Paper
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122024
Mechanical characterization of austenitic stainless steel under high-level ion-irradiation using nanoindentation experiment and simulation
Journal of Materials Research and TechnologyVan-Thanh Pham, Jong-Sung Kim, Hyun Joon Eom, Changheui JangLINK -
112024
Effect of initial microstructure on irradiation induced microstructure evolution in δ-ferrite in an austenitic stainless steel weld
Journal of Nuclear MaterialsByeong Seo Kong, Ji Ho Shin, Chaewon Jeong, Changheui JangLINK -
102024
Effect of impurity addition on the corrosion and carburization behavior of alloy 800HT in CO2 environment at 600° C
Journal of Materials Research and TechnologyMuthu Shanmugam Mannan, Gokul Obulan Subramanian, Taejeong An, Changheui JangLINK -
92024
The effect of microstructure of an advanced duplex stainless steel on the pitting corrosion and chloride-induced stress corrosion cracking resistance
Corrosion ScienceChaewon Jeong, Byeong Seo Kong, Junjie Chen, Qian Xiao, Changheui JangLINK -
82024
High temperature corrosion of wrought and wire arc additively manufactured 316L stainless steel in a simulated boiler environment
Journal of Materials Research and TechnologyMuthu Shanmugam Mannan, Changheui JangLINK -
72024
Long-term thermal aging of austenitic stainless-steel weld: Microstructure evolution in δ-ferrite and δ/γ phase boundary and apparent recovery of mechanical properties
Journal of Materials Research and TechnologyShoaib Mehboob, Byeong Seo Kong, Changheui JangLINK -
62024
Corrosion behaviour of Al-containing alloys in Cl-based molten salt environment
Journal of Nuclear MaterialsBright O Okonkwo, Chaewon Kim, Taejeong An, Changheui Jang, Dokyu Kang, Wonseok Yang, Sungyeol ChoiLINK -
52024
High-temperature corrosion and carburization behaviour of austenitic stainless steels in impurity-added CO2 environments
Corrosion ScienceGokul Obulan Subramanian, Sung Hwan Kim, Changheui Jang, Yu-Lung ChiuLINK -
42024
Assessment of environmental fatigue in nuclear power plants: A comparative analysis of the effects of plasticity correction
Nuclear Engineering and TechnologyTae-Song Han, Hee-Jin Kim, Nam-Su Huh, Hyeong-Yeon Lee, Changheui JangLINK -
32024
Effect of dissolved hydrogen on the early corrosion behavior of 316 stainless steel in simulated PWR environments
Journal of Nuclear MaterialsHyeon Bae Lee, Changheui JangLINK -
22024
Oxidation behavior of the directed energy deposited 316L stainless steel in supercritical carbon dioxide environment: Effect of post-manufacturing heat treatment
Additive ManufacturingJunjie Chen, Hyeon Bae Lee, Chaewon Jeong, Qian Xiao, Kyungnam Jang, Taejeong An, Changheui JangLINK -
12024
Development of a duplex stainless steel for dry storage canister with improved chloride-induced stress corrosion cracking resistance
Nuclear Engineering and TechnologyChaewon Jeong, Ji Ho Shin, Byeong Seo Kong, Junjie Chen, Qian Xiao, Changheui Jang, Yun-Jae KimLINK
