|About this Abstract
||2016 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors V
||Thermal Stability of Nanoscale Hardening Features in Irradiated Reactor Pressure Vessel Steels
||Peter Wells, Nathan Almirall, Yuan Wu, David Gragg, G. Robert Odette, Takuya Yamamoto
|On-Site Speaker (Planned)
Reactor pressure vessel (RPV) embrittlement could limit LWR extended lifetimes. Embrittlement is primarily caused by the formation of nm scale Cu-Mn-Ni-Si precipitates and induced defect clusters. This embrittlement, and the variables leading to the formation of the embrittling features, must be well understood to safely extend the lifetime of our nation’s reactors. Data will be presented on a number of RPV steels with a wide range of bulk Cu and Ni contents to assess the effects of these two solutes on both the microstructure and mechanical property evolution under irradiation. Annealing studies show that while steels with very low Ni contents have much less initial hardening than higher Ni steels, the hardening features are much more stable at annealing temperatures > 400°C. The likely difference between the hardening features at low and high Ni is presented along with implications for life extension.
||Planned: A print-only volume