Cyclic corrosion cracking in steel at some nuclear power stations at high water temperatures

Author:

Gnyp I. P.

Publisher

Springer Science and Business Media LLC

Subject

Mechanics of Materials

Reference26 articles.

1. W. H. Bamford, “The effect of pressurized water reactor environment of fatigue crack propagation in pressure vessel steel,” The Influence of Environment in Fatigue, No. 4, 51–56 (1977).

2. G. C. Salivar and D. L. Creighton, “Effect of frequency and environment on fatigue crack propagation of SA 533B1 steel,” Eng. Fract. Mech.,14, No. 2, 337–352 (1981).

3. J. H. Bullock and R. D. Achilles, “Stress corrosion cracking behavior of steel in a light water reactor environment,” Int. J. Pressure Vessel Pip.,36, No. 1, 57–64 (1989).

4. P. Scott and B. Tomkins, “Significance of corrosion fatigue in evaluating reliability of pressurized-water reactors,” in: Corrosion Fatigue in Metals [Russian translation], Naukova Dumka, Kiev (1982), pp. 310–350.

5. W. H. Cullen and K. Torronen, “A review of fatigue crack growth in pressure vessels and piping steels in high-temperature pressurized reactor grade water,” NUREG/CR-1576, NRL Memorandum Report 4298, Washington (1980).

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