Paper
-
17
Feasibility assessment of the alumina‐forming duplex stainless steels as accident tolerant fuel cladding materials for light water reactors
International Journal of Energy ResearchChaewon Kim, Hyunmyung Kim, Changheui Jang, Kangsan Kim, Yonghee Kim, Seungjae Lee, Hun JangLINK -
16
Effect of Minor Alloying Elements on the Oxidation Behavior of Ni-Base Alloys in a High-Temperature Steam Environment
Oxidation of MetalsSung Hwan Kim, Chaewon Kim, Ji-Hwan Cha, Changheui Jang, Young Soo YooLINK -
15
Cr diffusion coating to improve the corrosion resistance of an ODS steel in super-critical carbon dioxide environment
Surface and Coatings TechnologyChaewon Kim, Sung Hwan Kim, Ji-Hwan Cha, Changheui Jang, Tae Kyu KimLINK -
14
Corrosion behaviors of four stainless steels with similar chromium content in supercritical carbon dioxide environment at 650 C
Corrosion ScienceHongsheng Chen, Sung Hwan Kim, Chaewon Kim, Junjie Chen, Changheui JangLINK -
13
Environmentally-Assisted Fatigue Behavior of 316 Stainless Steels in Simulated PWR Primary Environment: Strain Holding, Zn-Addition, and Their Combined Effect
Pressure Vessels and Piping ConferenceHyeon Bae Lee, Ho-Sub Kim, Junjie Chen, Changheui Jang, Tae Soon Kim, Gary L Stevens, Kawaljit AhluwaliaLINK -
12
Investigation on the thermal butt fusion performance of the buried high density polyethylene piping in nuclear power plant
Nuclear Engineering and TechnologyJong-Sung Kim, Young-Jin Oh, Sun-Woong Choi, Changheui JangLINK -
11
Effect of thermal aging on the corrosion behaviors of ER316L stainless steel welds in simulated PWR environments
Junjie Chen, Changheui Jang, Qian Xiao, Byeong Seo Kong, Gokul Obulan Subramanian, Ji Ho ShinLINK -
10
Effects of heat treatment on mechanical properties and sensitization behavior of materials in dissimilar metal weld
International Journal of Pressure Vessels and PipingHo-Sub Kim, Jiho Shin, Byeong Seo Kong, Sunghoon Hong, Seungjin Oh, Jong-Dae Hong, Changheui Jang, Sanghoon LeeLINK -
9
Effect of zinc on the environmentally-assisted fatigue behavior of 316 stainless steels in simulated PWR primary environment
Corrosion ScienceHo-Sub Kim, Hyeon Bae Lee, Junjie Chen, Changheui Jang, Tae Soon Kim, Gary L Stevens, Kawaljit AhluwaliaLINK -
8
The corrosion behaviour of alloy 690 tube in simulated PWR secondary water with the effect of solid diffusing hydrogen
Journal of Nuclear MaterialsJunjie Chen, Zhanpeng Lu, Fanjiang Meng, Xuelian Xu, Qian Xiao, Ho-Sub Kim, Changheui JangLINK -
7
Comparison of oxide layers formed on the low-cycle fatigue crack surfaces of Alloy 690 and 316 SS tested in a simulated PWR environment
Nuclear Engineering and TechnologyJunjie Chen, Andrieanto Nurrochman, Jong-Dae Hong, Tae Soon Kim, Changheui Jang, Yongsun YiLINK -
6
Advancement of Supercritical Carbon Dioxide Technology through Round Robin Testing and Fundamental Modeling
OSTI.GOVJulie Tucker, Líney Árnadóttir, Mark Anderson, Bruce Pint, Ömer Doğan, Henry Saari, Changheui Jang, Steven KungLINK -
5
Development and Mechanical Characterization of Nuclear Accident Tolerant Duplex Stainless Steel (ADSS)
TMS Annual MeetingHyeonsu Do, Hyunmyung Kim, Changheui Jang, Dongchan JangLINK -
4
Integrity of Alumina Catalytic Support Prepared by Anodization in a High Temperature Steam Environment
Metals and Materials InternationalChaewon Kim, Sung Hwan Kim, Gokul Obulan Subramanian, Changheui Jang, Keun Man ParkLINK -
3
400° C aging embrittlement of FeCrAl alloys: Microstructure and fracture behavior
Materials Science and Engineering: AHyunmyung Kim, Gokul Obulan Subramanian, Chaewon Kim, Hun Jang, Changheui JangLINK -
2
Influence of δ-ferrite content on thermal aging induced mechanical property degradation in cast stainless steels
Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems–Water ReactorsThak Sang Byun, Timothy G Lach, Ying Yang, Changheui JangLINK -
1
Electrochemical Characteristics of Delta Ferrite in Thermally Aged Austenitic Stainless Steel Weld
Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems–Water ReactorsGokul Obulan Subramanian, Sunghoon Hong, Ho Jung Lee, Byeong Seo Kong, Kyoung-Soo Lee, Thak Sang Byun, Changheui JangLINK