|About this Abstract
||2017 TMS Annual Meeting & Exhibition
||Energy Materials 2017: Materials for Nuclear Energy
||IASCC Behavior of Nickel-based Alloys in Light Water Reactors (LWRs)
||Mi Wang, Miao Song, Gary Was
|On-Site Speaker (Planned)
Nickel-based alloys 625Plus, 725 and 625DA (Direct Age) have exhibited excellent mechanical properties and good resistance to corrosion, however, no data exists on their susceptibility to irradiation assisted stress corrosion cracking (IASCC) in light water reactor environments. IASCC behavior was studied using constant extension rate tensile (CERT) tests on tensile bars that were irradiated with 2 MeV protons to doses of ~5 dpa at 360°C at a strain rate of 1 x 10-7 s-1 in both PWR (320°C, 1000 ppm [B], 2 ppm [Li], 35 cc/kg H2) and BWR (288°C BWR NWC) environments to a fixed strain. Alloy 725 had the best resistance to IASCC in both environments while 625DA had the worst. The cracking behavior was interpreted in the context of the irradiated microstructure (dislocation loops, radiation induced precipitates, and RIS, etc…) and testing environments.
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