Corrosion fatigue crack growth in clad low-alloy steels: Part 1, medium-sulfur forging steel

Conference · Mon Apr 01 04:00:00 EST 1996

OSTI ID:230546

James, L A; Poskie, T J ^[1]; Auten, T A ^[2]; Cullen, W H ^[3]

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1. Bettis Atomic Power Lab., West Mifflin, PA (United States)
2. Knolls Atomic Power Lab., Schenectady, NY (United States)
3. Materials Engineering Associates, Inc., Lanham, MD (United States)

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 (O{sub 2} < 10 ppb) aqueous environment at 243{degrees}C, under loading conditions ({Delta}K, R, and cyclic frequency) conductive 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.

• Research Organization: Westinghouse Electric Corp., West Mifflin, PA (United States). Bettis Atomic Power Lab.
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC11-93PN38195
• OSTI ID: 230546
• Report Number(s): WAPD-T--3095; CONF-9604120--2-Pt.1; ON: DE96008864
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
CRACK PROPAGATION
CRACKS
FATIGUE
LOW ALLOY STEELS
REACTOR COMPONENTS
REACTOR MATERIALS
STEEL-ASTM-A302
STEEL-ASTM-A508
TESTING