation-Modified High Manganese-Nitrogen Austenitic Stainless Steel for Fast Reactor Pressure Vessel Cladding. Nuclear Science, 3(3), 45-51. https://doi.org/10.11648/j.ns.20180303.14
ACS Style
Aly Saeed; Raed Mohmed El-Shazly; Saeed Nabil Ghali; Samir Yousha El-khamisy; Soad Abd El-Moneem El-fiki, et al. Low Activation-Modified High Manganese-Nitrogen Austenitic Stainless Steel for Fast Reactor Pressure Vessel Cladding. Nucl. Sci. 2018, 3(3), 45-51. doi: 10.11648/j.ns.20180303.14
AMA Style
Aly Saeed, Raed Mohmed El-Shazly, Saeed Nabil Ghali, Samir Yousha El-khamisy, Soad Abd El-Moneem El-fiki, et al. Low Activation-Modified High Manganese-Nitrogen Austenitic Stainless Steel for Fast Reactor Pressure Vessel Cladding. Nucl Sci. 2018;3(3):45-51. doi: 10.11648/j.ns.20180303.14
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Download@article{10.11648/j.ns.20180303.14,
author = {Aly Saeed and Raed Mohmed El-Shazly and Saeed Nabil Ghali and Samir Yousha El-khamisy and Soad Abd El-Moneem El-fiki and Mamdouh Mahmoud Eissa},
title = {Low Activation-Modified High Manganese-Nitrogen Austenitic Stainless Steel for Fast Reactor Pressure Vessel Cladding},
journal = {Nuclear Science},
volume = {3},
number = {3},
pages = {45-51},
doi = {10.11648/j.ns.20180303.14},
url = {https://doi.org/10.11648/j.ns.20180303.14},
eprint = {https://article.sciencepublishinggroup.com/pdf/10.11648.j.ns.20180303.14},
abstract = {Low and free nickel austenitic stainless steel alloys were developed successfully and proposed to be used as a liquid sodium coolant fast reactor pressure vessel cladding. A standard austenitic stainless steel SS316L (AISI 316L) was produced as a reference sample. The nickel content was partially or totally replaced by manganese and nitrogen. The microstructure of the produced stainless steel alloys was investigated using Schaeffler diagram, optical microscopy and X-ray diffraction patterns (XRD). Mechanical properties of the developed stainless steel grads were investigated using Vickers hardness, impact and tensile tests at room temperature. Sodium chloride was used to study the corrosion rate of the investigated alloys by open circuit potential technique. Slow and total slow neutrons removal cross sections were measured using 241Am-Be neutron source and highly calibrated He-3 detector. Eight gamma ray lines which emitted from 60Co and 232Th radioactive sources and HPGe detector were used to study the attenuation parameters of the produced alloys. Metallography, Schaeffler diagram and XRD results showed that all the produced stainless steels are mainly of austenite phase with a small ferrite phase. The developed manganese-nitrogen stainless steels showed higher hardness, yield and ultimate tensile strength than SS316L. The elongation of developed stainless steels is relatively lower than the standard SS316L. The impact toughness was reduced with replacement of Ni by Mn. The developed manganese stainless steels have a higher total slow removal cross section than SS316L. On the other hand, the slow neutron and gamma rays have nearly the same behavior for all studied stainless steels.},
year = {2018}
}
TY - JOUR T1 - Low Activation-Modified High Manganese-Nitrogen Austenitic Stainless Steel for Fast Reactor Pressure Vessel Cladding AU - Aly Saeed AU - Raed Mohmed El-Shazly AU - Saeed Nabil Ghali AU - Samir Yousha El-khamisy AU - Soad Abd El-Moneem El-fiki AU - Mamdouh Mahmoud Eissa Y1 - 2018/11/21 PY - 2018 N1 - https://doi.org/10.11648/j.ns.20180303.14 DO - 10.11648/j.ns.20180303.14 T2 - Nuclear Science JF - Nuclear Science JO - Nuclear Science SP - 45 EP - 51 PB - Science Publishing Group SN - 2640-4346 UR - https://doi.org/10.11648/j.ns.20180303.14 AB - Low and free nickel austenitic stainless steel alloys were developed successfully and proposed to be used as a liquid sodium coolant fast reactor pressure vessel cladding. A standard austenitic stainless steel SS316L (AISI 316L) was produced as a reference sample. The nickel content was partially or totally replaced by manganese and nitrogen. The microstructure of the produced stainless steel alloys was investigated using Schaeffler diagram, optical microscopy and X-ray diffraction patterns (XRD). Mechanical properties of the developed stainless steel grads were investigated using Vickers hardness, impact and tensile tests at room temperature. Sodium chloride was used to study the corrosion rate of the investigated alloys by open circuit potential technique. Slow and total slow neutrons removal cross sections were measured using 241Am-Be neutron source and highly calibrated He-3 detector. Eight gamma ray lines which emitted from 60Co and 232Th radioactive sources and HPGe detector were used to study the attenuation parameters of the produced alloys. Metallography, Schaeffler diagram and XRD results showed that all the produced stainless steels are mainly of austenite phase with a small ferrite phase. The developed manganese-nitrogen stainless steels showed higher hardness, yield and ultimate tensile strength than SS316L. The elongation of developed stainless steels is relatively lower than the standard SS316L. The impact toughness was reduced with replacement of Ni by Mn. The developed manganese stainless steels have a higher total slow removal cross section than SS316L. On the other hand, the slow neutron and gamma rays have nearly the same behavior for all studied stainless steels. VL - 3 IS - 3 ER -
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