Mechanical properties of Alloy 718 in a gas-cooled reactor environment

Technical Report · Thu Oct 01 04:00:00 EDT 1987

OSTI ID:5638701

McCoy, H E

A brief program was run to evaluate Alloy 718 for high-temperature gas-cooled reactor (HTGR) applications. The testing included short-term tensile tests, impact tests, and creep tests. Samples were aged to 30,000 h at 593 and 649{degree}C in HTGR-He before testing. Short-term tensile tests showed that aging at 593{degree}C resulted in further hardening; aging at 649{degree}C resulted in some softening. The impact energy decreased with aging at both temperatures, with a slight recovery of the loss after very long aging times. Creep results obtained in HTGR-He agreed with data from other sources in which tests had been run in air. Thus, there is no detectable effect of the HTGR-He environment on creep behavior. Carbon analyses of test specimens did not reveal any evidence of carburization at 593 or 649{degree}C. 5 refs., 15 figs., 3 tabs.

• Research Organization: Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: DOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5638701
• Report Number(s): DOE/HTGR-87-097; ORNL--6413; ON: DE91015591
• Country of Publication: United States
• Language: English

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