PUBLICATION

Paper

Total : 361
  • 361
    2024

    Effect of dissolved hydrogen on the early corrosion behavior of 316 stainless steel in simulated PWR environments

    Journal of Nuclear Materials
    Hyeon Bae Lee, Changheui Jang
    LINK
  • 360
    2024

    Oxidation behavior of the directed energy deposited 316L stainless steel in supercritical carbon dioxide environment: Effect of post-manufacturing heat treatment

    Additive Manufacturing
    Junjie Chen, Hyeon Bae Lee, Chaewon Jeong, Qian Xiao, Kyungnam Jang, Taejeong An, Changheui Jang
    LINK
  • 359
    2024

    Development of a duplex stainless steel for dry storage canister with improved chloride-induced stress corrosion cracking resistance

    Nuclear Engineering and Technology
    Chaewon Jeong, Ji Ho Shin, Byeong Seo Kong, Junjie Chen, Qian Xiao, Changheui Jang, Yun-Jae Kim
    LINK
  • 358
    2023

    Accelerated Formation of Oxide Layers on Zircaloy-4 Utilizing Air Oxidation and Comparison with Water-Corroded Oxide Layers

    Materials
    Shanmugam Mannan Muthu, Hyeon-Bae Lee, Bright O Okonkwo, Dong Wang, Changheui Jang, Taehyung Na
    LINK
  • 357
    2023

    Development and optimization of trivalent chromium electrodeposit on 304L stainless steel to improve corrosion resistance in chloride-containing environment

    Heliyon
    Bright O Okonkwo, Chaewon Jeong, Hyeon Bae Lee, Changheui Jang, Ehsan Rahimi, Ali Davoodi
    LINK
  • 356
    2023

    Study on Microstructure and Thermal Cycling Performance of the Plasma-sprayed YSZ Coating in Simulated Turbine Environment

    High Temperature Corrosion of Materials
    SM Muthu, M Arivarasu, Changheui Jang, S Viknesh, K Surya Prakash Reddy, M Venkateshkannan, VD Vishnu Siddharth, Nafeez Ahmed Liyakat
    LINK
  • 355
    2023

    Multiscale simulations for estimating mechanical properties of ion irradiated 308 based on microstructural features

    Nuclear Engineering and Technology
    Dong-Hyeon Kwak, Jae Min Sim, Yoon-Suk Chang, Byeong Seo Kong, Changheui Jang
    LINK
  • 354
    2023

    Development of Eco-Friendly Chromium Electrodeposit for Corrosion Resistance in Chloride-Containing Environment

    AMPP CORROSION Coneference
    Bright O Okonkwo, Chaewon Jeong, Taejeong An, Hyun Joon Eom, Changheui Jang
    LINK
  • 353
    2023

    Microstructures, tensile properties and corrosion behaviors of Fe20Cr25NiNb stainless steels with different Al contents in supercritical carbon dioxide

    Journal of Materials Research and Technology
    Hongsheng Chen, Jiandong Luo, Tengfei Zhang, Changheui Jang, Rui Tang, Baojun Dong, Jin Li, Xuesong Leng
    LINK
  • 352
    2023

    Stability and strengthening effect of aging induced-nanofeatures in δ-ferrite in an austenitic stainless-steel weld

    Journal of Materials Research and Technology
    Byeong Seo Kong, Ji Ho Shin, Chaewon Jeong, Changheui Jang, Sung-Sik Kang
    LINK
  • 351
    2023

    Evaluation of radiation resistance of an austenitic stainless steel with nanosized carbide precipitates using heavy ion irradiation at 200 dpa

    Nuclear Engineering and Technology
    Ji Ho Shin, Byeong Seo Kong, Chaewon Jeong, Hyun Joon Eom, Changheui Jang, Lin Shao
    LINK
  • 350
    2023

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

    Corrosion Science
    Qian Xiao, Junjie Chen, Hyeon Bae Lee, Changheui Jang, Kyungnam Jang
    LINK
  • 349
    2022

    Determination of Irradiated Stainless Steel Properties and Its Effects on Reactor Vessel Internals

    Pressure Vessels and Piping Conference
    Dong-Hyeon Kwak, Jae Min Sim, Yoon-Suk Chang, Byeong Seo Kong, Changheui Jang
    LINK
  • 348
    2022

    The effect of zinc addition on corrosion behavior of stainless steels with different phases in simulated PWR primary water

    Corrosion Science
    Su Hyun Park, Hyeon Bae Lee, Chaewon Kim, Bright O Okonkwo, Changheui Jang, Qian Xiao
    LINK
  • 347
    2022

    Advances on Cr and Ni electrodeposition for industrial applications—a Review

    Coatings
    Bright O Okonkwo, Chaewon Jeong, Changheui Jang
    LINK
  • 346
    2022

    Strain-Rate Dependence of Tensile Behavior in Commercial-Grade Tungsten—Effect of Recrystallization Condition

    Materials
    Byeong Seo Kong, Ji Ho Shin, Taejeong An, Changheui Jang, Hyoung Chan Kim
    LINK
  • 345
    2022

    Effect of microstructure evolution at the interphase boundary on the thermal ageing embrittlement of CF8M cast austenitic stainless steel

    International Journal of Pressure Vessels and Piping
    Byeong Seo Kong, Ji Ho Shin, Chaewon Jeong, Changheui Jang, Sung-Sik Kang
    LINK
  • 344
    2022

    Oxidation mechanism and kinetics of nuclear-grade FeCrAl alloys in the temperature range of 500–1500° C in steam

    Journal of Nuclear Materials
    Chaewon Kim, Chongchong Tang, Mirco Grosse, Yunhwan Maeng, Changheui Jang, Martin Steinbrueck
    LINK
  • 343
    2022

    Swelling resistance of an austenitic stainless steel with uniformly distributed nanosized NbC precipitates under heavy ion irradiation

    Journal of Nuclear Materials
    Ji Ho Shin, Byeong Seo Kong, Chaewon Jeong, Hyun Joon Eom, Changheui Jang, Nouf AlMousa, Kevin B Woller, Michael P Short
    LINK
  • 342
    2022

    Enhanced pitting resistance of directed energy deposition 316L stainless steel by post-manufacturing heat treatment

    npj Materials Degradation
    Junjie Chen, Qian Xiao, Hyeon Bae Lee, Chaewon Jeong, Kyungnam Jang, Changheui Jang
    LINK
  • 341
    2022

    Classification of ultrasonic signals of thermally aged cast austenitic stainless steel (CASS) using machine learning (ML) models

    Nuclear Engineering and Technology
    Jin-Gyum Kim, Changheui Jang, Sung-Sik Kang
    LINK
  • 340
    2022

    Corrosion behaviour of alumina-forming heat resistant alloy with Ti in high temperature steam

    Corrosion Science
    Gokul Obulan Subramanian, Chaewon Kim, Woong Heo, Changheui Jang
    LINK
  • 339
    2022

    Dissolution of nanosized NbC precipitates in austenite matrix during elastic deformation-Deleterious effect of high number density

    Materials Science and Engineering: A
    Hyun Joon Eom, Ji Ho Shin, Byeong Seo Kong, Chaewon Jeong, Changheui Jang, Daehyeok Ahn, Dongchan Jang
    LINK
  • 338
    2022

    Evaluation of thermal aging activation energies based on multi-scale mechanical property tests for an austenitic stainless steel weld beads

    Materials Science and Engineering: A
    Chaewon Jeong, Byeong Seo Kong, Ji Ho Shin, Junjie Chen, Qian Xiao, Changheui Jang
    LINK
  • 337
    2022

    Effects of ATF cladding properties on PWR responses to an SBO accident: A sensitivity analysis

    Annals of Nuclear Energy
    Ali Alraisi, Yongsun Yi, Suwon Lee, Saeed A Alameri, Maryam Qasem, Chan-Young Paik, Changheui Jang
    LINK
  • 336
    2021

    On the feasibility of duplex stainless steel 2205 as an accident tolerant fuel cladding material for light water reactors

    Journal of Nuclear Materials
    Qian Xiao, Chaewon Kim, Changheui Jang, Chaewon Jeong, Hyunmyung Kim, Junjie Chen, Woong Heo
    LINK
  • 335
    2021

    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 Materials
    Hyeon Bae Lee, Junjie Chen, Shu Meng, Changheui Jang, Su Hyun Park, Qian Xiao, Ho Jung Lee, Kyung-Hwan Na
    LINK
  • 334
    2021

    Classification of ultrasonic signals of thermally aged cast austenitic stainless steel (CASS) using machine learning (ML) models

    Nuclear Engineering and Technology
    Jin-Gyum Kim, Changheui Jang, Sung-Sik Kang
    LINK
  • 333
    2021

    Effect of heat treatment on grain boundary carbides and primary water stress corrosion cracking resistance of Alloy 182 weld

    Corrosion Science
    Ho-Sub Kim, Junjie Chen, Hyeon Bae Lee, Ji Ho Shin, Byeong Seo Kong, Seungjin Oh, Hun Jang, Changheui Jang
    LINK
  • 332
    2021

    The carburization behavior of alloy 800HT in high temperature supercritical-CO2

    Materials Letters
    Gokul Obulan Subramanian, Sung Hwan Kim, Changheui Jang
    LINK
  • 331
    2021

    Effect of Stress Magnitude on Pit Growth Rate of 304 Austenitic Stainless Steel in Chloride Environments

    Metals
    Jae-Yoon Jeong, Chaewon Jeong, Yun-Jae Kim, Changheui Jang
    LINK
  • 330
    2021

    High-temperature steam oxidation behavior of alumina-forming duplex FeNiCrAl and ferritic FeCrAl alloys at 800 °C to 1050 °C

    Corrosion Science
    Chaewon Kim, Hyunmyung Kim, Woong Heo, Changheui Jang, Sung Yong Lee, Seungjae Lee, Jin-Soo Lee
    LINK
  • 329
    2021

    Supercritical-CO2 corrosion behavior of alumina-and chromia-forming heat resistant alloys with Ti

    Corrosion Science
    Gokul Obulan Subramanian, Sung Hwan Kim, Junjie Chen, Changheui Jang
    LINK
  • 328
    2021

    Effect of surface conditions and alloying elements on the early oxidation behaviour of two austenitic alloys in the pure steam environment

    Applied Surface Science
    Junjie Chen, Changheui Jang, Qian Xiao, Hyun Bae Lee, Chaewon Kim, Sung Hwan Kim, Ji Ho Shin, Gokul Obulan Subramanian
    LINK
  • 327
    2021

    Corrosion behavior of Fe-based candidate accident tolerant fuel cladding alloys in spent fuel pool environment―Effect of prior corrosion

    Journal of Nuclear Materials
    Qian Xiao, Changheui Jang, Chaewon Kim, Junjie Chen, Chaewon Jeong, Sung Hwan Kim
    LINK
  • 326
    2021

    Dynamic evolution of nanosized NbC precipitates in austenite matrix during deformation and its contribution to strengthening

    Materials Science and Engineering: A
    Ji Ho Shin, Byeong Seo Kong, Hyun Joon Eom, Changheui Jang, Hyeonsu Do, Dongchan Jang
    LINK
  • 325
    2021

    On the use of non-destructive, gigahertz ultrasonics to rapidly screen irradiated steels for swelling resistance

    Materials Characterization, 111017
    Nouf Almousa, Benjamin Dacus, Kevin B Woller, Ji Ho Shin, Changheui Jang, Lin Shao, Frank A Garner, Adam Gabriel, Michael P Short
    LINK
  • 324
    2021

    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, 152656
    BS Kong, JH Shin, C Jang, Y Na, D Jang, HJ Lee, JS Yang
    LINK
  • 323
    2021

    Corrosion behavior of Fe-based candidate accident tolerant fuel cladding alloys in spent fuel pool environment―Effect of prior corrosion

    Journal of Nuclear Materials, 152845
    Q Xiao, C Jang, C Kim, J Chen, C Jeong, SH Kim
    LINK
  • 322
    2021

    Dynamic evolution of nanosized NbC precipitates in austenite matrix during deformation and its contribution to strengthening

    Materials Science and Engineering: A, 140816
    JH Shin, BS Kong, HJ Eom, C Jang, H Do, D Jang
    LINK
  • 321
    2021

    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), 82
    GO Subramanian, C Jang, JH Shin, C Jeong
    LINK
  • 320
    2021

    Corrosion behavior of stainless steels in simulated PWR primary water: The effect of composition and matrix phases

    Corrosion Science
    Qian Xiao, Changheui Jang, Chaewon Kim, Hyunmyung Kim, Junjie Chen, Hyeon Bae Lee
    LINK
  • 319
    2021

    “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
    Byeong Seo Kong, Jiho Shin, Changheui Jang, Ye-eun Na, Dongchan Jang, Ho Jung Lee, Jun-Seog Yang
    LINK
  • 318
    2021

    Corrosion and creep behavior of a Ni-base alloy in supercritical-carbon dioxide environment at 650° C

    Corrosion Science
    Sung Hwan Kim, Ji-Hwan Cha, Changheui Jang
    LINK
  • 317
    2021

    Evaluation of thermal ageing activation energy of δ-ferrite in an austenitic stainless steel weld using nanopillar compression test

    Scripta Materialia
    Byeong Seo Kong, Jiho Shin, Gokul Obulan Subramanian, Junjie Chen, Changheui Jang, Ye-eun Na, Dongchan Jang, Ho Jung Lee, Jun-Seog Yang
    LINK
  • 316
    2021

    Mechanical Properties of Ion-Irradiated Stainless Steel Determined by Nanoindentation Tests and Finite Element Analyses

    Pressure Vessels and Piping Conference
    Jae Min Sim, Yoon-Suk Chang, Byeong Seo Kong, Changheui Jang
    LINK
  • 315
    2021

    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 Meeting
    Ji Ho Shin, Byeong Seo Kong, Changheui Jang, Mike P Short
    LINK
  • 314
    2021

    Effect of thermal ageing on the corrosion behaviour of austenitic stainless steel welds in the simulated PWR primary water

    Corrosion Science
    Junjie Chen, Changheui Jang, Byeon Seo Kong, Qian Xiao, Gokul Obulan Subramanian, Ho Sub Kim, Ji Ho Shin
    LINK
  • 313
    2021

    “Effect of Nb on the electrical resistivity of ZrO2 layer formed on Zr alloys”

    Journal of Nuclear Materials
    Oh Hyun Kwon, Ji Ho Shin, Changheui Jang, Jong-Sung Yoo, Ho-Sub Kim, Young-il Kwon, Hyun Gil Kim
    LINK
  • 312
    2021

    Chromium Diffusion Coating on an ODS Ferritic-Martensitic Steel and Its Oxidation Behavior in Air and Steam Environments

    Coatings
    Chaewon Kim, Sung Hwan Kim, Ji-Hwan Cha, Changheui Jang, Tae Kyu Kim
    LINK
  • 311
    2021

    Corrosion Behavior of Si Diffusion Coating on an Austenitic Fe-Base Alloy in High Temperature Supercritical-Carbon Dioxide and Steam Environment

    Coatings
    Sung Hwan Kim, Chaewon Kim, Ji-Hwan Cha, Changheui Jang
    LINK
  • 310
    2021

    Role of residual ferrites on crevice SCC of austenitic stainless steels in PWR water with high-dissolved oxygen

    Nuclear Engineering and Technology
    Abdullah Sinjlawi, Junjie Chen, Ho-Sub Kim, Hyeon Bae Lee, Changheui Jang, Sanghoon Lee
    LINK
  • 309
    2021

    Development of aluminide diffusion coatings on ODS ferritic-martensitic steel for corrosion resistance in high temperature super critical-carbon dioxide environment

    Applied Surface Science
    Chaewon Kim, Ji-Hwan Cha, Sung Hwan Kim, Changheui Jang, Tae Kyu Kim
    LINK
  • 308
    2021

    Microstructure and Tensile Properties of Diffusion Bonded Austenitic Fe-Base Alloys—Before and After Exposure to High Temperature Supercritical-CO2

    Metals
    Sung Hwan Kim, Ji-Hwan Cha, Changheui Jang, Injin Sah
    LINK
  • 307
    2021

    Effect of high-temperature supercritical carbon dioxide exposure on the microstructure and tensile properties of diffusion-bonded Alloy 690

    Journal of Materials Science
    Hongsheng Chen, Sung Hwan Kim, Changheui Jang
    LINK
  • 306
    2021

    Applicability of nonlinear ultrasonic technique to evaluation of thermally aged CF8M cast stainless steel

    Nuclear Engineering and Technology
    Jongbeom Kim, Jin-Gyum Kim, Byeongseo Kong, Kyung-Mo Kim, Changheui Jang, Sung-Sik Kang, Kyung-Young Jhang
    LINK
  • 305
    2021

    Development of thermo-mechanical processing to form high density of uniformly distributed nanosized carbides in austenitic stainless steels

    Materials Science and Engineering: A
    Ji Ho Shin, Ho-Sub Kim, Byeong Seo Kong, Gokul Obulan Subramanian, Sunghoon Hong, Ho Jung Lee, Changheui Jang
    LINK
  • 304
    2021

    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 Chaewon
    LINK
  • 303
    2021

    Measurement of Fracture Toughness of Pure Tungsten Using a Small-Sized Compact Tension Specimen

    Materials
    Byeong Seo Kong, Ji Ho Shin, Changheui Jang, Hyoung Chan Kim
    LINK
  • 302
    2020

    Feasibility assessment of the alumina‐forming duplex stainless steels as accident tolerant fuel cladding materials for light water reactors

    International Journal of Energy Research
    Chaewon Kim, Hyunmyung Kim, Changheui Jang, Kangsan Kim, Yonghee Kim, Seungjae Lee, Hun Jang
    LINK
  • 301
    2020

    Effect of Minor Alloying Elements on the Oxidation Behavior of Ni-Base Alloys in a High-Temperature Steam Environment

    Oxidation of Metals
    Sung Hwan Kim, Chaewon Kim, Ji-Hwan Cha, Changheui Jang, Young Soo Yoo
    LINK
  • 300
    2020

    Cr diffusion coating to improve the corrosion resistance of an ODS steel in super-critical carbon dioxide environment

    Surface and Coatings Technology
    Chaewon Kim, Sung Hwan Kim, Ji-Hwan Cha, Changheui Jang, Tae Kyu Kim
    LINK
  • 299
    2020

    Corrosion behaviors of four stainless steels with similar chromium content in supercritical carbon dioxide environment at 650 C

    Corrosion Science
    Hongsheng Chen, Sung Hwan Kim, Chaewon Kim, Junjie Chen, Changheui Jang
    LINK
  • 298
    2020

    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 Conference
    Hyeon Bae Lee, Ho-Sub Kim, Junjie Chen, Changheui Jang, Tae Soon Kim, Gary L Stevens, Kawaljit Ahluwalia
    LINK
  • 297
    2020

    Investigation on the thermal butt fusion performance of the buried high density polyethylene piping in nuclear power plant

    Nuclear Engineering and Technology
    Jong-Sung Kim, Young-Jin Oh, Sun-Woong Choi, Changheui Jang
    LINK
  • 296
    2020

    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 Shin
    LINK
  • 295
    2020

    Effects of heat treatment on mechanical properties and sensitization behavior of materials in dissimilar metal weld

    International Journal of Pressure Vessels and Piping
    Ho-Sub Kim, Jiho Shin, Byeong Seo Kong, Sunghoon Hong, Seungjin Oh, Jong-Dae Hong, Changheui Jang, Sanghoon Lee
    LINK
  • 294
    2020

    Effect of zinc on the environmentally-assisted fatigue behavior of 316 stainless steels in simulated PWR primary environment

    Corrosion Science
    Ho-Sub Kim, Hyeon Bae Lee, Junjie Chen, Changheui Jang, Tae Soon Kim, Gary L Stevens, Kawaljit Ahluwalia
    LINK
  • 293
    2020

    The corrosion behaviour of alloy 690 tube in simulated PWR secondary water with the effect of solid diffusing hydrogen

    Journal of Nuclear Materials
    Junjie Chen, Zhanpeng Lu, Fanjiang Meng, Xuelian Xu, Qian Xiao, Ho-Sub Kim, Changheui Jang
    LINK
  • 292
    2020

    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 Technology
    Junjie Chen, Andrieanto Nurrochman, Jong-Dae Hong, Tae Soon Kim, Changheui Jang, Yongsun Yi
    LINK
  • 291
    2020

    Advancement of Supercritical Carbon Dioxide Technology through Round Robin Testing and Fundamental Modeling

    OSTI.GOV
    Julie Tucker, Líney Árnadóttir, Mark Anderson, Bruce Pint, Ömer Doğan, Henry Saari, Changheui Jang, Steven Kung
    LINK
  • 290
    2020

    Development and Mechanical Characterization of Nuclear Accident Tolerant Duplex Stainless Steel (ADSS)

    TMS Annual Meeting
    Hyeonsu Do, Hyunmyung Kim, Changheui Jang, Dongchan Jang
    LINK
  • 289
    2020

    Integrity of Alumina Catalytic Support Prepared by Anodization in a High Temperature Steam Environment

    Metals and Materials International
    Chaewon Kim, Sung Hwan Kim, Gokul Obulan Subramanian, Changheui Jang, Keun Man Park
    LINK
  • 288
    2020

    400° C aging embrittlement of FeCrAl alloys: Microstructure and fracture behavior

    Materials Science and Engineering: A
    Hyunmyung Kim, Gokul Obulan Subramanian, Chaewon Kim, Hun Jang, Changheui Jang
    LINK
  • 287
    2020

    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 Reactors
    Thak Sang Byun, Timothy G Lach, Ying Yang, Changheui Jang
    LINK
  • 286
    2020

    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 Reactors
    Gokul Obulan Subramanian, Sunghoon Hong, Ho Jung Lee, Byeong Seo Kong, Kyoung-Soo Lee, Thak Sang Byun, Changheui Jang
    LINK
  • 285
    2019

    Oxidation behavior of high-strength FeCrAl alloys in a high-temperature supercritical carbon dioxide environment

    Progress in Natural Science: Materials International
    Hongsheng Chen, Sung Hwan Kim, Chongsheng Long, Chaewon Kim, Changheui Jang
    LINK
  • 284
    2019

    Oxidation behavior of Fe-20Cr-25Ni-Nb austenitic stainless steel in high-temperature environment with small amount of water vapor

    Corrosion Science
    Hongsheng Chen, Haibo Wang, Qingzhu Sun, Chongsheng Long, Tianguo Wei, Sung Hwan Kim, Junjie Chen, Chaewon Kim, Changheui Jang
    LINK
  • 283
    2019

    Evaluation of the thermal ageing of austenitic stainless steel welds with 10% of δ-ferrites

    International Journal of Pressure Vessels and Piping
    Sunghoon Hong, Hyunmyung Kim, Byeong Seo Kong, Changheui Jang, In Hwan Shin, Jun-Seog Yang, Kyoung-Soo Lee
    LINK
  • 282
    2019

    Evaluation of the thermal aging of δ-ferrite in austenitic stainless steel welds by electrochemical analysis

    Scientific reports
    Gokul Obulan Subramanian, Byeong Seo Kong, Ho Jung Lee, Changheui Jang
    LINK
  • 281
    2019

    Evaluation of thermal aging of δ-ferrite in austenitic stainless steel weld using nanopillar compression test

    Scripta Materialia
    Ho Jung Lee, Byeong Seo Kong, Gokul Obulan Subramanian, Jaewon Heo, Changheui Jang, Kyoung-Soo Lee
    LINK
  • 280
    2019

    Surface modification of austenitic stainless steel for corrosion resistance in high temperature supercritical-carbon dioxide environment

    Surface and Coatings Technology
    Sung Hwan Kim, Gokul Obulan Subramanian, Chaewon Kim, Changheui Jang, Keun Man Park
    LINK
  • 279
    2019

    Development of alumina-forming duplex stainless steels as accident-tolerant fuel cladding materials for light water reactors

    Journal of Nuclear Materials
    Hyunmyung Kim, Hun Jang, Gokul Obulan Subramanian, Chaewon Kim, Changheui Jang
    LINK
  • 278
    2019

    Corrosion and Carburization Behaviour of Ni-xCr Binary Alloys in a High-Temperature Supercritical-Carbon Dioxide Environment

    Oxidation of Metals
    Gokul Obulan Subramanian, Ho Jung Lee, Sung Hwan Kim, Changheui Jang
    LINK
  • 277
    2019

    Supercritical CO2 Round Robin Test Program.

    International Supercritical CO2 Power Cycles Symposium
    Jacob Thomas Mahaffey, Julie D Tucker, Henry Saari, Benjamin Adam, Lucas Teeter, Mark Anderson, Bruce Pint, Omer Dogan, Gordon R Holcomb, Changheui Jang, Casey S Carney, Steven Kung
    LINK
  • 276
    2019

    Diffusion bonding of a cold-worked Ni-base superalloy

    Pressure Technology
    Sung Hwan Kim, Chaewon Kim, Changheui Jang
    LINK
  • 275
    2019

    Characterization of Alloy 600 joints exposed to a high-temperature supercritical-carbon dioxide environment

    Materials Characterization
    Ho Jung Lee, Sung Hwan Kim, Changheui Jang
    LINK
  • 274
    2019

    Evaluation of Primary Water Stress Corrosion Cracking Resistance of Three Heats of Alloy 600 in 400° C Hydrogenated Steam Condition

    Metals
    Eunsub Yun, Hansub Chung, Changheui Jang
    LINK
  • 273
    2019

    Corrosion and Carburization Behaviour of Ni-Cr-Mo-Nb Superalloys in a High Temperature Supercritical-CO2 Environment

    Proceedings of the 9th International Symposium on Superalloy 718 & Derivatives: Energy, Aerospace, and Industrial Applications
    Sung Hwan Kim, Chaewon Kim, Gokul Obulan Subramanian, Changheui Jang
    LINK
  • 272
    2019

    Supercritical CO2 round robin test program

    The 6th International Supercritical CO2 Power Cycles Symposium
    Julie D Tucker, Benjamin Adam, Mark Anderson, Bruce Pint, Gordon R Holcomb, CS Carney, H Saari, L Teeter, J Mahaffey, O Dogan, C Jang, S Kung
    LINK
  • 271
    2018

    Effects of post weld heat treatment on mechanical properties and sensitization behaviour in heat affected zone of dissimilar metal weld in nuclear power plant

    Transactions, SMiRT-24
    Ho-Sub Kim, WY Joo, Myeong-Gyu Seo, CH Jang, SJ Oh
    LINK
  • 270
    2018

    Influence of microstructure on hydrothermal corrosion of chemically vapor processed SiC composite tubes

    Journal of Nuclear Materials
    Daejong Kim, Ho Jung Lee, Changheui Jang, Hyeon-Geun Lee, Ji Yeon Park, Weon-Ju Kim
    LINK
  • 269
    2018

    Investigation of the electrical conductivity of sintered monoclinic zirconia (ZrO2)

    Ceramics International
    Oh Hyun Kwon, Changheui Jang, Junho Lee, Hu Young Jeong, Young-il Kwon, Jong Hoon Joo, Hongjin Kim
    LINK
  • 268
    2018

    Environmental Fatigue Behaviors of Austenitic Stainless Steels in the Primary Water Environment of Nuclear Power Plants

    Transactions of the Korean Society of Pressure Vessels and Piping
    Hyeon Bae Lee, Ho-Sub Kim, Taesoon Kim, Changheui Jang
    LINK
  • 267
    2018

    Evaluation of Mechanical Properties and Microstructure of Thermally Aged 308 and 316L Stainless Steel Welds

    Transactions of the Korean Society of Pressure Vessels and Piping
    Byeong Seo Kong, Sunghoon Hong, Changheui Jang, Maan-Won Kim
    LINK
  • 266
    2017

    Corrosion and carburization behavior of Al-rich surface layer on Ni-base alloy in supercritical-carbon dioxide environment

    Applied Surface Science
    Ho Jung Lee, Sung Hwan Kim, Hyunmyung Kim, Changheui Jang
    LINK
  • 265
    2017

    Low cycle fatigue behavior of hot-bent 347 stainless steel in a simulated PWR water environment

    Journal of Mechanical Science and Technology
    Junho Lee, Myung-Gyu Seo, Jong-Dae Hong, Tae Soon Kim, Changheui Jang
    LINK
  • 264
    2017

    Microstructure and creep resistance of a diffusionally aluminized Ni-base superalloy

    Metals and Materials International
    Injin Sah, Sung Hwan Kim, Changheui Jang
    LINK
  • 263
    2017

    Plasma thermal performance of a dual-process PVD/PS tungsten coating on carbon-based panels for nuclear fusion application

    Fusion Engineering and Design
    Hyunmyung Kim, Ho Jung Lee, Sung Hwan Kim, Changheui Jang
    LINK
  • 262
    2017

    Performance of a dual-process PVD/PS tungsten coating structure under deuterium ion irradiation

    Fusion Engineering and Design
    Hyunmyung Kim, Ho Jung Lee, Sung Hwan Kim, Jae-Min Song, Changheui Jang
    LINK
  • 261
    2017

    Fatigue Life of Stainless Steel in PWR Environments with Strain Holding

    Transactions of the Korean Nuclear Society Autumn Meeting
    Myeonggyu Seo, Changheui Jang
    LINK
  • 260
    2017

    Creep behavior of Alloy 617 in high temperature air and helium environments–effect of oxidation damage

    Journal of Mechanical Science and Technology
    Changheui Jang, Sung Hwan Kim, Injin Sah, Daejong Kim
    LINK
  • 259
    2017

    Passivity breakdown of 316L stainless steel during potentiodynamic polarization in NaCl solution

    Corrosion Science
    Sara Al Saadi, Yongsun Yi, Pyungyeon Cho, Changheui Jang, Philip Beeley
    LINK
  • 258
    2017

    Effect of pressure on the corrosion and carburization behavior of chromia-forming heat-resistant alloys in high-temperature carbon dioxide environments

    Corrosion Science
    Ho Jung Lee, Gokul Obulan Subramanian, Sung Hwan Kim, Changheui Jang
    LINK
  • 257
    2017

    Effect of thermal ageing on mechanical properties of a high-strength ODS alloy

    Journal of Mechanical Science and Technology
    Sunghoon Hong, Sung Hwan Kim, Tae Kyu Kim, Changheui Jang
    LINK
  • 256
    2017

    Intergranular oxidation of Ni-based Alloy 600 in a simulated PWR primary water environment

    Corrosion Science
    Yun Soo Lim, Sung Woo Kim, Seong Sik Hwang, Hong Pyo Kim, Changheui Jang
    LINK
  • 255
    2017

    Oxidation Behavior of Surface-modified Stainless Steel 316LN in Supercritical-CO2 Environment

    Transactions of the Korean Nuclear Society Spring Meeting
    Sung Hwan Kim, Jin Woo Heo, Hyunmyung Kim, Changheui Jang
    LINK
  • 254
    2017

    Effect of Matrix Grain Size on the Oxidation and Carburization Resistance of Alloy 800HT in High Temperature CO_2 Environment

    Transactions of the Korean Nuclear Society Spring Meeting
    Gokul Obulan Subramanian, Ho Jung Lee, Ji Ho Shin, Changheui Jang
    LINK
  • 253
    2017

    Mechanical factors in primary water stress corrosion cracking of cold-worked stainless steel

    Nuclear Engineering and Design
    Rashid Al Hammadi, Yongsun Yi, Wael Zaki, Pyungyeon Cho, Changheui Jang
    LINK
  • 252
    2017

    Effects of mixed strain rates on low cycle fatigue behaviors of austenitic stainless steels in a simulated PWR environment

    International Journal of Fatigue
    Jong-Dae Hong, Changheui Jang, Tae Soon Kim
    LINK
  • 251
    2016

    Microstructural, Micro-hardness and Sensitization Evaluation in HAZ of Type 316L Stainless Steel Joint with Narrow Gap Welds

    Transactions of the Korean Nuclear Society Autumn Meeting
    Faisal Shafiqul Islama, Suk-Chull Kangb, Changheui Janga
    LINK
  • 250
    2016

    A comparison of PFM codes for analyzing structural reliability of components

    Transactions of the Korean Nuclear Society Autumn Meeting
    Md Nasimul Goni, Seung Hyun Kim, Yoon-Suk Chang, Changheui Jang
    LINK
  • 249
    2016

    Corrosion and carburization behavior of chromia-forming heat resistant alloys in a high-temperature supercritical-carbon dioxide environment

    Corrosion Science
    Ho Jung Lee, Hyunmyung Kim, Sung Hwan Kim, Changheui Jang
    LINK
  • 248
    2016

    Thermal performance of multilayer PVD tungsten coating for the first wall application in nuclear fusion devices

    Fusion Science and Technology
    Hyunmyung Kim, Ho Jung Lee, Changheui Jang
    LINK
  • 247
    2016

    Microstructure evolution of a Ni–Cr–W superalloy during long-term aging at high temperatures

    Materials Characterization
    Ho Jung Lee, Hyunmyung Kim, Donghoon Kim, Changheui Jang
    LINK
  • 246
    2016

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

    Corrosion Science
    Jian Xu, Tetsuo Shoji, Changheui Jang
    LINK
  • 245
    2016

    Evaluation of the recovery of thermal aging embrittlement of CF8M cast stainless steels after reversion heat treatments

    International Journal of Pressure Vessels and Piping
    Changheui Jang, Hun Jang, Sunghoon Hong, Jae Gon Lee
    LINK
  • 244
    2016

    The hold-time effects on the low cycle fatigue behaviors of 316 SS in PWR primary environment

    IAEA | 50 years of INIS
    Junho Lee, Jong-Dae Hong, Myung-Gyu Seo, Changheui Jang
    LINK
  • 243
    2016

    In-situ oxide layer analysis of alloy 182 using electrochemical impedance spectroscopy in high dissolved hydrogen condition in PWR environment

    IAEA | 50 years of INIS
    Ho-Sub Kim, Gokul Obulan Subramanian, Jong-Dae Hong, Junho Lee, Changheui Jang
    LINK
  • 242
    2016

    The Effects of CO 2 Pressure on Corrosion and Carburization Behaviors of Chromia-forming Austenitic Alloys

    IAEA | 50 years of INIS
    Ho Jung Lee, Sung Hwan Kim, Changheui Jang
    LINK
  • 241
    2016

    Mechanical Properties of Thermally Aged Austenitic Stainless Steel Welds and Cast Austenitic Stainless Steel

    Transactions of the Korean Nuclear Society Spring Meeting
    Sunghoon Honga, Myeong-Gyu Seoa, Changheui Janga, Kyoung Soo Leeb
    LINK
  • 240
    2016

    Creep-rupture Behaviors of a Diffusionally Aluminized Alloy 617

    Transactions of the Korean Nuclear Society Spring Meeting
    Injin Sah, Sung Hwan Kimb, Changheui Jang
    LINK
  • 239
    2016

    Critical conditions for pit initiation and growth of austenitic stainless steels

    Corrosion Science
    M Al Ameri, Y Yi, P Cho, S Al Saadi, C Jang, P Beeley
    LINK
  • 238
    2016

    Development of a Short-term Failure Assessment of High Density Polyethylene Pipe Welds-Application of the Limit Load Analysis

    Transactions of the Korean Society of Mechanical Engineers A
    Ho-Wan Ryu, Jae-Jun Han, Yun-Jae Kim, Jong-Sung Kim, Jeong-Hyeon Kim, Chang-Heui Jang
    LINK
  • 237
    2016

    Complex Leakage Probability Evaluation of Nuclear Pipes by Fatigue and Stress Corrosion Cracking

    Transactions of the Korean Society of Pressure Vessels and Piping
    Seung Hyun Kim, Nasimul Goni, Yoon-Suk Chang, Changheui Jang
    LINK
  • 236
    2016

    Effects of the Heat Treatment on the Microstructure and Mechanical Properties of the Diffusion-Bonded Ferritic/Martensitic Steel

    Transactions of the Korean Society of Pressure Vessels and Piping
    Injin Sah, Sunghwan Kim, Sunghoon Hong, Changheui Jang
    LINK
  • 235
    2016

    Evaluation of the effects of thermal aging of austenitic stainless steel welds using small punch test

    Procedia Engineering
    SH Hong, M-G Seo, CH Jang, K-S Lee
    LINK
  • 234
    2016

    Mechanical properties of Ni-base superalloys in high temperature steam environments

    IAEA | 50 years of INIS
    Changheui Jang, Donghoon Kim, Injin Sah, Ho Jung Lee
    LINK
  • 233
    2016

    The effect of post-bond heat treatment on tensile property of diffusion bonded austenitic alloys

    Transactions of the Korean Society of Mechanical Engineers A
    Sunghoon Hong, Sung Hwan Kim, Changheui Jang, Injin Sah
    LINK
  • 232
    2016

    The influence of cooling rate from annealing temperature on the microstructure of Haynes 230

    IAEA | 50 years of INIS
    Injin Sah, Sunghoon Hong, Changheui Jang
    LINK
  • 231
    2016

    Oxidation characteristics of the electron beam surface-treated Alloy 617 in high temperature helium environments

    Journal of Nuclear Materials
    Ho Jung Lee, Injin Sah, Donghoon Kim, Hyunmyung Kim, Changheui Jang
    LINK
  • 230
    2015

    Oxide characterization for the mechanistic understanding of the initiation behaviors of Alloy 182 weld in various water chemistry conditions

    IAEA | 50 years of INIS
    Jong-Dae Hong, Junho Lee, Ho-Sup Kim, Changheui Jang, Ji Hyun Kim, Yun Soo Lim, Masashi Watanabe, Jian Xu, Tetsuo Shoji
    LINK
  • 229
    2015

    The Effects of Hot Bending on the Low Cycle Fatigue Behaviors of 347 SS in PWR Primary Environment

    IAEA | 50 years of INIS
    Ho-Sub Kim, Jong-Dae Hong, Junho Lee, Changheui Jang
    LINK
  • 228
    2015

    The Effects of Dissolved Hydrogen on PWSCC Initiation Behavior and Oxide Characteristics of Alloy 182 Weld

    IAEA | 50 years of INIS
    Jong-Dae Hong, Ho-Sub Kim, Junho Lee, Myeong-Gyu Seo, Changheui Jang
    LINK
  • 227
    2015

    The Influence of Post Weld Heat Treatment in Alloy 82/182 Dissimilar Metal Weld between Low Alloy Steel and 316L Stainless Steel

    IAEA | 50 years of INIS
    Sunghoon Hong, Jong-Dae Hong, Changheui Jang, Kyoung Soo Lee
    LINK
  • 226
    2015

    Corrosion resistances of alloys in high temperature hydrogen iodide gas environment for sulfur–iodine thermochemical cycle

    International journal of hydrogen energy
    Jin Young Choi, Young Soo Kim, Injin Sah, Hee Cheon No, Changheui Jang
    LINK
  • 225
    2015

    Compatibility of candidate structural materials in high-temperature S-CO2 environment

    4th International Symposium-Supercritical CO2 Power Cycles, Pittsburgh, PA
    Ho Jung Lee, Hyunmyung Kim, Changheui Jang
    LINK
  • 224
    2015

    Low cycle fatigue behavior of alloy 690 in simulated PWR water—Effects of dynamic strain aging and hydrogen

    Materials Science and Engineering: A
    Jong-Dae Hong, Junho Lee, Changheui Jang, Tae Soon Kim
    LINK
  • 223
    2015

    DP780 을 적용한 리어 시트 등받이 프레임 개발

    한국자동차공학회 춘계학술대회
    정경근, 김동옥, 장창희, 이승은
    LINK
  • 222
    2015

    Solid-state Diffusion Bonding of Candidate Fe-base and Ni-base Alloys for the Application of S-CO 2 Cycle Heat Exchanger

    IAEA | 50 years of INIS
    Injin Sah, Sunghoon Hong, Changheui Jang
    LINK
  • 221
    2015

    Carbide Transformation in Haynes 230 during Long-term Exposure at High Temperature

    IAEA | 50 years of INIS
    Ho Jung Lee, Hyunmyung Kim, Sunghoon Hong, Changheui Jang
    LINK
  • 220
    2015

    Development of an aluminide coating layer on Alloy 617 by Al sputtering and inter-diffusion heat treatments

    Surface and Coatings Technology
    Donghoon Kim, Injin Sah, Ho Jung Lee, Sunghoon Hong, Changheui Jang
    LINK
  • 219
    2015

    The effects of reversion heat treatment on the recovery of thermal aging embrittlement of CF8M cast stainless steels

    Materials & Design (1980-2015)
    Hun Jang, Sunghoon Hong, Changheui Jang, Jae Gon Lee
    LINK
  • 218
    2015

    Evaluation of High-Temperature Tensile Property of Diffusion Bond of Austenitic Alloys for S-CO2 Cycle Heat Exchangers

    Transactions of the Korean Society of Mechanical Engineers A
    Sunghoon Hong, Injin Sah, Changheui Jang
    LINK
  • 217
    2015

    Environmental Fatigue Behaviors of CF8M Stainless Steel in 310℃ Deoxygenated Water-Effects of Hydrogen and Microstructure

    Transactions of the Korean Society of Mechanical Engineers A
    Hun Jang, Pyungyeon Cho, Changheui Jang, Tae Soon Kim
    LINK
  • 216
    2014

    Development and oxidation resistance evaluation of Al-rich surface layer on Alloy 617

    Surface and Coatings Technology
    Injin Sah, Donghoon Kim, Ho Jung Lee, Changheui Jang
    LINK
  • 215
    2014

    Environmental fatigue of metallic materials in nuclear power plants–a review of Korean test programs

    Nuclear Engineering and Technology
    Changheui Jang, Hun Jang, Jong-Dae Hong, Hyunchul Cho, Tae Soon Kim, Jae-Gon Lee
    LINK
  • 214
    2014

    Study on Alloy 600/690 oxide layer characteristic with Dissolved Hydrogen Concentration Variation and Zinc Injection

    2013 ISRSM
    Eun-Sub Yun, Sung-Ho Lee, Jae-Gon Lee, Jong-Il Yun, Changheui Jang
    LINK
  • 213
    2014

    Mechanical Properties of the Diffusion-bonded Ni-and Fe-base Alloys

    MST 2013 Conference and Exhibition
    Injin Sah, Sunghoon Hong, Changheui Jang
    LINK
  • 212
    2014

    Corrosion characteristics of Ni-base superalloys in high temperature steam with and without hydrogen

    Journal of nuclear materials
    Donghoon Kim, Daejong Kim, Ho Jung Lee, Changheui Jang, Duk Joo Yoon
    LINK
  • 211
    2014

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

    Materials Science and Engineering: A
    Hun Jang, Jeong-Hyeon Kim, Changheui Jang, Jae Gon Lee, Tae Soon Kim
    LINK
  • 210
    2014

    Effect of strain hardened microstructures on the electrochemical behaviour of 316L stainless steel

    EUROCORR 2013
    Ahmed Al Zaabi, Yongsun Yi, Pyungyeon Cho, Changheui Jang
    LINK
  • 209
    2014

    Role of Mechanical Factors in PWSCC of Stainless Steel

    EUROCORR 2013
    Pyungyeon Cho, Yongsun Yi, Wael Zaki, Changheui Jang
    LINK
  • 208
    2014

    Evaluation of the sensitization of 316L stainless steels after the post weld heat treatment

    IAEA | 50 years of INIS
    Changheui Jang, Hun Jang
    LINK
  • 207
    2014

    Potentiodynamic polarization behaviour of AISI type 316 stainless steel in NaCl solution

    Corrosion Science
    Y Yi, P Cho, A Al Zaabi, Y Addad, Changheui Jang
    LINK
  • 206
    2014

    Low Cycle Fatigue Behaviors of Alloy 690 and 52M in PWR Primary Water Condition

    16th EDM
    Changheui Jang, Jong-Dae Hong, Tae Soon Kim, Yong Sung Lee
    LINK
  • 205
    2014

    Environmentally Assisted Fatigue of Alloy 690/52M in PWR Environments

    2013 EPRI EAF Workshop
    Tae Soon Kim, Jong-Dae Hong, Changheui Jang
    LINK
  • 204
    2014

    Hydrogen effects on oxidation behaviors of Haynes 230 in high temperature steam environments

    Solid State Ionics
    Donghoon Kim, Injin Sah, Ho Jung Lee, Changheui Jang
    LINK
  • 203
    2014

    Environmental fatigue behaviors of Ni-base alloys in PWR primary water environments

    2013 ICG-EAC
    Jong-Dae Hong, Tae Soon Kim, Yong Sung Lee, Changheui Jang
    LINK
  • 202
    2014

    Mechanical Property Characteristics of Butt-Fusion Joint of High Density Polyethylene Pipe for NPP Safety Class Application

    IAEA | 50 years of INIS
    Youngjin Oh, Kyoungsu Kim, Seunggun Lee, Heungbae Park, Jeongho Yu, Jongsung Kim, Jeonghyun Kim, Changheui Jang, Sunwoong Choi
    LINK
  • 201
    2014

    Effect of Ferrite Morphology on Sensitization of 316L Austenitic Stainless Steels

    IAEA | 50 years of INIS
    Hun Jang, Jun Ho Lee, Changheui Jang
    LINK
  • 200
    2014

    Microstructural characteristics and mechanical properties of a mechanically alloyed 15Cr ODS ferritic steel

    IAEA | 50 years of INIS
    Injin Sah, Changheui Jang, Tae Kyu Kim, Sanghoon Noh
    LINK
  • 199
    2014

    Low cycle fatigue of Alloy 690 and welds in a simulated PWR primary water environment

    IAEA | 50 years of INIS
    Jongdae Hong, Pyungyeon Cho, Changheui Jang, Tae Soon Kim, Yong Sung Lee
    LINK
  • 198
    2014

    Long-Term Aging Effects on Microstructure and Tensile Properties of Ni-base Superalloys

    IAEA | 50 years of INIS
    Ho Jung Lee, Dong Hoon Kim, Hyun Myung Kim, Chang Heui Jang
    LINK
  • 197
    2014

    The recovery of tensile ductility in diffusion-bonded Ni-base alloys by post-bond heat treatments

    Materials & Design
    Injin Sah, Donghoon Kim, Ho Jung Lee, Changheui Jang
    LINK
  • 196
    2014

    Korean Status Of Environmental Fatigue Tests Of Structural Materials In A Simulated Primary Coolant System Water

    Proceedings of ICAPP 2013
    Changheui Jang, Hun Jang, Jong-Dae Hong, Tae Soon Kim
    LINK
  • 195
    2014

    Correlation of metallurgical analysis & higher harmonic ultrasound response for long term isothermally aged and crept FM steel for USC TPP turbine rotors

    NDT & E International
    Jaeseok Park, Minsu Kim, Byungha Chi, Changheui Jang
    LINK
  • 194
    2014

    Corrosion resistance of surface treated Alloy 617 in high temperature HI and H2SO4 environments

    MRS Online Proceedings Library Archive
    Donghoon Kim, Injin Sah, Jin Young Choi, Young Soo Kim, Hee Cheon No, Changheui Jang
    LINK
  • 193
    2013

    PFM application for the PWSCC integrity of Ni-base alloy welds—Development and application of PINEP-PWSCC

    Nucl. Eng. Technol
    Jong-Dae Hong, Changheui Jang, Tae Soon Kim
    LINK
  • 192
    2013

    Corrosion Resistance of Surface treated Alloy 617 in High Temperature HI and H2SO4 Environments

    Materials Research Society
    Changheui Jang, Injin Sah, Jin Young Choi, Young Soo Kim, Hee Cheon No
    LINK
  • 191
    2013

    Diffusion bonding of Ni-base superalloys for the application of VHTR intermediate heat exchanger

    International Welding Joining Conference-Korea 2012
    Changheui Jang, Injin Sah, Donghoon Kim
    LINK
  • 190
    2013

    Corrosion Resistance of Materials at High Temperature Under Gas Phase of Sulfuric Acid for IS Cycle

    Transactions
    Young Soo Kim, Jin Young Choi, In Jin Sah, Hee Cheon No, Chang Heui Jang
    LINK
  • 189
    2013

    Creep Behaviors of Alloy 617 in High Temperature Steam Environments

    NFSM 2012
    Changheui Jang, Donghoon Kim, Injin Sah, Jahyun Koo
    LINK
  • 188
    2013

    Effects Al Contents in the Surface Micro-Alloying Region on the High Temperature Oxidation Behaviors of Alloy 617

    NFSM 2012
    Changheui Jang, Ho Jung Lee, Donghoon Kim, Injin Sah
    LINK
  • 187
    2013

    Effects Al Contents in the Surface Micro-Alloying Region on the High Temperature Oxidation Behaviors of Alloy 617

    Transactions
    Ho Jung Lee, Injin Sah, Donghoon Kim, Changheui Jang
    LINK
  • 186
    2013

    Creep Behaviors of Alloy 617 in High Temperature Steam Environments

    Transactions
    Donghoon Kim, Injin Sah, Jahyun Koo, Changheui Jang
    LINK
  • 185
    2013

    Creep resistance of Alloy 617 in high temperature helium environments

    Asia Pacific Conference on Fracture Strength-Machanical and materials 2012
    Changheui Jang, Ho Jung Lee, Injin Sah, Jahyun Koo, Dae Jong Kim
    LINK
  • 184
    2013

    Diffusion Bonding of Ni-base Superalloys for the Application of VHTR Intermediate Heat Exchanger

    대한용접학회 특별강연 및 학술발표대회 개요집
    Injin Sah, Donghoon Kim, Changheui Jang
    LINK
  • 183
    2013

    Metal corrosion resistances in high temperature hydriodic acid gas environment for SI cycle

    2012 ANS Winter Meeting
    Hee Cheon No, Choi Jin Young, Kim Young Soo, In Jin Sah
    LINK
  • 182
    2013

    Fatigue crack growth behaviors of SA508 Gr. 3 Cl. 2 base and weld material in 290℃ water environment

    Corrosion Science and Technology
    Pyungyeon Cho, Jeong Hyeon Kim, Changheui Jang, Hyunchul Cho
    LINK
  • 181
    2013

    Analysis of oxidation behavior of Ni-base superalloys by laser-induced breakdown spectroscopy

    Journal of Analytical Atomic Spectrometry
    Tae-Hyeong Kim, Dong-Hyoung Lee, Donghoon Kim, Changheui Jang, Jong-Il Yun
    LINK
  • 180
    2012

    Corrosion resistance of materials at high temperature under gas phase of sulfuric acid for IS cycle

    2012 American Nuclear Society Winter Meetings
    Changheui Jang, Young Soo Kim, Jin Young Choi, In Jin Sah, Hee Cheon No
    LINK
  • 179
    2012

    Metal corrosion resistances in high temperature hydriodic aicd gas environment for SI cycle

    2012 American Nuclear Society Winter Meetings
    Changheui Jang, Jin Young Choi, Young Soo Kim, In Jin Sah, Hee Cheon No
    LINK
  • 178
    2012

    Oxidation behaviors of wrought nickel-based superalloys in various high temperature environments

    Transactions of nonferrous metals society of China
    JANG Changheui, KIM Daejong, KIM Donghoon, SAH Injin, RYU Woo-Seog, Young-sung Yoo
    LINK
  • 177
    2012

    Diametral creep prediction of the pressure tubes in CANDU reactors using a bundle position-wise linear model

    Nuclear Engineering and Technology
    Sung-Han Lee, Dong-Su Kim, Sim-Won Lee, Young-Gyu No, Man-Gyun Na, Jae-Yong Lee, Donghoon Kim, Changheui Jang
    LINK
  • 176
    2012

    High temperature oxidation characteristics of surface treated by alloy 617 by Al sputtering and inter-diffusion heat treatment

    IAEA | 50 years of INIS
    Donghoon Kim, Jahyun Koo, Injin Sah, Changheui Jang
    LINK
  • 175
    2012

    Evaluation of Accelerated Graphitic Corrosion Test of Gray Cast Iron

    IAEA | 50 years of INIS
    Jeong Hyeon Kim, Jong Dae Hong, Heui Chang, Kyung Hwan Na, Jae Gon Lee
    LINK
  • 174
    2012

    Oxidation behaviors of Ni-base Superalloys for Nuclear Hydrogen production in Steam with and without Hydrogen Environments

    IAEA | 50 years of INIS
    Dong Hoon Kim, Ja Hyun Koo, Chang Heui Jang, Dae Jong Kim, Young Sung Yoo
    LINK
  • 173
    2012

    Fatigue Crack Growth Rate and Fracture Resistance of Heat Affected Zone of Stainless Steel Narrow Gap Welds

    Transactions of the Korean Nuclear Society Spring Meeting
    HoJung Leea, Changheui Janga, Sun-Young Chob, Jun-Seog Yangc
    LINK
  • 172
    2012

    Creep Properties of Alloy 617 at 900. deg. C in Helium Environments with Various Oxygen Concentrations

    IAEA | 50 years of INIS
    Ja Hyun Koo, Dong Hoon Kim, In Jin Sah, Chang Heui Jang
    LINK
  • 171
    2012

    Application of Electron Beams for Surface Modification of Nickel-base Superalloys

    IAEA | 50 years of INIS
    In Jin Sah, Dong Hoon Kim, Ja Hyun Koo, Chang Heui Jang
    LINK
  • 170
    2012

    Combined Effect of Hydrogen and Dynamic Strain Aging on Low Cycle Fatigue Behaviors of SA508 Gr. 1a Low Alloy Steels in 310. deg. C Deoxygenated Water

    IAEA | 50 years of INIS
    Hun Jang, Jeong Hyeon Kim, Chang Heui Jang, Tae Soon Kim
    LINK
  • 169
    2012

    Microstructure and hydride embrittlement of zirconium model alloys containing niobium and tin

    Materials Science and Engineering: A
    Seung Jin Oh, Changheui Jang, Jun Hwan Kim, Yong Hwan Jeong
    LINK
  • 168
    2012

    High temperature oxidation behavior of alloy 617 and Haynes 230 in impurity-controlled helium environments

    Oxidation of metals
    Daejong Kim, Injin Sah, Donghoon Kim, Woo-Seog Ryu, Changheui Jang
    LINK
  • 167
    2012

    Effects of aging in high temperature helium environments on room temperature tensile properties of nickel-base superalloys

    Materials Science and Engineering: A
    Daejong Kim, Injin Sah, Changheui Jang
    LINK
  • 166
    2012

    Oxidation Behaviors of Nickel-Base Superalloys in High Temperature Steam Environments

    Transactions of the Korean Society of Pressure Vessels and Piping
    Donghoon Kim, Jahyun Koo, Daejong Kim, Young-Sung Yoo, Changheui Jang
    LINK
  • 165
    2012

    Creep and Oxidation Behaviors of Alloy 617 in High Temperature Helium Environments with Various Oxygen Concentrations

    Transactions of the Korean Society of Pressure Vessels and Piping
    Jahyun Koo, Daejong Kim, Changheui Jang
    LINK
  • 164
    2012

    Environmental fatigue behaviors of wrought and cast stainless steels in 310. deg. C Deoxygenated Water

    IAEA | 50 years of INIS
    Pyung Yeon Cho
    LINK
  • 163
    2012

    Fatigue Crack Growth Rate and Fracture Resistance of Heat Affected Zone of Type 316L Stainless Steel with Narrow Gap Welds

    Pressure Vessels and Piping Conference
    Ho-Jung Lee, Minu Kim, Changheui Jang, Sun-Young Cho, Jun-Seog Yang
    LINK
  • 162
    2012

    镍基变形高温合金在高温环境下的氧化行为 (英文)

    Transactions of Nonferrous Metals Society of China
    Changheui JANG, Daejong KIM, Donghoon KIM, Injin SAH, Woo-Seog RYU, Young-sung YOO
    LINK
  • 161
    2011

    An Assessment of the Integrity of the PWR Vessels An Assessment of the Integrity of the PWR Vessels, 1982

    Journal of nuclear science and technology
    Myung Jo Jhung, Seok Hun Kim, Young Hwan Choi, Yoon Suk CHANG, Xiangyuan XU, Jong Min KIM, Jong Wook KIM, Changheui JANG
    LINK
  • 160
    2011

    Stress Intensity Factors for Circumferential Surface Cracks in Pipes and Rods under Tension and Bending Loads

    Journal of nuclear science and technology
    Myung Jo Jhung, Seok Hun Kim, Young Hwan Choi, Yoon Suk CHANG, Xiangyuan XU, Jong Min KIM, Jong Wook KIM, Changheui JANG
    LINK
  • 159
    2011

    Boiler and Pressure Vessel Code Boiler and Pressure Vessel Code Section XI, 2004

    Journal of nuclear science and technology
    Myung Jo Jhung, Seok Hun Kim, Young Hwan Choi, Yoon Suk CHANG, Xiangyuan XU, Jong Min KIM, Jong Wook KIM, Changheui JANG
    LINK
  • 158
    2011

    VISA-II : A Computer Code for Predicting the Probability of Reactor Vessel Failure

    Journal of nuclear science and technology
    Myung Jo Jhung, Seok Hun Kim, Young Hwan Choi, Yoon Suk CHANG, Xiangyuan XU, Jong Min KIM, Jong Wook KIM, Changheui JANG
    LINK
  • 157
    2011

    Documentation of Probabilistic Fracture Mechanics Codes Used for Reactor Pressure Vessels Subjected to Pressurized Thermal Shock Loading

    Journal of nuclear science and technology
    Myung Jo Jhung, Seok Hun Kim, Young Hwan Choi, Yoon Suk CHANG, Xiangyuan XU, Jong Min KIM, Jong Wook KIM, Changheui JANG
    LINK
  • 156
    2011

    Probabilistic fracture mechanics round robin analysis of reactor pressure vessels during pressurized thermal shock

    Journal of nuclear science and technology
    Myung Jo Jhung, Seok Hun Kim, Young Hwan Choi, Yoon Suk Chang, Xiangyuan Xu, Jong Min Kim, Jong Wook Kim, Changheui Jang
    LINK
  • 155
    2011

    Effects of high temperature aging in an impure helium environment on low temperature embrittlement of Alloy 617 and Haynes 230

    Journal of Nuclear Materials
    Daejong Kim, Injin Sah, Changheui Jang
    LINK
  • 154
    2011

    Effects Of Carburization and Decarburization On The Mechanical Properties Of Nickel-Base Superalloys For VHTR Applications

    Structural Materials for Innovative Nuclear Systems (SMINS-2)
    Daejong Kim, Injin Sah, Changheui Jang
    LINK
  • 153
    2011

    Integrity of Ni-base superalloys for advanced nuclear systems application-environment and materials interaction

    Structural Materials for Innovative Nuclear System (SMINS)-2
    Changheui Jang, D Kim, M Kim, I Sah, WS Ryu, DJ Yoon
    LINK
  • 152
    2011

    Hot Steam Corrosion Characteristics of Ni-Base Superalloys for Intermediate Heat Exchangers of HTSE System

    Transactions
    Donghoon Kim, Daejong Kim, Jahyun Koo, Duk Joo Yoon, Changheui Jang
    LINK
  • 151
    2011

    Diametral creep prediction of pressure tube using statistical regression methods

    31st Annual Conference of the Canadian Nuclear Society and 34th CNS/CNA Student Conference 2010
    D Kim, JY Lee, MG Na, Changheui Jang
    LINK
  • 150
    2011

    Diametral Creep Prediction of the Pressure Tubes in CANDU Reactors Using a Genetic Optimized Linear Model

    IAEA | 50 years of INIS
    Sung Han Lee, Young Gyu No, Man Gyun Na, Jae Yong Lee, Chang Heui Jang, Dong Hoon Kim
    LINK
  • 149
    2011

    Effects of microstructure and residual stress on fatigue crack growth of stainless steel narrow gap welds

    Materials & Design
    Changheui Jang, Pyung-Yeon Cho, Minu Kim, Seung-Jin Oh, Jun-Seog Yang
    LINK
  • 148
    2011

    Effect of Nb on hydride embrittlement of Zr–xNb alloys

    Materials Science and Engineering: A
    Seungjin Oh, Changheui Jang, Jun Hwan Kim, Yong Hwan Jeong
    LINK
  • 147
    2011

    Hot Steam Corrosion Behavior of Ni-based Superalloys at High Temperature Steam Environments

    TMS 2010 Spring Meeting
    Donghoon Kim, Minu Kim, Hyun Min Lee, Daejong Kim, Changheui Jang, Duk-Joo Yoon
    LINK
  • 146
    2011

    Probabilistic fracture mechanics application for Alloy 600 components in PWRs

    IAEA | 50 years of INIS
    Jong-Dae Hong, Changheui Jang
    LINK
  • 145
    2011

    Effects of Crack Measurement Methods on The Determination of Fracture Toughness of IG-110 Isotropic Graphite

    IAEA | 50 years of INIS
    Se Hwan Chi, Dae Jong Kim, Chang Heui Jang
    LINK
  • 144
    2011

    Prediction of the Fundamental Mode Lamb Wave Reflection from a Crack-Like Discontinuity Using Eigen-Mode Expansion

    Journal of the Korean Society for Nondestructive Testing
    Jae-Seok Park, Chang-Heui Jang, Jong-Po Lee
    LINK
  • 143
    2011

    Incorporation of Materials’ Sensitive Simulation Technique Into the PINTIN-CAM Code for Integrity of Nuclear Piping System

    Pressure Vessels and Piping Conference
    Debashis Datta, Changheui Jang
    LINK
  • 142
    2011

    Probabilistic Fracture Mechanics Application for Alloy 82/182 Welds in PWRs

    Pressure Vessels and Piping Conference
    Jong-Dae Hong, Changheui Jang
    LINK
  • 141
    2010

    Effects of the Helium Environment on Degradation of Nickel-Base Superalloys

    U.S. Department of Energy Office of Scientific and Technical Information
    CH Jang, DJ Kim, D Datta, MW Kim, JH Kwon, A Arief, JY Cho
    LINK
  • 140
    2010

    Diametral Creep Prediction of the Pressure Tubes in CANDU Reactors Using Fuzzy Neural Networks

    IAEA | 50 years of INIS
    Sung Han Lee, Young Gyu No, Man Gyun Na, Jae Yong Lee, Chang Heui Jang, Dong Hoon Kim
    LINK
  • 139
    2010

    Effects of Carburization and Decarburization on Mechanical Properties of Nickel-Base Superalloys

    Proceeding of the 12th International Conference on Pressure Vessel Technology
    D Kim, I Sah, Changheui Jang
    LINK
  • 138
    2010

    The effect of material variability on low cycle fatigue resistance of low alloy steels in a 310°C deoxygenated water

    714th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009
    H Jang, J-D Hong, JG Lee, Changheui Jang
    LINK
  • 137
    2010

    Korean PMMD: Approach and Prospect

    Transactions
    Il Soon Hwang, Suk Chull Kang, Jun Hwa Hong, Ho Sang Shin, Changheui Jang, Young Suk Kim
    LINK
  • 136
    2010

    Effect of thermo-mechanical processing on microstructure and creep properties of the foils of alloy 617

    Journal of nuclear materials
    SK Sharma, Changheui Jang, KJ Kang
    LINK
  • 135
    2010

    Oxidation characteristics and oxide layer evolution of alloy 617 and Haynes 230 at 900°C and 1100°C

    Oxidation of Metals
    Daejong Kim, Changheui Jang, Woo Seog Ryu
    LINK
  • 134
    2010

    Diametral Compressive Strength and Elastic Modulus of Flattened Disc using Diametral Compressive Test

    IAEA | 50 years of INIS
    Dong Hoon Kim, Byung Jun Kim, Chang Heui Jang, Se Hwan Chi
    LINK
  • 133
    2010

    Environmental Fatigue Behaviors of Type 316LN Stainless Steels in Simulated PWR Water with Different Dissolved Hydrogen Contents

    IAEA | 50 years of INIS
    Hun Jang, Pyung Yeon Jo, Chang Heui Jang
    LINK
  • 132
    2010

    The Effect of Inspection Model on the Probability of Vessel Failure due to Pressurized Thermal Shock

    IAEA | 50 years of INIS
    Myung Jo Jhung, Young Hwan Choi, Chang Heui Jang
    LINK
  • 131
    2010

    Irradiation hardening and embrittlement in high-Cr oxide dispersion strengthened steels

    Journal of nuclear materials
    S Oh, JS Lee, Changheui Jang, A Kimura
    LINK
  • 130
    2010

    Estimation of Pressure Tube Diametral Creep for CANDU Reactors Using Fuzzy Neural Networks

    6th International Topical Meeting on Nuclear Plant Instrumentation Control and Human Machine Interface Technology
    Changheui Jang
    LINK
  • 129
    2010

    Ancient flood records from historical documents in Korea

    EGUGA
    HJ Kim, SJ Noh, CH Jang
    LINK
  • 128
    2010

    An Assessment of the Integrity of the PWR Vessels, Second report by a study group under the chairmanship of D. W. Marshall

    Journal of nuclear science and technology
    Myung Jo Jhung, Young Hwan Choi, Changheui Jang
    LINK
  • 127
    2010

    Format and Content of Plant-Specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactor

    Journal of nuclear science and technology
    Myung Jo Jhung, Young Hwan Choi, Changheui Jang
    LINK
  • 126
    2010

    Failure Probability of Kori 1 Reactor Pressure Vessel for Pressurized Thermal Shock Failure Probability of Kori 1 Reactor Pressure Vessel for Pressurized Thermal Shock, 2008

    Journal of nuclear science and technology
    Myung Jo Jhung, Young Hwan Choi, Changheui Jang
    LINK
  • 125
    2010

    Boiler and Pressure Vessel Code Boiler and Pressure Vessel Code, 2004

    Journal of nuclear science and technology
    Myung Jo Jhung, Young Hwan Choi, Changheui Jang
    LINK
  • 124
    2010

    Reactor Probabilistic Integrity Evaluation (RPIE) Code: User's Guide Reactor Probabilistic Integrity Evaluation (RPIE) Code: User's Guide, 2008

    Journal of nuclear science and technology
    Myung Jo Jhung, Young Hwan Choi, Changheui Jang
    LINK
  • 123
    2010

    Radiation Embrittlement of Reactor Vessel Materials Radiation Embrittlement of Reactor Vessel Materials, 1988

    Journal of nuclear science and technology
    Myung Jo Jhung, Young Hwan Choi, Changheui Jang
    LINK
  • 122
    2010

    Structural integrity of reactor pressure vessel for small break loss of coolant accident

    Journal of nuclear science and technology
    Myung Jo Jhung, Young Hwan Choi, Changheui Jang
    LINK
  • 121
    2010

    Current Status of Hot Steam Corrosion Evaluation of the Candidate Materials for Intermediate Heat Exchangers of HTSE System

    Transactions of the Korean Society of Pressure Vessels and Piping
    Minu Kim, Dong Hoon Kim, Changheui Jang, Duk-Joo Yoon
    LINK
  • 120
    2010

    Corrosive Wear of Alloy 690 Tubes in Alkaline Water

    Corrosion Science and Technology
    Seung Mo Hong, Changheui Jang, In Sup Kim
    LINK
  • 119
    2010

    Failure assessment of nuclear piping components due to combined degradation mechanisms by an advanced probabilistic fracture mechanics code

    ASME Pressure Vessels and Piping Conference
    Debashis Datta, Changheui Jang
    LINK
  • 118
    2010

    Application of fracture mechanics for the integrity analysis of reactor pressure vessel

    16th Pacific Basin Nuclear Conference (16PBNC)
    Changheui Jang, Bong-Sang Lee
    LINK
  • 117
    2010

    Leak failure analysis for reactor coolant loop in a nuclear power plant

    Proceedings of the 16th Pacific Basin Nuclear Conference (16PBNC), Aomori, Japan, P16P1153
    Debashis Datta, Changheui Jang, Jun-Seog Yang
    LINK
  • 116
    2010

    Microstructural Damages of Alloy 617 under Creep Stress at Elevated Temperature

    IAEA | 50 years of INIS
    Daejong Kim, Changheui Jang, Wooseog Ryu
    LINK
  • 115
    2010

    The Effect of Heat Treatment on Mechanical Properties and Microstructures of Alloy 690

    IAEA | 50 years of INIS
    Pyeongyeon Jo, Hun Jang, Changheui Jang, Hyunchul Cho, Byeongwook Noh
    LINK
  • 114
    2010

    Effect of niobium content on hydride embrittlement of zirconium alloys

    IAEA | 50 years of INIS
    Seung Jin Oh, Chang Heui Jang, Jun Hwan Kim, Yong Hwan Jeong
    LINK
  • 113
    2010

    Mechanical property variation within Inconel 82/182 dissimilar metal weld between low alloy steel and 316 stainless steel

    International Journal of Pressure Vessels and Piping
    Changheui Jang, Jounghoon Lee, Jong Sung Kim, Tae Eun Jin
    LINK
  • 112
    2010

    Structural integrity assessment of reactor pressure vessels during pressurized thermal shock

    Journal of mechanical science and technology
    Myung Jo Jhung, Seok Hun Kim, Young Hwan Choi, Sunggyu Jung, Jong Min Kim, Ji Ho Kim, Jong Wook Kim, Changheui Jang, Yoon Suk Chang, Ki Sig Kang
    LINK
  • 111
    2010

    Characterisation of oxidation and oxide layers of nickel-base superalloys at high temperature

    Nuclear Science Structural Materials for Innovative Nuclear Systems (SMINS) Workshop Proceedings-Karlsruhe, Germany 4-6 June 2007: Workshop Proceedings-Karlsruhe, Germany 4-6 June 2007
    Changheui Jang, Daejin Lee, Daejong Kim
    LINK
  • 110
    2010

    Creep behaviors of alloy 617 at temperatures between 800 and 1000℃

    International Conference on Advances in Nuclear Power Plants, ICAPP 2008
    Daejong Kim, Changheui Jang, WS Ryu
    LINK
  • 109
    2010

    Oxidation behaviour of an Alloy 617 in very high-temperature air and helium environments

    International Journal of Pressure Vessels and Piping
    Changheui Jang, Daejin Lee, Daejong Kim
    LINK
  • 108
    2010

    Effect of Cyclic Strain Rate and Sulfides on Environmentally Assisted Cracking Behaviors of SA508 GR. 1A Low Alloy Steel in Deoxygenated Water at 310℃

    Nuclear Engineering and Technology
    Hun Jang, HYUNCHUL Cho, CHANGHEUI Jang, Tae Soon Kim, Chan Kook Moon
    LINK
  • 107
    2010

    Low cycle fatigue behaviors of type 316LN austenitic stainless steel in 310° C deaerated water–fatigue life and dislocation structure development

    Materials Science and Engineering: A
    Hyunchul Cho, Byoung Koo Kim, In Sup Kim, Changheui Jang
    LINK
  • 106
    2010

    Prediction of Streamflow and the Effect of Input Parameters in Small Urban Catchments

    iEMSs
    HJ Kim, SJ Noh, CH Jang, YJ Lee
    LINK
  • 105
    2010

    A Study on the Structural Integrity Assessment of Dissimilar Welds on Nuclear Power Plant

    Journal of Welding and Joining
    Jong-Sung Kim, Tae-Eun Jin, Yun-Jae Kim, Chang-Heui Jang
    LINK
  • 104
    2010

    Feasibility of Ultrasonic Inspection for Nuclear Grade Graphite

    Journal of the Korean Society for Nondestructive Testing
    Jae-Seok Park, Byung-Sik Yoon, Chang-Heui Jang, Jong-Po Lee
    LINK
  • 103
    2010

    Creep-Environment Interactions of Alloy 617 at Elevated Temperature

    ASME Pressure Vessels and Piping Conference
    Daejong Kim, Changheui Jang, Woo Seog Ryu
    LINK
  • 102
    2010

    Creep behaviors of alloy 617 at temperatures between 800 and 1000 deg. C

    Proceedings of the 2008 International Congress on Advances in Nuclear Power Plants-ICAPP'08
    D Kim, C Jang, WS Ryu
    LINK
  • 101
    2010

    Development of Probabilistic Fracture Mechanics Code for Primary System Pipes and Application for RI-ISI

    ASME Pressure Vessels and Piping Conference
    Changheui Jang, Debashis Datta, Jun-Seog Yang
    LINK
  • 100
    2010

    Failure probability assessment of a PWR Primary System Piping Subcomponents under different loading conditions

    IAEA Second International Symposium on Nuclear Power Plant Life Management, Shanghai, China
    D Datta, C Jang
    LINK
  • 99
    2010

    Effect of Niobium on hydride embrittlement of zirconium alloys

    IAEA | 50 years of INIS
    Seungjin Oh, Changheui Jang, Junhwan Kim, Yonghwan Jeong
    LINK
  • 98
    2010

    Leak Failure Analysis of the Stainless Steel Narrow Gap Welds in Nuclear Power Plant Piping

    Debashis Datta, Changheui Jang
    LINK
  • 97
    2010

    Environmental Effect on the Characteristics of the Structural Materials of the New Advanced Power Plant

    IAEA | 50 years of INIS
    Taesoon Kim, Chankook Moon, Changheui Jang, Hyunchul Cho
    LINK
  • 96
    2010

    Creep and Oxidation Behaviors of Alloy 617 in Air and He Environment

    IAEA | 50 years of INIS
    Daejong Kim, Changheui Jang, Daejin Lee, Wooseog Ryu
    LINK
  • 95
    2010

    Mechanical Properties Evaluation in Inconel 82/182 Dissimilar Metal Welds

    IASMiRT
    Jounghoon Lee, Changheui Jang, Jong Sung Kim, Tae Eun Jin
    LINK
  • 94
    2010

    Embrittlement and hardening during thermal aging of high Cr oxide dispersion strengthened alloys

    Journal of nuclear materials
    JS Lee, CH Jang, In Sup Kim, A Kimura
    LINK
  • 93
    2010

    ASME Boiler and Pressure Vessel Code III Division 1-Appendices ASME Boiler and Pressure Vessel Code III Division 1-Appendices, 1986

    Journal of nuclear science and technology
    Hyunchul Cho, Byoung Koo Kim, In Sup Kim, Changheui JANG, Dae Yul JUNG
    LINK
  • 92
    2010

    Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials, 2006

    Journal of nuclear science and technology
    Hyunchul Cho, Byoung Koo Kim, In Sup Kim, Changheui JANG, Dae Yul JUNG
    LINK
  • 91
    2010

    Effects of LWR Coolant Environments on Fatigue Design Curves of Austenitic Stainless Steels Effects of LWR Coolant Environments on Fatigue Design Curves of Austenitic Stainless …

    Journal of nuclear science and technology
    Hyunchul Cho, Byoung Koo Kim, In Sup Kim, Changheui JANG, Dae Yul JUNG
    LINK
  • 90
    2010

    Hydrogen Effects on Material Behavior and Corrosion Deformation Interactions Hydrogen Effects on Material Behavior and Corrosion Deformation Interactions, 2003

    Journal of nuclear science and technology
    Hyunchul Cho, Byoung Koo Kim, In Sup Kim, Changheui JANG, Dae Yul JUNG
    LINK
  • 89
    2010

    Oxidation characteristics of nickel-base superalloys at high temperature in air and helium atmospheres

    U.S. Department of Energy Office of Scientific and Technical Information
    Lee Daejin, Kim Daejong, Jang Changheui
    LINK
  • 88
    2010

    A Numerical Study on an Optimum Design of a Cross-flow Type Power Turbine (CPT)

    U.S. Department of Energy Office of Scientific and Technical Information
    Joung Hoon Lee, Chang Heui Jang, Jong Sung Kim, Tae Eun Jin
    LINK
  • 87
    2010

    Effect of alloying elements on the tensile properties of hydrided zirconium alloys

    U.S. Department of Energy Office of Scientific and Technical Information
    Seungjin Oh, Changheui Jang, Jun Hwan Kim, Yong Hwan Jeong
    LINK
  • 86
    2010

    The Cyclic Strain Rate Dependence on Environmentally Assisted Cracking Behaviors of SA508 Gr. 1a Low Alloy Steel in 310. deg. C Deoxygenated Water

    U.S. Department of Energy Office of Scientific and Technical Information
    Hun Jang, Hyun Chul Cho, Byoung Koo Kim, In Sup Kim, Chang Heui Jang, Byoung Koo Kim
    LINK
  • 85
    2010

    Fatigue life and crack growth mechanisms of the type 316LN austenitic stainless steel in 310° C deoxygenated water

    Journal of nuclear science and technology
    Hyunchul Cho, Byoung Koo Kim, In Sup Kim, Changheui Jang, Dae Yul Jung
    LINK
  • 84
    2010

    The effect of corrosion product on the corrosion resistance of the galvanized steel in NaCl solutions

    ISRSM2007
    Changheui Jang, SM Hong, SJ Lee, JM Kim, SH Lee
    LINK
  • 83
    2010

    Evaluation of Mechanical Properties in Inconel 82/182 Dissimilar Metal Welds

    Proceedings of the KSME Conference
    Joung-Hoon Lee, Chang-Heui Jang, Jong-Sung Kim, Tae-Eun Jin
    LINK
  • 82
    2010

    VLBI monitoring of OVV 1633+ 382 after mm flare-22GHz preliminary results

    The Bulletin of The Korean Astronomical Society
    Byeong-Won Son, T Krichbaum, SS Lee, A Witzel, A Zensus
    LINK
  • 81
    2010

    Part 2-IX Environmental Effects on Mechanical Behavior-Environmental Fatigue Behaviors of SA508 Gr. 1a Low Alloy Steel in 310 (degree) C Deoxygenated Water

    Key Engineering Materials
    HC Cho, H Jang, BK Kim, IS Kim, CH Jang
    LINK
  • 80
    2010

    Effect of cyclic strain rate on environmental fatigue behaviors of SA508 Gr. 1a low alloy steel in 310° C deoxygenated water

    Advanced Materials Research
    Hyun Chul Cho, Hun Jang, Byoung Koo Kim, In Sup Kim, Chang Heui Jang
    LINK
  • 79
    2010

    Environmental Fatigue Behaviors of SA508 Gr. 1a Low Alloy Steel in 310° C Deoxygenated Water

    Key Engineering Materials
    Hyun Chul Cho, Hun Jang, Byoung Koo Kim, In Sup Kim, Chang Heui Jang
    LINK
  • 78
    2010

    Environmental Fatigue Tests in the Deaerated High Temperature Water

    2007 KEPIC Week
    Changheui Jang, Hyunchul Cho, Hun Jang, In Sup Kim, Chan Kook Moon
    LINK
  • 77
    2010

    Treatment of the thermal–hydraulic uncertainties in the pressurized thermal shock analysis

    Nuclear engineering and design
    Changheui Jang
    LINK
  • 76
    2010

    The high temperature oxidation behaviors of several nickel base superalloys

    2006 Winter Meeting of the American Nuclear Society
    L Daejin, L Sanggyu, Changheui Jang
    LINK
  • 75
    2010

    Fracture toughness of IG-11 graphite with crack size measurement methods

    Transactions
    Daejong Kim, Changheui Jang, Se-Hwan Chi
    LINK
  • 74
    2010

    Study on Low Cycle Fatigue Behavior of Type 316 Stainless Steel in a 310C Water Environment

    International Conference on Water Chemistry of Nuclear Reactor Systems
    Changheui Jang
    LINK
  • 73
    2010

    Oxidation of Inconel alloy 617 at the Elevated Temperature Air Environment

    Korea Nuclear Society
    Daejin Lee, Sanggyu Lee, In Sup Kim, Changheui Jang
    LINK
  • 72
    2010

    Comparative Study of Fatigue Life of Type 316LN Austenitic Stainless Steel in 310. deg. C Low Oxygen-containing Water with Prediction Models

    U.S. Department of Energy Office of Scientific and Technical Information
    Hyun Chul Cho, Byoung Koo Kim, Chang Heui Jang, In Sup Kim, Byong Sup Kim, Seong Cheol Byeon
    LINK
  • 71
    2010

    Corrosive Wear Test of Alloy 690 in Water Chemistry Environment at Room Temperature

    Korean Nuclear Society
    Seung Mo Hong, Changheui Jang, Sang Gyu Lee, In Sup Kim
    LINK
  • 70
    2010

    Evaluation of the corrosion resistance of the galvanized SS400 steel in NaCl solutions

    U.S. Department of Energy Office of Scientific and Technical Information
    Seung Mo Hong, Changheui Jang, In Sup Kim, Kyung Ho Lee, Byung Il Choi
    LINK
  • 69
    2010

    Tensile property evaluation of dissimilar metal welds containing alloy 82/182 fusion weld using miniature specimen

    Proc. of KNS Spring Meeting, Chunchon, Korea. Small Sub-size Sp
    Changheui Jang, Joung Hoon Lee, Sung Yup Jung, Jong Sung Kim, Tae Eun Jin
    LINK
  • 68
    2010

    Spatial variation of mechanical properties in alloy 82/182 dissimilar metal welds

    6th ASINCO
    Changheui Jang
    LINK
  • 67
    2010

    Fracture Toughness and Crack Growth Resistance of the Fine Grain Isotropic Graphite

    Carbon letters
    Daejong Kim, Seung Jin Oh, Changheui Jang, In Sup Kim, Se-Hwan Chi
    LINK
  • 66
    2010

    Approximation method for the calculation of stress intensity factors for the semi-elliptical surface flaws on thin-walled cylinder

    Journal of mechanical science and technology
    Changheui Jang
    LINK
  • 65
    2010

    Effects of hydrogen on the fatigue crack growth rate of low alloy steels

    PROCEEDINGS OF THE 2006 INTERNATIONAL CONGRESS ON ADVANCES IN NUCLEAR POWER PLANTS
    Sang Gyu Lee, Changheui Jang, IS Kim
    LINK
  • 64
    2010

    Reduction in fatigue life of SA508 Gr. 1a low alloy steel in 310C low oxygen-containing water

    한국압력기기공학회 학술대회
    Hyunchul Cho, Byoung Koo Kim, Changheui Jang, In Sup Kim, Hun Jang
    LINK
  • 63
    2010

    Cyclic Hardening Behaviors and Reduction in Fatigue Life of Type 316LN Austenitic Stainless Steel in 310° C Low Oxygen-Containing Water

    International Conference on Nuclear Engineering
    Hyunchul Cho, Byoung Koo Kim, Changheui Jang, In Sup Kim, Seung Mo Hong
    LINK
  • 62
    2010

    Irradiation embrittlement of cladding and HAZ of RPV steel

    Nuclear Engineering and Technology
    CH JANG, In Sup Kim, A KIMURA, JS LEE
    LINK
  • 61
    2010

    475℃ Embrittlement in High Chromium Oxide Dispersion Strengthened Steels

    한국원자력학회 2005 년도 추계학술발표회
    JS Lee, In Sup Kim, CH Jang, A Kimura, BG Kim, KN Choo, YS Choo, YH Kang
    LINK
  • 60
    2010

    Probabilistic Structural Integrity of Reactor Pressure Vessel under Pressurized Thermal Shock

    Changheui Jang
    LINK
  • 59
    2010

    Probabilistic structural integrity of reactor vessel under pressurized thermal shock

    IASMiRT
    Myung Jo Jhung, Young Hwan Choi, Hho Jung Kim, Changheui Jang
    LINK
  • 58
    2010

    475. deg. C embrittlement in high chromium oxide dispersion strengthened steels

    U.S. Department of Energy Office of Scientific and Technical Information
    JS Lee, IS Kim, CH Jang, A Kimura, BG Kim, KN Choo, YS Choo, YH Kang
    LINK
  • 57
    2010

    X-ray diffraction measurements of ion-irradiated graphite

    Proceedings of the Korean Nuclear Society Conference
    Dae Jong Kim, Chang Heui Jang, In Sup Kim, Eung Seon Kim, Se Hwan Chi
    LINK
  • 56
    2010

    Cyclic Deformation Behavior of SA508 Gr. 1a Low Alloy Steel under Low Cycle Fatigue Loading in 310 ℃ Low Oxygen-Contained Water

    한국원자력학회 2005 년도 춘계학술발표회
    Hyunchul Cho, Byoung Koo Kim, Changheui Jang, In Sup Kim, Dae Yul Jung, Seong-Cheol Byeon
    LINK
  • 55
    2010

    Round robin analysis for probabilistic structural integrity of reactor pressure vessel under pressurized thermal shock

    Journal of mechanical science and technology
    Myung Jo Jhung, Changheui Jang, Seok Hun Kim, Young Hwan Choi, Hho Jung Kim, Sunggyu Jung, Jong Min Kim, Gap Heon Sohn, Tae Eun Jin, Taek Sang Choi, Ji Ho Kim, Jong Wook Kim, Keun Bae Park
    LINK
  • 54
    2010

    Low Cycle Fatigue Behaviors of Type 316 Stainless Steel in 310℃ Water Environment

    Proceedings of the Korean Nuclear Society Conference
    Byoung-Koo Kim, Hyun-Chul Cho, In-Sup Kim, Chang-Heui Jang, Dae-Yul Jung, Seong-Cheol Byeon
    LINK
  • 53
    2010

    Thermal aging embrittlement of high chromium oxide dispersion strengthened steels

    Proceedings of the Korean Nuclear Society Conference
    JS Lee, In Sup Kim, CH Jang, A Kimura, BG Kim, KN Choo, YS Choo, YH Kang
    LINK
  • 52
    2010

    Cyclic Deformation Behavior of SA508 Gr.1a Low Alloy Steel under Low Cycle Fatigue Loading in 310℃ Low Oxygen-Contained Water

    Proceedings of the Korean Nuclear Society Conference
    Hyun-Chul Cho, Byoung-Koo Kim, Chang-Heui Jang, In-Sup Kim, Dae-Yul Jung, Seong-Cheol Byeon
    LINK
  • 51
    2010

    Development of Experimental Method to Simulate the Corrosion Products in the Primary System of Nuclear Power Plant

    Proceedings of the Korean Nuclear Society Conference
    Sang-Hyun Kim, In-Sup Kim, Chang-Heui Jang
    LINK
  • 50
    2010

    Cyclic Stress Response and Fatigue Life of Type 316LN Stainless Steel in 310℃ Low Oxygen-containing Water

    Proceedings of the Korean Nuclear Society Conference
    Hyun-Chul Cho, Byoung-Koo Kim, Chang-Heui Jang, In-Sup Kim, Byong-Sup Kim, Seong-Cheol Byeon
    LINK
  • 49
    2010

    Mechanical Property Changes during Accelerated Thermal Aging Embrittlement Heat Treatment of Cast Stainless Steel, CF-8A

    Proceedings of the Korean Nuclear Society Conference
    Korean Nuclear Society
    LINK
  • 48
    2010

    Maintenance Technology Status of Korean Nuclear Power Plants; A Questionnaire Survey

    Proceedings of the Korean Nuclear Society Conference
    Jun-Seok Lee, Poong-Hyun Seong, Chang-Heui Jang, Hyuk-Soon Lim, Jang-Hwan Na, Seong-Jong Oh
    LINK
  • 47
    2010

    Comparative Study on the Technical Standards for the In-Service Inspection of Nuclear Power Plant Components in Several Countries

    Korean Society for Nondestructive Testing
    Ho-Sang Shin, Kyung-Jo Kim, Chang-Heui Jang, Suk-Chull Kang
    LINK
  • 46
    2010

    The effect of analysis variables on the failure probability of the reactor pressure vessel by pressurized thermal shock

    Transactions of the Korean Society of Mechanical Engineers
    Chang-Heui Jang, Myung-Jo Jhung, Suk-Chull Kang, Young-Hwan Choi
    LINK
  • 45
    2010

    The effects of the stainless steel cladding in pressurized thermal shock evaluation

    Nuclear engineering and design
    Changheui Jang, Suk-Chull Kang, Ho-Rim Moonn, Ill-Seok Jeong, Tae-Ryong Kim
    LINK
  • 44
    2010

    Corrosion fatigue cracking of low alloy steel in high temperature water

    Corrosion Science and Technology
    SG Lee, IS Kim, CH Jang, IS Jeong
    LINK
  • 43
    2010

    Comparision and prediction of mechnical properties for the thermally aged cast stainless steels

    IAEA | 50 years of INIS
    SY Cho, CH Jang, IS Jung
    LINK
  • 42
    2010

    PT limit curve construction for the reactor pressure vessel: heatup curve

    IAEA | 50 years of INIS
    CH Jang, HR Mun, IS Jeong, TR Kim
    LINK
  • 41
    2010

    Strain-life curve of SA508Cl. 3 pressure vessel steel in high temperature water environment

    IAEA | 50 years of INIS
    HC Cho, SK Lee, IC Kim, CH Jang, IS Jeong
    LINK
  • 40
    2010

    Experience of the integrity assessment of the highly embrittled reactor pressure vessel for the life extension

    Nuclear engineering and design
    SY Hong, C Jang, IS Jeong
    LINK
  • 39
    2010

    Construction of the PT limit curve for the nuclear reactor pressure vessel using influence coefficient methods: cooldown curve

    Transactions of the Korean Society of Mechanical Engineers
    CH Jang
    LINK
  • 38
    2010

    An Economic Assessment Methodology for Replacement of the Components of Nuclear Power Plant

    ASME Pressure Vessels and Piping Conference
    Ho-Rim Moonn, Changheui Jang, Jun-Hyun Park, Ill-Seok Jeong, Tae-Ryong Kim
    LINK
  • 37
    2010

    Stress intensity factor calculation for the axial semi-elliptical surface flaws on the thin-wall cylinder using influence coefficients

    Transactions of the Korean Society of Mechanical Engineers A
    Chang-Heui Jang, Ho-Rim Moon, Ill-Seok Jeong, Tae-Ryong Kim
    LINK
  • 36
    2010

    Initial RTNDT Re-evaluation of WF-233 weld for Kori unit 1 using master curve technology

    IAEA | 50 years of INIS
    Chang Heui Jang, Ill Seok Jeong, Tae Ryong Kim, Bong Sang Lee, Jun Hwa Hong
    LINK
  • 35
    2010

    The effect of hydrogen behavior on environmentally assisted cracking of vessel steel SA508C1. 3 in high temperature water environment

    IAEA | 50 years of INIS
    JW Kim, CH Jang, IS Jung, SG Lee, IS Kim
    LINK
  • 34
    2010

    Assessment of PWR reactor vessel internals and aging management program for lifetime management

    IAEA | 50 years of INIS
    SK Jeong, TE Jin, CH Jang, IS Jeong
    LINK
  • 33
    2010

    Development of the improved probabilistic fracture mechanics analysis code: VINTIN

    IAEA | 50 years of INIS
    CH Jang, HL Mun, IS Jeong, SY Hong
    LINK
  • 32
    2010

    Initial RT(NDT) Re-evaluation of WF-233 Weld of Kori Unit 1 using Master Curve Technology

    Proceedings of the Korean Nuclear Society Conference
    Jang Changheui, Ill-Seok Jeong, Tae-Ryong Kim, Bong-Sang Lee, Jun-Hwa Hong
    LINK
  • 31
    2010

    Fatigue management considering LWR coolant environments

    Proceedings of the Korean Nuclear Society Conference
    Heung-Bae Park, Tae-Eun Jin, Jang Changheui, Ill-Seok Jeong
    LINK
  • 30
    2010

    Comparison of Stress Intensity Factors for Longitudinal Semi-elliptical Surface Cracks in Cyclindrical Pressure Vessels

    Proceedings of the KSME Conference
    HR Moonn, CH Jang
    LINK
  • 29
    2010

    Stress Intensity Factor Calculation For The Semi-Elliptical Surface Flaws On The Thin-Wall Cylinder Using Influence Coefficients

    Proceedings of the KSME Conference
    Chang-Heui Jang, Ho-Rim Moonn, Ill-Seok Jeong
    LINK
  • 28
    2010

    Treatment of stainless steel cladding in pressurized thermal shock evaluation: deterministic analyses

    Nuclear Engineering and Technology
    Jang Changheui, Sung-Yull Hong
    LINK
  • 27
    2010

    Integrity assessment of the Kori Unit 1 reactor pressure vessel

    Proc. of Korean Nuclear Society Autumn meeting
    Ill-Seok Jeong, Changheui Jang, Sung-Yull Hong
    LINK
  • 26
    2010

    Methodology to decide optimum replacement term for components of nuclear power plants using decision analysis

    IAEA | 50 years of INIS
    HL Moon, CH Jang, JH Park, IS Jung
    LINK
  • 25
    2010

    Activities to Attain Integrity of Embrittled Reactor Pressure Vessel for Plant Lifetime Management Program

    PVP 2000
    Changheui Jang
    LINK
  • 24
    2010

    The Effect of Reference Flaw Size on PT Limit Curves for Pressurized Water Reactor

    PVP 2000
    Changheui Jang
    LINK
  • 23
    2010

    Probabilistic risk assessment of the pt limit curves for pressurized water reactors: cooldown curves

    Changheui Jang, Ill-Seok Jeong, Sung-Yull Hong
    LINK
  • 22
    2010

    Fracture toughness master curve characterization of the low toughness linde 80 weld by small ABI and PCVN specimens

    IAEA | 50 years of INIS
    BS Lee, WJ Yang, JH Hong, CH Jang, SY Hong
    LINK
  • 21
    2010

    Plant-specific pressurized thermal shock integrity evaluation for Kori unit 1 reactor pressure vessel

    Ill-Seok Jeong, Changheui Jang, Jun-Hyun Park, Sung-Yull Hong, Tae-Eun Jin, Sung-Gyu Jung, Hag-Gi Yuem
    LINK
  • 20
    2010

    A study on a probabilistic economic analysis method of steam generation replacement for nuclear power plants

    U.S. Department of Energy Office of Scientific and Technical Information
    HL Moon, CH Jang, JH Park, IS Jung
    LINK
  • 19
    2010

    The effect of flaw orientation on the integrity of PWR pressure vessel at the events of pressurized thermal shock

    Nuclear engineering and design
    Changheui Jang, Ill-Seok Jeong, Sung-Yull Hong
    LINK
  • 18
    2010

    A Probabilistic Fracture Mechanics Analysis for PTS Evaluation of Kori Unit 1 RPV

    ASME
    SG Jung, HS Kim, TE Jin, CH Jang, IS Jeong
    LINK
  • 17
    2010

    A study on the integrity evaluation for PWR vessel by PTS

    IAEA | 50 years of INIS
    SK Jung, TE Jin, CH Jang, IS Jung
    LINK
  • 16
    2010

    Pressurized thermal shock analyses of a reactor pressure vessel using critical crack depth diagrams

    International journal of pressure vessels and piping
    MJ Jhung, YW Park, C Jang
    LINK
  • 15
    2010

    The Estimation of Critical RTNDT and Probability of Failure for PWR vessels

    IASMiRT
    Sung-Gyu Jung, Hyun-Su Kim, Tae-Eun Jin, Chang-Heui Jang, Il-Seok Jeong
    LINK
  • 14
    2010

    Major components life evaluation for nuclear PLIM feasibility study

    IASMiRT
    IS Jeong, CH Jang
    LINK
  • 13
    2010

    Comparative study of probabilistic fracture mechanics codes

    IAEA | 50 years of INIS
    CH Jang, IS Jung, SK Jung, TE Jin
    LINK
  • 12
    2010

    Fatigue life evaluation of major components for nuclear power plant lifetime management

    Changheui Jang, IS Jeong, SY Hong, TE Jin, SG Jung
    LINK
  • 11
    2010

    Korean nuclear power plant lifetime improvement study and future plan

    IAEA | 50 years of INIS
    IS Jeong, CH Jang, SY Hong
    LINK
  • 10
    2010

    Plant specific PTS analysis of Kori Unit 1

    IAEA | International Nuclear Information System
    Sung-Yull Hong, Changheui Jang, Ill-Seok Jeong, Tae-Eun Jin
    LINK
  • 9
    2010

    Nuclear Power Plant Lifetime Management Study (I)

    U.S. Department of Energy Office of Scientific and Technical Information
    Sung Yull Hong, Ill Seok Jeong, Chang Heui Jang, Taek Ho Song, Woo Young Song, Tae Eun Jin, Woo Chul Kim
    LINK
  • 8
    2010

    Fatigue tests and life estimation of Incoloy alloy 908

    Advances in Cryogenic Engineering Materials
    J Feng, LS Toma, CH Jang, MM Steeves
    LINK
  • 7
    2010

    Characterization of simulated production welds in alloy 908

    Advances in Cryogenic Engineering Materials
    CH Jang, DC Grundy, RG Ballinger, MM Steeves
    LINK
  • 6
    2010

    Weld development for Incoloy alloy 908, a low thermal expansion superalloy

    Chang Heui Jang
    LINK
  • 5
    2010

    Development of a high toughness weld for Incoloy alloy 908

    Advances in Cryogenic Engineering Materials
    CH Jang, IS Hwang, RG Ballinger, MM Steeves
    LINK
  • 4
    2010

    US conductor R&D and small scale experiments for the ITER magnets

    15th IEEE/NPSS Symposium. Fusion Engineering
    JV Minervini, MM Steeves, DB Montgomery, R Randall, MK Takayasu
    LINK
  • 3
    2010

    A533B—1 Nuclear Pressure Vessel Steels

    Journal of the Korean Nuclear Society
    CH Jang
    LINK
  • 2
    2010

    A533B-1 원자로 압력용기 강의 미시적 파괴특성에 관한 연구

    Journal of the Korean Nuclear Society
    CH Jang, IS Kim
    LINK
  • 1
    2010

    A study on the microscopic fracture characteristics of A533B-1 nuclear pressure vessel steels

    Nuclear Engineering and Technology
    CH Jang, IS Kim, SP Park
    LINK

최상단으로