Keywords: Nuclear reactor, wire-wrapped fuel rod, Experimental study, Flow-induced Vibration
Nuclear reactor, wire-wrapped fuel rod, Experimental study, Flow-induced Vibration
Narrow rectangular channel, Localized deformation, Annular flow, Liquid film, Disturbance wave
Zirconium alloy, MAO coating, Microstructure, Corrosion mechanism, Phase transition
two-phase flow, helical cruciform fuel, wire-mesh sensor, void fraction, pressure drop
Experimental study, Zr-4 alloy cladding, Fretting wear, Wear mechanism
Annular Fuel Rod Bundle, Reflooding, RELAP5, LOCA
Alloy 718, Stress Corrosion Cracking, PWR primary water, Crack growth rate, Cold work, Nano-precipitates