Environmentally assisted cracking in LWR materials

Conference · Sun Mar 01 00:00:00 EST 1998

OSTI ID:305911

Chopra, O K; Chung, H M; Kassner, T F; Park, J H; Shack, W J ^[1]; Zhang, J; Brust, F W; Dong, P ^[2]

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1. Argonne National Lab., IL (United States)
2. Battelle Columbus Labs., Columbus, OH (United States)

The effect of dissolved oxygen level on fatigue life of austenitic stainless steels is discussed and the results of a detailed study of the effect of the environment on the growth of cracks during fatigue initiation are presented. Initial test results are given for specimens irradiated in the Halden reactor. Impurities introduced by shielded metal arc welding that may affect susceptibility to stress corrosion cracking are described. Results of calculations of residual stresses in core shroud weldments are summarized. Crack growth rates of high-nickel alloys under cyclic loading with R ratios from 0.2--0.95 in water that contains a wide range of dissolved oxygen and hydrogen concentrations at 289 and 320 C are summarized.

• Research Organization: Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Washington, DC (United States); Brookhaven National Lab. (BNL), Upton, NY (United States)
• OSTI ID: 305911
• Report Number(s): NUREG/CP-0162-Vol.1; CONF-9710101-Vol.1; ON: TI98007503; TRN: 99:002831
• Resource Relation: Conference: 25. water reactor safety information meeting, Bethesda, MD (United States), 20-22 Oct 1997; Other Information: PBD: Mar 1998; Related Information: Is Part Of Twenty-fifth water reactor safety information meeting: Proceedings. Volume 1: Plenary sessions; Pressure vessel research; BWR strainer blockage and other generic safety issues; Environmentally assisted degradation of LWR components; Update on severe accident code improvements and applications; Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)]; PB: 376 p.
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
PWR TYPE REACTORS
WATER CHEMISTRY
FATIGUE
REACTOR MATERIALS
AUSTENITIC STEELS
STAINLESS STEELS
CRACK PROPAGATION
NICKEL BASE ALLOYS
CARBON STEELS
LOW ALLOY STEELS
PHYSICAL RADIATION EFFECTS
STRESS CORROSION
WELDED JOINTS