Effect of Grain Boundary Microchemistry on IGSCC of Alloy 132 in a Simulated BWR Environment

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Abstract:

The effects of cold working and heat treatment on caustic stress corrosion cracking (SCC) of mill annealed (MA) alloy 800M in boiling solution of 50%NaOH+0.3%SiO2+0.3%Na2S2O3 were investigated by means of microstructure examination, tensile test, X-ray stress analysis, SCC testing of C-rings, Auger electron spectroscopy (AES), scanning electron microscopy (SEM) and metallography. The microstructure of alloy 800M under tested conditions was austenite. With a strain of 25% by cold working, the grains of alloy 800M became longer, yield strength (YS) and ultimate tensile strength (UTS) increased, elongation (δ ) decreased, residual stress and the susceptibility to SCC increased. With increasing temperature of heat treatment of alloy 800M with cold working, the grains became bigger , residual stress, YS and UTS decreased and δ increased, the susceptibility to SCC of alloy 800M decreased. In boiling caustic solution, SCC cracks on the surfaces of C-ring specimens polarized potentiostatically at –20mV/SCE initiated from pitting and propagated along grain boundaries. AES analysis indicated that the surface films on MA alloy 800M were enriched in nickel and depleted in iron and chromium.

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Key Engineering Materials (Volumes 297-300)

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986-992

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November 2005

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© 2005 Trans Tech Publications Ltd. All Rights Reserved

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[1] T. Cassagne, D. Caron and J. Daret et al: Proc. 9th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, TMS, Warrendale, PA (1999), pp.217-224.

DOI: 10.1002/9781118787618.ch22

Google Scholar

[2] R.A. Page: Corrosion Vol. 44 (4) (1988), pp.239-247.

Google Scholar

[3] G. Nakayama and M. Akashi: Proc. 6th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, TMS, Warrendale, PA (1993), pp.883-888.

Google Scholar

[4] M. Itow, Y. Abe and A. Sudo et al: Proc. 7th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, NACE, Houston, TX (1995), pp.541-551.

Google Scholar

[5] C.L. Briant, C.S. O'Toole and E.L. Hall: Corrosion Vol. 42 (1) (1986), pp.15-27.

Google Scholar

[6] J.P. Foster, W.H. Bamford and R.S. Pathania: Proc. 8th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, ANS, La Grange Park, IL (1997), pp.340-348.

Google Scholar

[7] M. Kowaka, H. Nagano and T. Kudo et al: Nucl. Technol. Vol. 55 (2) (1981), pp.394-404.

Google Scholar

[8] G.S. Was and V.B. Rajan: Metall. Trans. A Vol. 18A (7) (1987), pp.1313-1323.

Google Scholar

[9] C.L. Briant, C.S. O'Toole and E.L. Hall: Corrosion Vol. 42 (1) (1986), pp.15-27.

Google Scholar

[10] G.S. Was, H.H. Tischner and R.M. Latanision: Metall. Trans. A Vol. 12A (8) (1981), pp.1397-1408.

Google Scholar