Effects of irradiation with nickel ions in the microstructure and superficial composition of DIN 1.4970 austenitic steel irradiated at high doses and temperatures
DOI:
https://doi.org/10.31349/RevMexFis.72.031002Keywords:
Grazing Incidence X-Ray Diffraction, XPS, irradiation, austenitic stainless steel, materials, TEM, SEMAbstract
In this work, we conducted a study on the microstructural and compositional changes on the surface of German Institute for Standardization in English (DIN) 1.4970 Austenitic Steel irradiated with Nickel (Ni) ions at a dose of 360 (dpa) and a temperature of 650°C. We employed techniques of S diffraction in Grazing X-Ray Diffraction (GXRD) and X-ray Photoelectron Spectroscopy (XPS) to characterize the surface of the steel after each treatment. The study found that the concentration of iron (Fe) and chromium (Cr) in the Non-Irradiated Zone (NIZ) was greater with respect to the Irradiated Zone (IZ), while the concentration of the elements Nickel (Ni) and Silicon (Si) in the NIZ is lesser with respect to the IZ. In addition, there was a decrease of Fe and Cr and an increase of Ni and Si due to the irradiation. The damage caused by the Ni ions to the DIN 1.4970 steel is found at 1.560 µm below the surface.
Downloads
References
M. Griffiths, Effect of neutron irradiation on the mechanical properties, swelling and creep of austenitic stainless steels, Materials 14 (2021) 2622, https://doi.org/10.3390/ma14102622 DOI: https://doi.org/10.3390/ma14102622
P. J. Maziasz and J. T. Busby, Properties of austenitic steels for nuclear reactor applications (Elsevier Ltd., Ox ford,UK, 2020), p. 303 DOI: https://doi.org/10.1016/B978-0-12-803581-8.11736-9
B. Radiguet et al., Irradiation behavior of nanostructured 316 austenitic stainless steel, J. Mater. Sci. 43 (2008) 7338, https://doi.org/10.1007/s10853-008-2875-8 DOI: https://doi.org/10.1007/s10853-008-2875-8
W. Daenner, A comparison of AISI type 316 and German type DIN 1.4970 stainless steel with regard to the first-wall lifetime, J. Nucl. Mater. 103 (1981) 121 DOI: https://doi.org/10.1016/0022-3115(82)90584-0
W. Kesternich, Dislocation-Controlled precipitation of TiC particles and their resistance to coarsening, Philos. Mag. 52 (1985) 533, https://doi.org/10.1080/01418618508237645 DOI: https://doi.org/10.1080/01418618508237645
K. Ehrlich, Irradiation creep and interrelation with swelling in austenitic stainless steels, J. Nucl. Mater. 100 (1981) 149, https://doi.org/10.1016/0022-3115(81)90531-6 DOI: https://doi.org/10.1016/0022-3115(81)90531-6
F. A. Garner, Radiation-Induced Damage in Austenitic Structural Steels Used in Nuclear Reactors In Comprehensive Nuclear Materials, Second Edition. (2020) 157-158, https://doi.org/10.1016/B978-0-12-803581-8.12067-3 DOI: https://doi.org/10.1016/B978-0-12-803581-8.12067-3
S. Kasahara et al., Effect of Mn addition on decrease of Cr depletion at grain boundary in austenitic alloys irradiated with electrons, J. Nucl. Mater. 239 (1996) 194, https://doi.org/10.1016/S0022-3115(96)00468-0 DOI: https://doi.org/10.1016/S0022-3115(96)00468-0
N. Cautaerts et al., Thermal creep properties of Ti-stabilized DIN 1.4970 (15-15Ti) austenitic stainless steel pressurized cladding tubes, J. Nucl. Mater. 493 (2017) 154, https://doi.org/10.1016/j.jnucmat.2017.06.013 DOI: https://doi.org/10.1016/j.jnucmat.2017.06.013
L. H. Wang et al., Effect of prior thermal treatment on the microchemistry and crack propagation of proton-irradiated AISI 304 stainless steels, J. Nucl. Mater. 328 (2004) 11, https://doi.org/10.1016/j.jnucmat.2004.02.003 DOI: https://doi.org/10.1016/j.jnucmat.2004.02.003
M. Terada et al., Microstructure and intergranular corrosion of the austenitic stainless steel 1.4970, J. Nucl. Mater. 358 (2006) 40, https://doi.org/10.1016/j.jnucmat.2006.06.010 DOI: https://doi.org/10.1016/j.jnucmat.2006.06.010
N. Cautaerts et al., The role of Ti and TiC nanoprecipitates in radiation resistant austenitic steel: A nanoscale study, Acta Mater. 197 (2020), https://doi.org/10.1016/j.actamat.2020.07.022 DOI: https://doi.org/10.1016/j.actamat.2020.07.022
W. Kesternich and A. Garcia-Borquez, Inversion of the radiation-induced segregation behaviour at grain boundaries in austenitic steel, Scripta Mater. 36 (1997) 1127, https://doi.org/10.1016/S1359-6462(97)00004-3 DOI: https://doi.org/10.1016/S1359-6462(97)00004-3
N. Cautaerts et al., Characterization of (Ti,Mo,Cr) C nanoprecipitates in an austenitic stainless steel on the atomic scale, Acta. Mater. 164 (2019) 90, https://doi.org/10.1016/j.actamat.2018.10.018 DOI: https://doi.org/10.1016/j.actamat.2018.10.018
J. Titchmarsh and S. Dumbill, On the measurement of radiation-induced segregation (RIS) at point defect sinks, J. Nucl. Mater. 227 (1996) 203, https://doi.org/10.1016/0022-3115(95)00159-X DOI: https://doi.org/10.1016/0022-3115(95)00159-X
F. Onimus et al., Irradiation Creep in Materials, 1 (2021), https://doi.org/10.1016/B978-0-12-803581-8.11645-5 DOI: https://doi.org/10.1016/B978-0-12-803581-8.11645-5
P. Yvon, Structural Materials for Generation IV Nuclear Reactors (2016)
Y. Yamamoto et al., Alumina-Forming Austenitic Stainless Steels Strengthened by Laves Phase and MC Carbide Precipitates, Metall. Mater. Trans. A 38 (2007) 2737, https://doi.org/10.1007/s11661-007-9319-y DOI: https://doi.org/10.1007/s11661-007-9319-y
P. J. Maziasz and C. J. McHargue, Microstructural evolution in annealed austenitic steels during neutron irradiation, Mater. Sci. Technol. 32 (1987) 190, https://doi.org/10.1179/095066087790150 DOI: https://doi.org/10.1179/095066087790150331
D. Koury et al., Analysis of bi-layer oxide on austenitic stainless steel, 316L, exposed to Lead-Bismuth Eutectic (LBE) by X-ray Photoelectron Spectroscopy (XPS), J. Nucl. Mater. 440 (2013) 28, https://doi.org/10.1016/j.jnucmat.2013.03.093 DOI: https://doi.org/10.1016/j.jnucmat.2013.03.093
P. Hosemann et al., Characterization of oxide layers grown on D9 austenitic stainless steel in lead bismuth eutectic, J. Nucl. Mater 375 (2008) 323, https://doi.org/10.1016/j.jnucmat.2007.12.005 DOI: https://doi.org/10.1016/j.jnucmat.2007.12.005
R. V. Nandedkar and W. Kesternich, Effect of boron on hightemperature creep behavior of austenitic stainless steel DIN 1.4970, Metall. Trans. A 21 (1990) 3033, https://doi.org/10.1007/BF02647301 DOI: https://doi.org/10.1007/BF02647301
E. Longo et al., In situ Transmission Electron Microscopy observation of Ag nanocrystal evolution by surfactant free electron-driven synthesis, Sci. Rep. 6 (2016) 21498, https://doi.org/10.1038/srep21498 DOI: https://doi.org/10.1038/srep21498
A. Courcelle et al., Evolution under Irradiation of Optimized Austenitic Steel For Gen-IV Reactors. Impact on Fuel Cladding Properties and Performances, EPJ Web Conf. 115 (2016) 47, https://doi.org/10.1051/epjconf/201611504003 DOI: https://doi.org/10.1051/epjconf/201611504003
F. A. Garner, Radiation Damage in Austenitic Steels, In R. J. M. Konings, ed., Compr. Nucl. Mater. (2012) pp. 33-95 DOI: https://doi.org/10.1016/B978-0-08-056033-5.00065-3
N. Hashimoto et al., Microstructure of austenitic stainless steels irradiated at 400◦ in the ORR and the HFIR spectral tailoring experiment, J. Nucl. Mater. 280 (2000) 186, https://doi.org/10.1016/S0022-3115(00)00046-5 DOI: https://doi.org/10.1016/S0022-3115(00)00046-5
H. Huang et al., TEM, XRD and nanoindentation characterization of Xenon ion irradiation damage in austenitic stainless steels, J. Nucl. Mater. 454 (2014) 168, https://doi.org/10.1016/j.jnucmat.2014.07.033 DOI: https://doi.org/10.1016/j.jnucmat.2014.07.033
R. L. Plaut et al., Microstructure after Solution Annealing of the Nuclear Grade Austenitic Stainless Steel DIN 1.4970, Mater. Sci. Forum 1016 (2021) 1147, https://doi.org/10.4028/www.scientific.net/MSF.1016.1147 DOI: https://doi.org/10.4028/www.scientific.net/MSF.1016.1147
E. Charalampopoulou et al., Transmission electron microscopy study of complex oxide scales on DIN 1.4970 steel exposed to liquid Pb-Bi eutectic, Corros. Sci. 147 (2019) 22, https://doi.org/10.1016/j.corsci.2018.10.018 DOI: https://doi.org/10.1016/j.corsci.2018.10.018
D. Chen et al., The effects of loop size on the unfaulting of Frank loops in heavy ion irradiation, J. Nucl. Mater. 529 (2020) 151942, https://doi.org/10.1016/j.jnucmat.2019.151942 DOI: https://doi.org/10.1016/j.jnucmat.2019.151942
A. Garcia-Borquez and W. Kesternich, Controlled-Depth and cross-section preparation techniques for transmission electron microscopy subsurface studies in metals, Microsc. Res. Tech. 25 (1993) 255, https://doi.org/10.1002/jemt.1070250307 DOI: https://doi.org/10.1002/jemt.1070250307
P. Flewitt and R. Wild, Physical Methods for Materials Characterisation, Graduate student series in materials science and engineering (Inst. Phys. Pub., 1994)
H. Schroeder and Y. Dai, Helium concentration dependence of embrittlement effects in DIN 1.4970, 13% cw austenitic stainless steel at 873 K, J. Nucl. Mater. 191-194 (1992) 781, https://doi.org/10.1016/0022-3115(92)90578-9 DOI: https://doi.org/10.1016/0022-3115(92)90578-9
S. Rugel et al., Grazing-incidence X-ray diffraction on ionimplanted silicon, Appl. Surf. Sci. 54 (1992), https://doi.org/10.1016/0169-4332(92)90096-G DOI: https://doi.org/10.1016/0169-4332(92)90096-G
J. Dudognon et al., Simulation of X-ray diffractograms obtained by grazing incidence X-ray diffraction of implanted stainless steel, Surf. Interface Anal. 40 (2008) 441, https://doi.org/10.1002/sia.2638 DOI: https://doi.org/10.1002/sia.2638
J. Dudognon et al., Modelling of grazing incidence X-ray diffraction spectra from Mo-implanted stainless steel, Surf. Coat. Technol. 200 (2006) 5058, https://doi.org/10.1016/j.surfcoat.2005.05.025 DOI: https://doi.org/10.1016/j.surfcoat.2005.05.025
Y. Dai et al., The Effects of Helium in Irradiated Structural Alloys, 1 (2020) 186-234 DOI: https://doi.org/10.1016/B978-0-12-803581-8.12046-6
R. García, Surface modification study in stainlees steel irradiated with 3.66 MeV Ni ions, 1st ed. (Proceeding of XXIX Annual Meeting International Conference on Surface Materials and Vacuum, S.L.P., México, 2009) p. 199
N. Flores-Fuentes, Estudio Comparativo por diferentes técnicas, de los cambios microestructurales en aceros austeníticos, inducidos por la irradiación con iones de Ni, Ph.D. tesis, Escuela Superior de Física y Matemáticas, Instituto Politécnico Nacional, México (2013)
J. A. Abasolo et al., Transmission electron microscopy characterization of radiation-induced precipitates with high energy ions in stabilized austenitic steels, Rev. Latim Am. Met 22 (2022)
J. Ziegler, SRIM-The Stopping and Range of Ions in Matter, version 2010, In SRIM Software, available at: http://www.srim.org/ (2010) DOI: https://doi.org/10.1016/j.nimb.2010.02.091
Downloads
Published
How to Cite
Issue
Section
License
Copyright (c) 2026 N. A. Flores-Fuentes, C. Juárez-León, Á. Morales-González, J. M. Tirado-Lule, J. A. Morales-González, R. Vázquez-Arreguín, E. O. Madrigal-Santillán, L. Anguiano-Robledo, L. Delgado Olivares, E. O. López-de-León

This work is licensed under a Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 International License.
Authors retain copyright and grant the Revista Mexicana de Física right of first publication with the work simultaneously licensed under a CC BY-NC-ND 4.0 that allows others to share the work with an acknowledgement of the work's authorship and initial publication in this journal.