Corrosion Fatigue Crack Growth in Clad Low-Alloy Steels—Part I: Medium-Sulfur Forging Steel

Author:

James L. A.1,Auten T. A.2,Poskie T. J.3,Cullen W. H.4

Affiliation:

1. Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, P.O. Box 79, West Mifflin, PA 15122-0079

2. Knolls Atomic Power Laboratory, Schenectady, NY 12301

3. Bettis Atomic Power Laboratory West Mifflin, PA 15122-0079

4. Lanham, MD 20706

Abstract

Corrosion fatigue crack propagation tests were conducted on a medium-sulfur ASTM A508-2 forging steel overlaid with weld-deposited alloy EN82H cladding. The specimens featured semi-elliptical surface cracks penetrating approximately 6.3 mm of cladding into the underlying steel. The initial crack sizes were relatively large with surface lengths of 30.3–38.3 mm, and depths of 13.1–16.8 mm. The experiments were conducted in a quasi-stagnant low-oxygen (O2 < 10ppb) aqueous environment at 243°C, under loading conditions (ΔK, R, and cyclic frequency) conducive to environmentally assisted cracking (EAC) in higher-sulfur steels under quasi-stagnant conditions. Earlier experiments on unclad compact tension specimens of this heat of steel did not exhibit EAC, and the present experiments on semi-elliptical surface cracks penetrating cladding also did not exhibit EAC.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality

Reference29 articles.

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2. Auten, T. A., Hayden, S. Z., and Emanuelson, R. H., 1993, “Fatigue Crack Growth Rate Studies of Medium Sulfur Low Alloy Steels Tested in High Temperature Water,” Proceedings, Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, TMS-AIME, pp. 35–41

3. Bazˇant Z. P. and EstenssoroL. F., 1979, “Surface Singularity and Crack Propagation,” International Journal of Solids and Structures, Vol. 15, No. 5, pp. 405–426.

4. Bernard J. L. , VagnerJ., Pellissier-TanonA., and FauerF., 1992, “Effect of Residual Stresses and Complex Loadings on the Fatigue Behavior of Underclad Cracks,” Nuclear Engineering and Design, Vol. 133, No. 1, pp. 3–15.

5. Bramwell, I. L., Tice, D. R., Worswick, D., and Heys, G. B., 1995, “The Effect of Stainless Steel Overlay Cladding on Corrosion Fatigue Crack Propagation in a Pressure Vessel Steel in PWR Primary Coolant,” Proceedings, Seventh International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors, Vol. 2, NACE, pp. 1157–1168.

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