Baseline Fracture Toughness and SCC Testing of Alloys X750 and XM-19 (Phase I)

Technical Report · Wed Feb 29 04:00:00 EST 2012

DOI:https://doi.org/10.2172/1035808· OSTI ID:1035808

Jackson, John H. ^[1]

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1. Idaho National Laboratory (INL), Idaho Falls, ID (United States)

The Advanced Test Reactor National Scientific User Facility (ATR NSUF) based at INL and Electric Power Research Institute (EPRI) formed an agreement to test representative alloys used as reactor structural materials as a pilot program toward establishing guidelines for future ATR NSUF research programs. This report contains results from the portion of this program established as Phase I (of three phases) that entails baseline fracture toughness, stress corrosion cracking (SCC), and tensile testing of selected materials. The intent of this Phase I research program is to determine baseline properties for the materials of interest prior to irradiation, and to ensure comparability between laboratories using similar testing techniques, prior to applying these techniques to the same materials after having been irradiated at the Advanced Test Reactor (ATR). The materials chosen for this research are the nickel based super alloy X-750, and nitrogen strengthened austenitic stainless steel XM-19. A spare core shroud upper support bracket of alloy X-750 was purchased by EPRI from Southern Co. and a section of XM-19 plate was purchased by EPRI from GE-Hitachi. These materials were sectioned at GE Global Research and provided to INL.

• Research Organization: Idaho National Laboratory (INL), Idaho Falls, ID (United States); Electric Power Research Inst. (EPRI), Palo Alto, CA (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1035808
• Report Number(s): INL/CRADA--09-02; INL/EXT--11-24173
• Country of Publication: United States
• Language: English