-
Study of the degradation mechanisms of zirconium alloy nuclear fuel claddings...
In nuclear plants, some accidental situations can result in air exposure of Pressurized Water Reactor (PWR) fuelassemblies: air ingress following a breach in the... -
High temperature creep behavior in the (α + β) phase temperature range of M5®...
The isothermal steady-state creep behavior of a M5® thin sheet alloy in a vacuum environment was investigated in the (α+β) temperature, low-stress (1-10MPa) range. To...
