Three austenitic alloys with different Ni content were stress corrosion cracking (SCC) tested in simulated pressurized water reactor (PWR) primary at 320 and 360 °C. Diffusion-induced grain boundary migration (DIGM) associated preferential intergranular oxidation (PIO) is observed ahead of all SCC crack tips. The occurrence DIGM revealed to be driven by PIO-induced diffusion Cr, Fe, Ni. extent ...

A comprehensive uncertainty analysis in the event of a severe accident two-loop pressurized water reactor is conducted using an package integrated ASYST code. The plant model based on nuclear power (NPP) Krško, Westinghouse-type plant. station blackout scenario with small break loss coolant analyzed, and all processes in-vessel phase are covered. best estimate plus (BEPU) methodology probabilis...

The accident-tolerant fuel concept involves replacing the conventional cladding system (zirconium) with a new material or coating that has specific thermomechanical properties. aim of this study is to evaluate neutronics performance chromium and design solutions. A Zircaloy–uranium (Zr–U) currently used as standard in pressurized water reactors around world. This investigation presents benefits...