Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Subject CRACK-GROWTH

Showing results 1 to 4 of 4

1
Effect of heat treatment on corrosion behaviour of additively manufactured 316L stainless steel in high-temperature water

Xiao, Qian; Chen, Junjie; Lee, Hyeon Bae; Jang, Changheui; Jang, Kyungnam, CORROSION SCIENCE, v.210, 2023-01

2
ENVIRONMENTAL FATIGUE OF METALLIC MATERIALS IN NUCLEAR POWER PLANTS - A REVIEW OF KOREAN TEST PROGRAMS

Jang, Changheui; Jang, Hun; Hong, Jong-Dae; Cho, Hyunchul; Kim, Tae Soon; Lee, Jae-Gon, NUCLEAR ENGINEERING AND TECHNOLOGY, v.45, no.7, pp.929 - 940, 2013-12

3
Low-cycle fatigue behaviors of two heats of SA508 Gr.1a low alloy steel in 310 degrees C air and deoxygenated water-Effects of dynamic strain aging and microstructures

Jang, Hun; Kim, Jeong-Hyeon; Jang, Chang-Heui; Lee, Jae-Gon; Kim, Tae-Soon, MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, v.580, pp.41 - 50, 2013-09

4
The effects of dissolved hydrogen on the corrosion behavior of Alloy 182 Cross Mark in simulated primary water

Xu, Jian; Shoji, Tetsuo; Jang, Changheui, CORROSION SCIENCE, v.97, pp.115 - 125, 2015-05

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