|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||Accident Tolerant Fuels for Light Water Reactor
||Effect of Dynamic Strain Aging on Mechanical Properties of Zircaloy-4
||Nilesh Kumar, Abdullah Alomari, Korukonda L Murty
|On-Site Speaker (Planned)
The development of novel alloys for advanced structural applications depend on our ability to understand micro-mechanism(s) governing the plastic deformation. This work focuses on dynamic strain aging and its effect on mechanical properties of recrystallized Zircaloy-4 (used in pressurized water nuclear reactors). To that end, uniaxial quasi-static tensile and repeated stress relaxation tests were carried out at temperatures ranging from 293 K to 1073 K. The strength, ductility, work-hardening rate, and activation volume were investigated as a function of temperature. The alloy exhibited dynamic strain aging (DSA) at intermediate temperatures. The yield strength of the alloy was found to be independent of temperature in the DSA regime. An increase in uniform ductility, a decrease in total ductility, and a high value of activation volume (compared to where the DSA was absent) were noted for the alloy in DSA regime. The research is supported by the US National Science Foundation.
||Planned: Supplemental Proceedings volume