Mechanical properties of Hastelloy X and Inconel 617 after aging 53,000 hours in HTGR-He

Technical Report · Sun Sep 01 04:00:00 EDT 1985

OSTI ID:712740

McCoy, H E

Twenty-four creep and tensile samples of Hastelloy X, Inconel 617, and each material containing a transverse weldment were aged 53,000 h at 593, 704, and 871{sup 0}C in impure helium that simulated the coolant gas in a high-temperature gas-cooled reactor. Half of the samples were subjected to short-term tensile tests at 25{sup 0}C. Large changes in properties were noted at an aging temperature of 593{sup 0}C, and some overaging occurred at 704 and 871{sup 0}C. The other half of the samples is being creep tested, with each sample tested at its aging temperature. This portion of the test program is in progress, and the trend thus far seems to be that the aged material is weaker than unaged material. Metallographic studies showed that large amounts of precipitate had formed and that these (1) formed continuous intergranular layers that caused brittle fracture and (2) depleted the matrix in solid-solution strengthening elements and thereby reduced the creep strength. 5 refs., 46 figs., 10 tabs.

• Research Organization: Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 712740
• Report Number(s): DOE/HTGR--85-072; ORNL/TM--9604; ON: TI86025296
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
AGING
CARBIDES
CHEMICAL COMPOSITION
CREEP
DUCTILITY
EXPERIMENTAL DATA
FRACTURES
GAS TUNGSTEN-ARC WELDING
HASTELLOY X
HIGH TEMPERATURE
HTGR TYPE REACTORS
INCONEL 617
METALLOGRAPHY
MICROSTRUCTURE
REACTOR MATERIALS
TEMPERATURE DEPENDENCE
ULTIMATE STRENGTH
VERY HIGH TEMPERATURE
YIELD STRENGTH