Stress Corrosion Cracking in Nickel-Base Alloys 690 and 152 Weld in Simulated PWR Environment: 2009.

摘要

Alloys 600 and 182 are used as structural materials in pressurized water reactors (PWRs) and have been found to undergo stress corrosion cracking (SCC). Alloys 690 and 152 are the replacement materials of choice for Alloys 600 and 182, respectively. The primary objective of this work is to determine the crack growth rates (CGRs) in a simulated PWR water environment for the replacement alloys. This is an ongoing effort, and the report presents the initial investigations on Alloys 690 and 152 weld. A second objective was to obtain tensile data for these alloys for a wide temperature range, from operating to extreme conditions. To meet the objectives, testing conducted at ANL included Alloy 690 in the asreceived condition and cold-rolled by 26%, as well as a laboratory-prepared Alloy 152 double-J weld in the as-welded condition. For the SCC CGR measurements, the specimens were pre-cracked under cyclic loading in a primary water environment, and the cyclic CGRs were monitored to determine the transition from the fatigue transgranular fracture mode to the intergranular SCC fracture mode.