|About this Abstract
||2016 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors V
||AA-2: Fractography of Neutron-irradiated Alloy 690
||Joo-Hag Kim, Han-Bum Surh, Jong-Wook Kim
|On-Site Speaker (Planned)
Alloy 690(60Ni-29Cr-9Fe), which is to be utilized as the material for helically coiled tubes in a heat exchanger of an integral reactor type SMART, has been irradiated by neutrons at the HANARO research reactor. A tensile test, a compact tension test, and a fractographic analysis of Alloy 690 were conducted in the IMEF hot cell. The target fluence of fast neutrons used for testing was evaluated as approximately 1.0x10E18n/cm2~1.0x10E20n/cm2 (E>1.0MeV). The irradiation temperature was about 250oC. The fractured tensile and compact tension specimens of irradiated Alloy 690 were examined through SEM and EPMA for a fractographic analysis. Correlations between the mechanical properties and fractographs of Alloy 690 were discussed.
||Planned: A print-only volume