PREDICTION OF TRANSIENT MECHANICAL RESPONSE OF TYPE-316 STAINLESS-STEEL CLADDING USING AN EQUATION-OF-STATE APPROACH

Correlations of short-term mechanical properties of breeder reactor core component materials play an important role in design and safety analysis. A description of the short-term high strain-rate flow properties for 20% CW 316 SS was developed using a mechanical equation-of-state approach developed by Hart. The stress strain-rate relationship was developed from tensile yield strength data over the temperature range 427-871°C. The description, developed for constant structure or hardness, was then combined with simplified work hardening and recovery models to predict response of unirradiated 20% CW 316 SS over loading paths important to breeder reactor cladding. The advantage of the method is that it provides a description of mechanical response under a wide range of loading conditions, yet the formulation is simple in form with a single structure parameter used to describe material structure changes. The method is also shown to be applicable to neutron irradiated 316 SS. This implies that while neutron irradiation can change the hardness and ductility of 316 SS, the basic flow law is unchanged by irradiation. © 1979.