Baseline Fracture Toughness and CGR testing of alloys X-750 and XM-19 (EPRI Phase I)

J. H. Jackson ; S. P. Teysseyre

关键词: ALLOYS;    BUILDING MATERIALS;    EPRI;    FRACTURE PROPERTIES;    IRRADIATION;    NICKEL;    NITROGEN;    PLATES;    RECOMMENDATIONS;    RESEARCH PROGRAMS;    SHROUDS;    STAINLESS STEELS;    STRESS CORROSION;    TEST REACTORS;    TESTING Boiling Water Reactor;    Crack Growth Rate;    Fracture Toughness;    Stress Corrosion Cracking;    X-750;    XM-19;   

DOI  :  10.2172/1036263
RP-ID  :  INL/EXT-11-24173
PID  :  OSTI ID: 1036263
Others  :  TRN: US1201378

美国|英语

来源: SciTech Connect

【 摘 要 】

The Advanced Test Reactor National Scientific User Facility (ATR NSUF) 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 for comparison to similar tests conducted at GE Global Research. 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.