Browse > Article
http://dx.doi.org/10.1016/j.net.2019.08.017

High alloyed new stainless steel shielding material for gamma and fast neutron radiation  

Aygun, Bunyamin (Agri Ibrahim Cecen University, Department of Electronics and Automation, Vocational School)
Publication Information
Nuclear Engineering and Technology / v.52, no.3, 2020 , pp. 647-653 More about this Journal
Abstract
Stainless steel is used commonly in nuclear applications for shielding radiation, so in this study, three different types of new stainless steel samples were designed and developed. New stainless steel compound ratios were determined by using Monte Carlo Simulation program Geant 4 code. In the sample production, iron (Fe), nickel (Ni), chromium (Cr), silicium (Si), sulphur (S), carbon (C), molybdenum (Mo), manganese (Mn), wolfram (W), rhenium (Re), titanium (Ti) and vanadium (V), powder materials were used with powder metallurgy method. Total macroscopic cross sections, mean free path and transmission number were calculated for the fast neutron radiation shielding by using (Geant 4) code. In addition to neutron shielding, the gamma absorption parameters such as mass attenuation coefficients (MACs) and half value layer (HVL) were calculated using Win-XCOM software. Sulfuric acid abrasion and compressive strength tests were carried out and all samples showed good resistance to acid wear and pressure force. The neutron equivalent dose was measured using an average 4.5 MeV energy fast neutron source. Results were compared to 316LN type stainless steel, which commonly used in shielding radiation. New stainless steel samples were found to absorb neutron better than 316LN stainless steel at both low and high temperatures.
Keywords
Stainless steel; Alloy; Neutron shielding; Geant4; Gamma;
Citations & Related Records
연도 인용수 순위
  • Reference
1 Fattah-Alhosseini, A.F. Shirsalimi, M. Yousefi, A. Abedi, Electrochemical behavior investigation of two low activation austenitic stainless steels in an acidic solution, J. Mater. Environ. Sci. 6 (2014) 1847-1853.
2 T. Singh, P. Kaur, P.S. Singh, Thickness optimization of SnePb alloys for experimentally measuring mass attenuation coefficients, Nucl. Energy Technol. 3 (2017) 1-5.   DOI
3 D. Dawson, R. Fleck, A. Wadham, Radiation damage to materials, Approv. Issues Course Modul. 4 (1999) 228-230.
4 V. Mclane, L. Charles, P. Dunford, F. Rose, Neutron Cross Sections, 1988, ISBN 978-0-12-484220-5.
5 S. Agostinelli, et al., Geant4 simulation toolkit, Nucl. Instrum. Methods Phys. Res. 506 (2003) 250-303.   DOI
6 W. Qianglin, Y. Bo, W. Yi, Y. Ting, L. Yibao, M-C simulation of slow neutron attenuation in boron- containing stainless steel, Nucl. Sci. Tech. 33 (5) (2010) 367-369.
7 T. Yonezawa, Nickel alloys properties and characteristics, Ref. Modul. Mater. Sci. Mater. Eng. 2 (2016) 233-266.
8 T. Dewen, Z. Shuliang, Y. Liang, Research on the preparation and shielding properties of WeNieFe alloy material by liquid phase sintering, Powder Metall. 61 (1) (2018) 28-35.   DOI
9 F. Mughabghab, Neutron Cross-Sections, Neutron Resonance Parameters and Thermal Cross-Sections, vol. 4, Academic Press, 1984, pp. 61-100.
10 V. McLane, C.L. Dunford, P.F. Rose, Neutron Cross Sections. 2, Neutron Cross Section Curves, N. P., Web, United States, 1988.
11 P. Rinard, Neutron Interactions with Matter Passive Nondestructive Assay of Nuclear Materials, 1991.
12 The International Nickel Company, inc, The Corrosion Resistance of Nickel-Containing Alloys in Sulfuric Acid, 1983.
13 G.E. Dieter, Mechanical Metallurgy, third ed., McGraw Hill International Edition, New York (USA), 2014.
14 M. Kwon, Y.S. Bae, S. Cho, W. Choe, B.G. Hong, Y.S. Hwang, J.Y. Kim, K. Kim, Yaung-Soo Kim, Jong-Gu Kwak, Hyeon Gon Lee, Sangil Lee, Na Yong-Su, Byung-Hoon Oh, Yeong-Kook Oh, JiYeon Park, Hyung Lyeo Yang, In Keun Yu, Current status of nuclear fusion energy research in Korea, Nucl. Eng. Technol. 41 (2009) 4455-4476.
15 U.S.NRC, United States Nuclear Regulatory Commission, 1997.
16 1 National Research Council, Health Risks from Exposure to Low Levels of Ionizing Radiation: BEIR VII Phase 2, The National Academies Press, Washington, DC, 2006, p. 7.
17 R.E. Shore, et al., Implications of recent epidemiologic studies for the linear nonthreshold model and radiation protection, J. Radiol. Prot. 38 (2018) 1217-1233.   DOI
18 V.P. Singh, N.M. Badiger, Gamma ray and neutron shielding properties of some alloy materials, Ann. Nucl. Energy 64 (2014) 301-310.   DOI
19 Mukherjee, N.I. Jamnapara, Materials research and development opportunities in fusion reactors, Proc. Indian Natl. Sci. Acad. 81 (4) (2015) 827-839.
20 W. Betteridge, J. Heslop, The Nimonic Alloys, and Other Nickel-Base High-Temperature Alloys, 1974, p. 29. New York.
21 V.P. Singh, N.M. Badiger, N. Chanthima, J. Kaewkhao, Evaluation of gamma-ray exposure buildup factors and neutron shielding for bismuth boro silicate glasses, Radiat. Phys. Chem. 98 (2014) 14-21.   DOI
22 Ramesh Singh, Applied Welding Engineering, second ed., 2016, 978-0-12-8041, 76-5.
23 William D. Callister Jr., G. David, Rethwisch Materials Science and Engineering an Introduction, ninth ed., 2004.
24 M.J. Berger, J.H. Hubbell, XCOM Photon Cross Sections Database, Web Version 1.2, National Institute of Standard Sand Technology, Gaithersburg, MD 20899, USA, 1987 available at: http://physics.nist.gov/xcom. Originally published as NBSIR 87-3597 "XCOM:Photon Cross Sections on a Personal Computer.
25 M.I. Sayyed, F. Akman, V. Turan, A. Araz, Evaluation of radiation absorption capacity of some soil samples, Radiochim. Acta 107 (1) (2019) 83-93.   DOI
26 M.I. Sayyed, Half value layer, mean free path and exposure buildup factor for tellurite glasses with different oxide compositions, J. Alloy. Comp. 695 (25) (2017) 3191-3197.   DOI
27 K.O. Ott, W.A. Bezella, Introductory Nuclear Reactor Statics, Revised edition, American Nuclear Society, 1989, ISBN 0-894-48033-2.