Serrated Flow Behavior of Aisi 316l Austenitic Stainless Steel for Nuclear Reactors

3rd Annual International Workshop on Materials Science and Engineering

Li, Qingshan^1 ; Shen, Yinzhong^1 ; Han, Pengcheng^1

School of Mechanical Engineering, Shanghai Jiao Tong University, No. 800 Dongchuan Road, Shanghai

200240, China^1

关键词: Aisi 316l austenitic stainless steels;    Candidate materials;    Dynamic strain ageing;    Effective activation energy;    Generation IV reactors;    High temperature;    Initial strains;    Serrated flow;   

Others  :  https://iopscience.iop.org/article/10.1088/1757-899X/250/1/012013/pdf
DOI  :  10.1088/1757-899X/250/1/012013

来源: IOP

【 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 2×10-4s-1. Another group of tensile tests were carried out at strain rates ranging from 1×10-4to 1×10-2s-1at 600 °C 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 2×10-4s-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.