Paper
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34
On the feasibility of duplex stainless steel 2205 as an accident tolerant fuel cladding material for light water reactors
Journal of Nuclear MaterialsQian Xiao, Chaewon Kim, Changheui Jang, Chaewon Jeong, Hyunmyung Kim, Junjie Chen, Woong HeoLINK -
33
Characterization of oxide layers formed on type 316 stainless steel exposed to the simulated PWR primary water environment with varying dissolved hydrogen and zinc concentrations
Journal of Nuclear MaterialsHyeon Bae Lee, Junjie Chen, Shu Meng, Changheui Jang, Su Hyun Park, Qian Xiao, Ho Jung Lee, Kyung-Hwan NaLINK -
32
Classification of ultrasonic signals of thermally aged cast austenitic stainless steel (CASS) using machine learning (ML) models
Nuclear Engineering and TechnologyJin-Gyum Kim, Changheui Jang, Sung-Sik KangLINK -
31
Effect of heat treatment on grain boundary carbides and primary water stress corrosion cracking resistance of Alloy 182 weld
Corrosion ScienceHo-Sub Kim, Junjie Chen, Hyeon Bae Lee, Ji Ho Shin, Byeong Seo Kong, Seungjin Oh, Hun Jang, Changheui JangLINK -
30
The carburization behavior of alloy 800HT in high temperature supercritical-CO2
Materials LettersGokul Obulan Subramanian, Sung Hwan Kim, Changheui JangLINK -
29
Effect of Stress Magnitude on Pit Growth Rate of 304 Austenitic Stainless Steel in Chloride Environments
MetalsJae-Yoon Jeong, Chaewon Jeong, Yun-Jae Kim, Changheui JangLINK -
28
High-temperature steam oxidation behavior of alumina-forming duplex FeNiCrAl and ferritic FeCrAl alloys at 800 °C to 1050 °C
Corrosion ScienceChaewon Kim, Hyunmyung Kim, Woong Heo, Changheui Jang, Sung Yong Lee, Seungjae Lee, Jin-Soo LeeLINK -
27
Supercritical-CO2 corrosion behavior of alumina-and chromia-forming heat resistant alloys with Ti
Corrosion ScienceGokul Obulan Subramanian, Sung Hwan Kim, Junjie Chen, Changheui JangLINK -
26
Effect of surface conditions and alloying elements on the early oxidation behaviour of two austenitic alloys in the pure steam environment
Applied Surface ScienceJunjie Chen, Changheui Jang, Qian Xiao, Hyun Bae Lee, Chaewon Kim, Sung Hwan Kim, Ji Ho Shin, Gokul Obulan SubramanianLINK -
25
Corrosion behavior of Fe-based candidate accident tolerant fuel cladding alloys in spent fuel pool environment―Effect of prior corrosion
Journal of Nuclear MaterialsQian Xiao, Changheui Jang, Chaewon Kim, Junjie Chen, Chaewon Jeong, Sung Hwan KimLINK -
24
Dynamic evolution of nanosized NbC precipitates in austenite matrix during deformation and its contribution to strengthening
Materials Science and Engineering: AJi Ho Shin, Byeong Seo Kong, Hyun Joon Eom, Changheui Jang, Hyeonsu Do, Dongchan JangLINK -
23
On the use of non-destructive, gigahertz ultrasonics to rapidly screen irradiated steels for swelling resistance
Materials Characterization, 111017Nouf Almousa, Benjamin Dacus, Kevin B Woller, Ji Ho Shin, Changheui Jang, Lin Shao, Frank A Garner, Adam Gabriel, Michael P ShortLINK -
22
Effect of proton irradiation on δ-ferrite in the thermally aged austenitic stainless steel weld: Precipitation of G-phase and additional hardening
Journal of Nuclear Materials 544, 152656BS Kong, JH Shin, C Jang, Y Na, D Jang, HJ Lee, JS YangLINK -
21
Corrosion behavior of Fe-based candidate accident tolerant fuel cladding alloys in spent fuel pool environment―Effect of prior corrosion
Journal of Nuclear Materials, 152845Q Xiao, C Jang, C Kim, J Chen, C Jeong, SH KimLINK -
20
Dynamic evolution of nanosized NbC precipitates in austenite matrix during deformation and its contribution to strengthening
Materials Science and Engineering: A, 140816JH Shin, BS Kong, HJ Eom, C Jang, H Do, D JangLINK -
19
Effect of Ti Content on the Microstructure and High-Temperature Creep Property of Cast Fe-Ni-Based Alloys with High-Al Content
Materials 14 (1), 82GO Subramanian, C Jang, JH Shin, C JeongLINK -
18
Corrosion behavior of stainless steels in simulated PWR primary water: The effect of composition and matrix phases
Corrosion ScienceQian Xiao, Changheui Jang, Chaewon Kim, Hyunmyung Kim, Junjie Chen, Hyeon Bae LeeLINK -
17
“Effect of proton irradiation on δ-ferrite in the thermally aged austenitic stainless steel weld: Precipitation of G-phase and additional hardening”
Journal of Nuclear MaterialsByeong Seo Kong, Jiho Shin, Changheui Jang, Ye-eun Na, Dongchan Jang, Ho Jung Lee, Jun-Seog YangLINK -
16
Corrosion and creep behavior of a Ni-base alloy in supercritical-carbon dioxide environment at 650° C
Corrosion ScienceSung Hwan Kim, Ji-Hwan Cha, Changheui JangLINK -
15
Evaluation of thermal ageing activation energy of δ-ferrite in an austenitic stainless steel weld using nanopillar compression test
Scripta MaterialiaByeong Seo Kong, Jiho Shin, Gokul Obulan Subramanian, Junjie Chen, Changheui Jang, Ye-eun Na, Dongchan Jang, Ho Jung Lee, Jun-Seog YangLINK -
14
Mechanical Properties of Ion-Irradiated Stainless Steel Determined by Nanoindentation Tests and Finite Element Analyses
Pressure Vessels and Piping ConferenceJae Min Sim, Yoon-Suk Chang, Byeong Seo Kong, Changheui JangLINK -
13
Influence of the Nano Carbide dispersed Advanced radiation Resistant austenitic stainless Steels (NC-ARES) microstructure on the radiation resistance under ion irradiation
Transactions of the Korean Nuclear Society Virtual Spring MeetingJi Ho Shin, Byeong Seo Kong, Changheui Jang, Mike P ShortLINK -
12
Effect of thermal ageing on the corrosion behaviour of austenitic stainless steel welds in the simulated PWR primary water
Corrosion ScienceJunjie Chen, Changheui Jang, Byeon Seo Kong, Qian Xiao, Gokul Obulan Subramanian, Ho Sub Kim, Ji Ho ShinLINK -
11
“Effect of Nb on the electrical resistivity of ZrO2 layer formed on Zr alloys”
Journal of Nuclear MaterialsOh Hyun Kwon, Ji Ho Shin, Changheui Jang, Jong-Sung Yoo, Ho-Sub Kim, Young-il Kwon, Hyun Gil KimLINK -
10
Chromium Diffusion Coating on an ODS Ferritic-Martensitic Steel and Its Oxidation Behavior in Air and Steam Environments
CoatingsChaewon Kim, Sung Hwan Kim, Ji-Hwan Cha, Changheui Jang, Tae Kyu KimLINK -
9
Corrosion Behavior of Si Diffusion Coating on an Austenitic Fe-Base Alloy in High Temperature Supercritical-Carbon Dioxide and Steam Environment
CoatingsSung Hwan Kim, Chaewon Kim, Ji-Hwan Cha, Changheui JangLINK -
8
Role of residual ferrites on crevice SCC of austenitic stainless steels in PWR water with high-dissolved oxygen
Nuclear Engineering and TechnologyAbdullah Sinjlawi, Junjie Chen, Ho-Sub Kim, Hyeon Bae Lee, Changheui Jang, Sanghoon LeeLINK -
7
Development of aluminide diffusion coatings on ODS ferritic-martensitic steel for corrosion resistance in high temperature super critical-carbon dioxide environment
Applied Surface ScienceChaewon Kim, Ji-Hwan Cha, Sung Hwan Kim, Changheui Jang, Tae Kyu KimLINK -
6
Microstructure and Tensile Properties of Diffusion Bonded Austenitic Fe-Base Alloys—Before and After Exposure to High Temperature Supercritical-CO2
MetalsSung Hwan Kim, Ji-Hwan Cha, Changheui Jang, Injin SahLINK -
5
Effect of high-temperature supercritical carbon dioxide exposure on the microstructure and tensile properties of diffusion-bonded Alloy 690
Journal of Materials ScienceHongsheng Chen, Sung Hwan Kim, Changheui JangLINK -
4
Applicability of nonlinear ultrasonic technique to evaluation of thermally aged CF8M cast stainless steel
Nuclear Engineering and TechnologyJongbeom Kim, Jin-Gyum Kim, Byeongseo Kong, Kyung-Mo Kim, Changheui Jang, Sung-Sik Kang, Kyung-Young JhangLINK -
3
Development of thermo-mechanical processing to form high density of uniformly distributed nanosized carbides in austenitic stainless steels
Materials Science and Engineering: AJi Ho Shin, Ho-Sub Kim, Byeong Seo Kong, Gokul Obulan Subramanian, Sunghoon Hong, Ho Jung Lee, Changheui JangLINK -
2
HIGH-STRENGTH Fe-Cr-Ni-Al MULTIPLEX STAINLESS STEEL AND MANUFACTURING METHOD THEREFOR
JANG Changheui, Hyunmyung Kim, Gokul Obulan Subramanian, Jin Woo Heo, Ho Jung Lee, Sunghoon Hong, KIM ChaewonLINK -
1
Measurement of Fracture Toughness of Pure Tungsten Using a Small-Sized Compact Tension Specimen
MaterialsByeong Seo Kong, Ji Ho Shin, Changheui Jang, Hyoung Chan KimLINK