Serrated Flow Behavior of Aisi 3161 Austenitic Stainless Steel for Nuclear Reactors NQingshan LiDSchool of Mechanical Engineering, Shanghai Jiao Tong University, No. 800 Dongchuan Road, Shanghai 200240, China NYinzhong ShenDSchool of Mechanical Engineering, Shanghai Jiao Tong University, No. 800 Dongchuan Road, Shanghai 200240, ChinaMshenyz@sjtu.edu.cn NPengcheng HanDSchool of Mechanical Engineering, Shanghai Jiao Tong University, No. 800

摘要

AISI 316L austenitic stainless steel is a candidate material for Generation IV reactors. In order to investigate the influence of temperature on serrated flow behavior, tensile tests were performed at temperatures ranging from 300 to 700 °C at an initial strain rate of 2xl0~(-4)s~(-1). Another group of tensile tests were carried out at strain rates ranging from 1x10~(-4) to lxl0~(-2)s~(-1)at 600oC to examine the influence of strain rates on serrated flow behavior. The steel exhibited serrated flow, suggesting the occurrence of dynamic strain ageing at 450-650°C. No plateau of yield stresses of the steel was observed at an initial strain rate of 2x10~(-4) s~(-1). The effective activation energy for serrated flow occurrence was calculated to be about 254.72 kJ/mol~(-1). Cr, Mn, Ni and Mo solute atoms are expected to be responsible for dynamic strain ageing at high temperatures of 450-650 °C in the steel.