| Abstract Scope |
Irradiation-assisted stress corrosion cracking (IASCC) and stress corrosion cracking (SCC) of austenitic stainless steel affect the structural integrity of light-water based nuclear systems. Over the past 40 years, significant progress has been made regarding the fundamental understandings of these phenomena in high temperature water systems. Strategies, including water chemistry control, weld residual stress management, steel sensitization management, high Cr alloy design, etc., have been implemented. This talk highlights our continuing efforts to understand these phenomena and develop new alloying strategies to improve the IASCC and SCC resistance of austenitic stainless steel in high temperature water environments. In particular, the talk will discuss two technical topics, including (1) the new mechanistic understanding of the superior IASCC resistance of 316L stainless steel made by laser additive manufacturing; (2) developing radiation and cracking resistant stainless steel for nuclear environments. These work aim to provide advanced stainless steel design concepts to future reactor applications. |