Showing results 1 to 3 of 3
Comparison of oxide layers formed on the low-cycle fatigue crack surfaces of Alloy 690 and 316 SS tested in a simulated PWR environment![]() Chen, Junjie; Nurrochman, Andrieanto; Hong, Jong-Dae; Kim, Tae Soon; Jang, Changheui; Yi, Yongsun, NUCLEAR ENGINEERING AND TECHNOLOGY, v.51, no.2, pp.479 - 489, 2019-04 |
Low cycle fatigue behavior of alloy 690 in simulated PWR water-Effects of dynamic strain aging and hydrogen Hong, Jongdae; Lee, Junho; Jang, Changheui; Kim, Tae Soon, MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, v.611, pp.37 - 44, 2014-08 |
The corrosion behaviour of alloy 690 tube in simulated PWR secondary water with the effect of solid diffusing hydrogen Chen, Junjie; Lu, Zhanpeng; Meng, Fanjiang; Xu, Xuelian; Xiao, Qian; Kim, Ho-Sub; Jang, Changheui, JOURNAL OF NUCLEAR MATERIALS, v.517, pp.179 - 191, 2019-04 |
Discover