Abstract
Effect of different levels of oversize element, cerium, on radiation-induced segregation (RIS) in type 316 stainless steel was investigated. The effect of prior cold-work on RIS was also investigated. Samples with 0.00, 0.01, and 0.04 wt.% cerium were irradiated to 0.70 dpa using 4.8 MeV protons at 300 °C. Characterization of proton-irradiated specimens was carried out using electrochemical potentiokinetic reactivation (EPR) test followed by atomic force microscopic examination. The specimen with prior cold-work (without cerium addition) showed the lowest EPR values indicating the lowest chromium depletion in this material. The specimen with 0.04 wt.% cerium showed the lower EPR value as compared to the specimen with 0.01 wt.% Ce. The irradiated specimen with prior cold-work showed linear features after the EPR tests and such features were attributed to decoration of dislocations, generated due to prior cold-work, by point defects produced during irradiation. The resistance to RIS offered by cold-work (linear features) has been more effective as compared to that by the addition of oversize solute addition.
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A. Etienne, M. Hernàndez-Mayrol, C. Genevois, B. Radiguet, and P. Parieige, Dislocation Loop Evolution Under Ion Irradiation in Austenitic Stainless Steels, J. Nucl. Mater., 2010, 400, p 56–63
Z. Jiao, J.T. Busby, and G.S. Was, Deformation Microstructure of Proton-Irradiated Stainless Steels, J. Nucl. Mater., 2007, 361, p 218–227
P.L. Andresen, F.P Ford, S.M. Murphy, J.M. Perks, Proc. of the 4th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, NACE International, Houston, 1990
M.J. Hackett, R. Najafabadi, and G.S. Was, Modeling Solute-Vacancy Trapping at Oversized Solutes and its Effect on Radiation-Induced Segregation in Fe-Cr-Ni Alloys, J. Nucl. Mater., 2009, 389, p 279–287
H. Watanbe, T. Muroga, and N. Yshida, The Effects of Oversized Solute Addition on Microstructural Evolution in Fe-Cr-Ni Alloys During Electron Irradiation, J. Nucl. Mater., 1996, 239, p 95
N. Shigenaka, S. Ono, Y. Isobe, T. Hashimoto, H. Fujimori, and S. Uchida, Effect of Zirconium Addition to Austenitic Stainless Steels on Suppression of Radiation Induced Chromium Segregation at Grain Boundaries under Ion Irradiation, J. Nucl. Sci. Technol., 1996, 33, p 577
S. Kasahara, K. Nakata, K. Fukuya, S. Shima, A.J Jacobs, G.P. Wozadlo, and S. Suzuki, Proc. of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power, Systems Water Reactors, 15 August, San Diego, CA, The Minerals, Metals and Materials Society, 1993, p 615
N. Sakaguchi, S. Watanabe, and H. Takahashi, Effect of Additional Minor Element on Radiation-Induced Grain Boundary Segregation in Austenitic Stainless Steel Under Electron Irradiation, Nucl. Instrum. Methods B, 1999, 153, p 142
T. Kato, H. Takahashi, and M. Izumiya, Grain Boundary Segregation Under Electron Irradiation in Austenitic Stainless Steels Modified With Oversized Elements, J. Nucl. Mater., 1992, 189, p 167
M.A. Ashworth, D.I.R. Norris, and I.P. Jones, Radiation-Induced Segregation in Fe-20Cr-25Ni-Nb Based Austenitic Stainless Steels, J. Nucl. Mater., 1992, 189, p 289
S. Ohnuki, S. Yamashita, H. Takahashi, and T. Kato, Proc. of the 19th Inter-national Symposium on the Effects of Radiation on Materials, 16-18 June, Seattle, WA American Society for Testing and Materials, 1999, p 756
S. Dumbill, and W. Hanks, Proc. of the Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors, 15 August, San Diego, CA, The Minerals, Metals and Materials Society, 1993, p 521
L. Fournier, B.H. Sencer, G.S. Was, E.P. Simonen, and S.M. Bruemmer, The Influence of Oversized Solute Additions on Radiation-Induced Changes and Post-Irradiation Intergranular Stress Corrosion Cracking Behavior in High-Purity 316 Stainless Steels, J. Nucl. Mater., 2003, 321, p 192–209
Y.C. Lu and M.B. Ives, The Improvement of the Localized Corrosion Resistance of Stainless Steel by Cerium, Corros. Sci., 1993, 39, p 1773
Y.C. Lu and M.B. Ives, Chemical Treatment With Cerium to Improve the Crevice Corrosion Resistance of Austenitic Stainless Steels, Corros. Sci., 1995, 37, p 145
Y. Nakamura, The Oxidation Behavior of an Iron-Chromium Alloy Containing Yttrium or Rare Earth Elements Between 900 and 1200°C, Metall. Trans., 1974, 5, p 909
Y. Saito, T. Kiryu, T. Kimura, T. Amano, and K.J. Yajima, Jpn. Inst. Met., 1975, 39, p 1110
Y. Watanabe, V. Kain, T. Tonozuka, T. Shoji, T. Kondo, and F. Masuyama, Effect of Ce Addition on the Sensitization Properties of Stainless Steels, Scripta Mater., 2000, 42, p 307–312
Y. Watanabe, T. Tonozuka, T. Shoji, and T. Kondo, Corrosion 99, Paper No. 453 (1999), p 1–10
O. Okada, K. Nakata, and S. Kasahara, Effects of Thermal Sensitization on Radiation-Induced Segregation in Type 304 Stainless Steel Irradiated With He-Ions, J. Nucl. Mater., 1999, 265, p 232–239
K. Kondou, A. Hasegawa, K. Abe, V. Kain, and Y. Watanbe, Proc. of 10th International Conference on Degradation of Materials in Nuclear Power Systems-Water Reactors, Paper No. 66, Nevada, American Nuclear Society and National Association of Corrosion Engineers, August 1991
R. Katsura and S. Nishimura, The NACE Annual Conference and Corrosion Show, Paper No. 91, Corrosion 92, 1992
G.E.C. Bell, T. Inazumi, E.A. Kenik, and T. Kondo, Effect of Additional Minor Element on Radiation-Induced Grain Boundary Segregation in Austenitic Stainless Steel Under Electron Irradiation, J. Nucl. Mater., 1992, 187, p 170–179
P. Ahmedabadi, V. Kain, K. Arora, and I. Samajdar, Effect of Residual Strain on RIS in Type 304 SS, Corros. Sci., 2011, 53, p 1465–1475
K. Kondou, A. Hasegawa, and K. Abe, Study on Irradiation Induced Corrosion Behavior in Austenitic Stainless Steel Using Hydrogen-Ion Bombardment, J. Nucl. Mater., 2004, 329–333, p 652–656
J.F. Ziegler and J.P. Biersack, SRIM2003 Program, IBM Corp, Yorktown, NY, 2003
M.J. Norgett, M.T. Robinson, and I.M. Torrens, A Proposed Method of Calculating Displacement Dose Rates, Nucl. Eng. Des., 1975, 33, p 30
R. Babić and M. Metikoš-Huković, Semiconducting Properties of Passive Films on AISI, 304 and 316 Stainless Steels, J. Electroanal. Chem., 1993, 358(1–2), p 143–160
V. Kain and Y. Watanabe, Development of a Single Loop EPR Test Method and its Relation to Grain Boundary Microchemistry for Alloy 600, J. Nucl. Mater., 2002, 302, p 49–59
Periodic table of the elements, Introduction solid-state chemistry, MIT web-site. http://web.mit.edu/course/3/3.091/www3/pt/Ce.html and http://web.mit.edu/course/3/3.091/www3/pt/Fe.html
W. Karlsen, K. Dohi, and T. Onchi, Proc. of 13th International Conference on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, CNS-SNC, 2007
D.N. Wasnik, I.K. Gopalkrishnan, J.V. Yakhami, V. Kain, and I. Samajdar, Cold Rolled Texture and Microstructure in Types 304 and 316L Austenitic Stainless Steels, ISIJ Int., 2003, 43, p 1581–1589
P. Ahmedabadi, V. Kain, K. Arora, I. Samajdar, S. Sharma, and P. Bhagwat, The Role of Niobium Carbide in Radiation Induced Segregation Behaviour of Type 347 Austenitic Stainless Steel, J. Nucl. Mater., 2011, 416, p 335–344
P. Ahmedabadi, V. Kain, K. Arora, I. Samajdar, S. Sharma, S. Ravindra, P. Bhagwat, and R.K. Chowdhury, Radiation-Induced Segregation in Austenitic Stainless Steel Type 304: Effect of High Fraction of Twin Boundaries, Mater. Sci. Eng. A, 2011, 528, p 7541–7551
P. Ahmedabadi, V. Kain, G.K. Dey, I. Samajdar, S.C. Sharma, P. Bhagwat, and S. Kailas, International Topical Meeting on Nuclear Research Applications and Utilization of Accelerators, Vienna; 4 May 2009 through 8 May 2009; Code 84190
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Ahmedabadi, P.M., Kain, V., Gupta, M. et al. Electrochemical Evaluation of Radiation-Induced Segregation in Austenitic Stainless Steels with Oversize Solute Addition. J. of Materi Eng and Perform 21, 2472–2479 (2012). https://doi.org/10.1007/s11665-012-0201-8
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DOI: https://doi.org/10.1007/s11665-012-0201-8