Inelastic Cyclic Deformation Behaviors of Type 316H Stainless Steel for Reactor Pressure Vessel of Sodium-Cooled Fast Reactor at Elevated Temperatures

被引:4
|
作者
Yoon, Ji-Hyun [1 ,2 ]
Kim, Young-Chun [2 ]
Hong, Seokmin [1 ]
Koo, Gyeong-Hoi [1 ]
Lee, Bong-Sang [1 ,2 ]
机构
[1] Korea Atom Energy Res Inst, Daejeon 34057, South Korea
[2] Univ Sci & Technol, Daejeon 34113, South Korea
来源
关键词
Type; 316H; sodium-cooled fast reactor; dynamic strain aging; inelastic; ratcheting; FATIGUE BEHAVIOR; TENSILE;
D O I
10.3365/KJMM.2015.53.10.681
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Type 316H stainless steel is a primary candidate material for a reactor pressure vessel of a sodium-cooled fast (SFR) reactor which is under development in Korea. The reactor pressure vessel for a SFR is subjected to inelastic deformation induced by cyclic thermal stress. Fully reversed cyclic testing and ratcheting testing at elevated temperatures were performed to characterize the inelastic cyclic deformation behaviors of Type 316H stainless steel at the SFR operating temperature. It was found that cyclic hardening of Type 316H stainless steel was enhanced, and the accumulation of ratcheting deformation of Type 316H stainless steel was retarded at around the SFR operating temperature. The results of the tensile testing and the microstructural investigation for dislocated structures after the inelastic deformation testing showed that dynamic strain aging affected the inelastic cyclic deformation behavior of Type 316 stainless steel at around the SFR operating temperature.
引用
收藏
页码:681 / 687
页数:7
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