Paper
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361
Effect of dissolved hydrogen on the early corrosion behavior of 316 stainless steel in simulated PWR environments
Journal of Nuclear MaterialsHyeon Bae Lee, Changheui JangLINK -
360
Oxidation behavior of the directed energy deposited 316L stainless steel in supercritical carbon dioxide environment: Effect of post-manufacturing heat treatment
Additive ManufacturingJunjie Chen, Hyeon Bae Lee, Chaewon Jeong, Qian Xiao, Kyungnam Jang, Taejeong An, Changheui JangLINK -
359
Development of a duplex stainless steel for dry storage canister with improved chloride-induced stress corrosion cracking resistance
Nuclear Engineering and TechnologyChaewon Jeong, Ji Ho Shin, Byeong Seo Kong, Junjie Chen, Qian Xiao, Changheui Jang, Yun-Jae KimLINK -
358
Accelerated Formation of Oxide Layers on Zircaloy-4 Utilizing Air Oxidation and Comparison with Water-Corroded Oxide Layers
MaterialsShanmugam Mannan Muthu, Hyeon-Bae Lee, Bright O Okonkwo, Dong Wang, Changheui Jang, Taehyung NaLINK -
357
Development and optimization of trivalent chromium electrodeposit on 304L stainless steel to improve corrosion resistance in chloride-containing environment
HeliyonBright O Okonkwo, Chaewon Jeong, Hyeon Bae Lee, Changheui Jang, Ehsan Rahimi, Ali DavoodiLINK -
356
Study on Microstructure and Thermal Cycling Performance of the Plasma-sprayed YSZ Coating in Simulated Turbine Environment
High Temperature Corrosion of MaterialsSM Muthu, M Arivarasu, Changheui Jang, S Viknesh, K Surya Prakash Reddy, M Venkateshkannan, VD Vishnu Siddharth, Nafeez Ahmed LiyakatLINK -
355
Multiscale simulations for estimating mechanical properties of ion irradiated 308 based on microstructural features
Nuclear Engineering and TechnologyDong-Hyeon Kwak, Jae Min Sim, Yoon-Suk Chang, Byeong Seo Kong, Changheui JangLINK -
354
Development of Eco-Friendly Chromium Electrodeposit for Corrosion Resistance in Chloride-Containing Environment
AMPP CORROSION ConeferenceBright O Okonkwo, Chaewon Jeong, Taejeong An, Hyun Joon Eom, Changheui JangLINK -
353
Microstructures, tensile properties and corrosion behaviors of Fe20Cr25NiNb stainless steels with different Al contents in supercritical carbon dioxide
Journal of Materials Research and TechnologyHongsheng Chen, Jiandong Luo, Tengfei Zhang, Changheui Jang, Rui Tang, Baojun Dong, Jin Li, Xuesong LengLINK -
352
Stability and strengthening effect of aging induced-nanofeatures in δ-ferrite in an austenitic stainless-steel weld
Journal of Materials Research and TechnologyByeong Seo Kong, Ji Ho Shin, Chaewon Jeong, Changheui Jang, Sung-Sik KangLINK -
351
Evaluation of radiation resistance of an austenitic stainless steel with nanosized carbide precipitates using heavy ion irradiation at 200 dpa
Nuclear Engineering and TechnologyJi Ho Shin, Byeong Seo Kong, Chaewon Jeong, Hyun Joon Eom, Changheui Jang, Lin ShaoLINK -
350
Effect of heat treatment on corrosion behaviour of additively manufactured 316L stainless steel in high-temperature water
Corrosion ScienceQian Xiao, Junjie Chen, Hyeon Bae Lee, Changheui Jang, Kyungnam JangLINK -
349
Determination of Irradiated Stainless Steel Properties and Its Effects on Reactor Vessel Internals
Pressure Vessels and Piping ConferenceDong-Hyeon Kwak, Jae Min Sim, Yoon-Suk Chang, Byeong Seo Kong, Changheui JangLINK -
348
The effect of zinc addition on corrosion behavior of stainless steels with different phases in simulated PWR primary water
Corrosion ScienceSu Hyun Park, Hyeon Bae Lee, Chaewon Kim, Bright O Okonkwo, Changheui Jang, Qian XiaoLINK -
347
Advances on Cr and Ni electrodeposition for industrial applications—a Review
CoatingsBright O Okonkwo, Chaewon Jeong, Changheui JangLINK -
346
Strain-Rate Dependence of Tensile Behavior in Commercial-Grade Tungsten—Effect of Recrystallization Condition
MaterialsByeong Seo Kong, Ji Ho Shin, Taejeong An, Changheui Jang, Hyoung Chan KimLINK -
345
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 PipingByeong Seo Kong, Ji Ho Shin, Chaewon Jeong, Changheui Jang, Sung-Sik KangLINK -
344
Oxidation mechanism and kinetics of nuclear-grade FeCrAl alloys in the temperature range of 500–1500° C in steam
Journal of Nuclear MaterialsChaewon Kim, Chongchong Tang, Mirco Grosse, Yunhwan Maeng, Changheui Jang, Martin SteinbrueckLINK -
343
Swelling resistance of an austenitic stainless steel with uniformly distributed nanosized NbC precipitates under heavy ion irradiation
Journal of Nuclear MaterialsJi Ho Shin, Byeong Seo Kong, Chaewon Jeong, Hyun Joon Eom, Changheui Jang, Nouf AlMousa, Kevin B Woller, Michael P ShortLINK -
342
Enhanced pitting resistance of directed energy deposition 316L stainless steel by post-manufacturing heat treatment
npj Materials DegradationJunjie Chen, Qian Xiao, Hyeon Bae Lee, Chaewon Jeong, Kyungnam Jang, Changheui JangLINK -
341
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 -
340
Corrosion behaviour of alumina-forming heat resistant alloy with Ti in high temperature steam
Corrosion ScienceGokul Obulan Subramanian, Chaewon Kim, Woong Heo, Changheui JangLINK -
339
Dissolution of nanosized NbC precipitates in austenite matrix during elastic deformation-Deleterious effect of high number density
Materials Science and Engineering: AHyun Joon Eom, Ji Ho Shin, Byeong Seo Kong, Chaewon Jeong, Changheui Jang, Daehyeok Ahn, Dongchan JangLINK -
338
Evaluation of thermal aging activation energies based on multi-scale mechanical property tests for an austenitic stainless steel weld beads
Materials Science and Engineering: AChaewon Jeong, Byeong Seo Kong, Ji Ho Shin, Junjie Chen, Qian Xiao, Changheui JangLINK -
337
Effects of ATF cladding properties on PWR responses to an SBO accident: A sensitivity analysis
Annals of Nuclear EnergyAli Alraisi, Yongsun Yi, Suwon Lee, Saeed A Alameri, Maryam Qasem, Chan-Young Paik, Changheui JangLINK -
336
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 -
335
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 -
334
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 -
333
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 -
332
The carburization behavior of alloy 800HT in high temperature supercritical-CO2
Materials LettersGokul Obulan Subramanian, Sung Hwan Kim, Changheui JangLINK -
331
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 -
330
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 -
329
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 -
328
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 -
327
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 -
326
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 -
325
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 -
324
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 -
323
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 -
322
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 -
321
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 -
320
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 -
319
“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 -
318
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 -
317
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 -
316
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 -
315
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 -
314
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 -
313
“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 -
312
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 -
311
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 -
310
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 -
309
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 -
308
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 -
307
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 -
306
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 -
305
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 -
304
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 -
303
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 -
302
Feasibility assessment of the alumina‐forming duplex stainless steels as accident tolerant fuel cladding materials for light water reactors
International Journal of Energy ResearchChaewon Kim, Hyunmyung Kim, Changheui Jang, Kangsan Kim, Yonghee Kim, Seungjae Lee, Hun JangLINK -
301
Effect of Minor Alloying Elements on the Oxidation Behavior of Ni-Base Alloys in a High-Temperature Steam Environment
Oxidation of MetalsSung Hwan Kim, Chaewon Kim, Ji-Hwan Cha, Changheui Jang, Young Soo YooLINK -
300
Cr diffusion coating to improve the corrosion resistance of an ODS steel in super-critical carbon dioxide environment
Surface and Coatings TechnologyChaewon Kim, Sung Hwan Kim, Ji-Hwan Cha, Changheui Jang, Tae Kyu KimLINK -
299
Corrosion behaviors of four stainless steels with similar chromium content in supercritical carbon dioxide environment at 650 C
Corrosion ScienceHongsheng Chen, Sung Hwan Kim, Chaewon Kim, Junjie Chen, Changheui JangLINK -
298
Environmentally-Assisted Fatigue Behavior of 316 Stainless Steels in Simulated PWR Primary Environment: Strain Holding, Zn-Addition, and Their Combined Effect
Pressure Vessels and Piping ConferenceHyeon Bae Lee, Ho-Sub Kim, Junjie Chen, Changheui Jang, Tae Soon Kim, Gary L Stevens, Kawaljit AhluwaliaLINK -
297
Investigation on the thermal butt fusion performance of the buried high density polyethylene piping in nuclear power plant
Nuclear Engineering and TechnologyJong-Sung Kim, Young-Jin Oh, Sun-Woong Choi, Changheui JangLINK -
296
Effect of thermal aging on the corrosion behaviors of ER316L stainless steel welds in simulated PWR environments
Junjie Chen, Changheui Jang, Qian Xiao, Byeong Seo Kong, Gokul Obulan Subramanian, Ji Ho ShinLINK -
295
Effects of heat treatment on mechanical properties and sensitization behavior of materials in dissimilar metal weld
International Journal of Pressure Vessels and PipingHo-Sub Kim, Jiho Shin, Byeong Seo Kong, Sunghoon Hong, Seungjin Oh, Jong-Dae Hong, Changheui Jang, Sanghoon LeeLINK -
294
Effect of zinc on the environmentally-assisted fatigue behavior of 316 stainless steels in simulated PWR primary environment
Corrosion ScienceHo-Sub Kim, Hyeon Bae Lee, Junjie Chen, Changheui Jang, Tae Soon Kim, Gary L Stevens, Kawaljit AhluwaliaLINK -
293
The corrosion behaviour of alloy 690 tube in simulated PWR secondary water with the effect of solid diffusing hydrogen
Journal of Nuclear MaterialsJunjie Chen, Zhanpeng Lu, Fanjiang Meng, Xuelian Xu, Qian Xiao, Ho-Sub Kim, Changheui JangLINK -
292
Comparison of oxide layers formed on the low-cycle fatigue crack surfaces of Alloy 690 and 316 SS tested in a simulated PWR environment
Nuclear Engineering and TechnologyJunjie Chen, Andrieanto Nurrochman, Jong-Dae Hong, Tae Soon Kim, Changheui Jang, Yongsun YiLINK -
291
Advancement of Supercritical Carbon Dioxide Technology through Round Robin Testing and Fundamental Modeling
OSTI.GOVJulie Tucker, Líney Árnadóttir, Mark Anderson, Bruce Pint, Ömer Doğan, Henry Saari, Changheui Jang, Steven KungLINK -
290
Development and Mechanical Characterization of Nuclear Accident Tolerant Duplex Stainless Steel (ADSS)
TMS Annual MeetingHyeonsu Do, Hyunmyung Kim, Changheui Jang, Dongchan JangLINK -
289
Integrity of Alumina Catalytic Support Prepared by Anodization in a High Temperature Steam Environment
Metals and Materials InternationalChaewon Kim, Sung Hwan Kim, Gokul Obulan Subramanian, Changheui Jang, Keun Man ParkLINK -
288
400° C aging embrittlement of FeCrAl alloys: Microstructure and fracture behavior
Materials Science and Engineering: AHyunmyung Kim, Gokul Obulan Subramanian, Chaewon Kim, Hun Jang, Changheui JangLINK -
287
Influence of δ-ferrite content on thermal aging induced mechanical property degradation in cast stainless steels
Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems–Water ReactorsThak Sang Byun, Timothy G Lach, Ying Yang, Changheui JangLINK -
286
Electrochemical Characteristics of Delta Ferrite in Thermally Aged Austenitic Stainless Steel Weld
Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems–Water ReactorsGokul Obulan Subramanian, Sunghoon Hong, Ho Jung Lee, Byeong Seo Kong, Kyoung-Soo Lee, Thak Sang Byun, Changheui JangLINK -
285
Oxidation behavior of high-strength FeCrAl alloys in a high-temperature supercritical carbon dioxide environment
Progress in Natural Science: Materials InternationalHongsheng Chen, Sung Hwan Kim, Chongsheng Long, Chaewon Kim, Changheui JangLINK -
284
Oxidation behavior of Fe-20Cr-25Ni-Nb austenitic stainless steel in high-temperature environment with small amount of water vapor
Corrosion ScienceHongsheng Chen, Haibo Wang, Qingzhu Sun, Chongsheng Long, Tianguo Wei, Sung Hwan Kim, Junjie Chen, Chaewon Kim, Changheui JangLINK -
283
Evaluation of the thermal ageing of austenitic stainless steel welds with 10% of δ-ferrites
International Journal of Pressure Vessels and PipingSunghoon Hong, Hyunmyung Kim, Byeong Seo Kong, Changheui Jang, In Hwan Shin, Jun-Seog Yang, Kyoung-Soo LeeLINK -
282
Evaluation of the thermal aging of δ-ferrite in austenitic stainless steel welds by electrochemical analysis
Scientific reportsGokul Obulan Subramanian, Byeong Seo Kong, Ho Jung Lee, Changheui JangLINK -
281
Evaluation of thermal aging of δ-ferrite in austenitic stainless steel weld using nanopillar compression test
Scripta MaterialiaHo Jung Lee, Byeong Seo Kong, Gokul Obulan Subramanian, Jaewon Heo, Changheui Jang, Kyoung-Soo LeeLINK -
280
Surface modification of austenitic stainless steel for corrosion resistance in high temperature supercritical-carbon dioxide environment
Surface and Coatings TechnologySung Hwan Kim, Gokul Obulan Subramanian, Chaewon Kim, Changheui Jang, Keun Man ParkLINK -
279
Development of alumina-forming duplex stainless steels as accident-tolerant fuel cladding materials for light water reactors
Journal of Nuclear MaterialsHyunmyung Kim, Hun Jang, Gokul Obulan Subramanian, Chaewon Kim, Changheui JangLINK -
278
Corrosion and Carburization Behaviour of Ni-xCr Binary Alloys in a High-Temperature Supercritical-Carbon Dioxide Environment
Oxidation of MetalsGokul Obulan Subramanian, Ho Jung Lee, Sung Hwan Kim, Changheui JangLINK -
277
Supercritical CO2 Round Robin Test Program.
International Supercritical CO2 Power Cycles SymposiumJacob 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 KungLINK -
276
Diffusion bonding of a cold-worked Ni-base superalloy
Pressure TechnologySung Hwan Kim, Chaewon Kim, Changheui JangLINK -
275
Characterization of Alloy 600 joints exposed to a high-temperature supercritical-carbon dioxide environment
Materials CharacterizationHo Jung Lee, Sung Hwan Kim, Changheui JangLINK -
274
Evaluation of Primary Water Stress Corrosion Cracking Resistance of Three Heats of Alloy 600 in 400° C Hydrogenated Steam Condition
MetalsEunsub Yun, Hansub Chung, Changheui JangLINK -
273
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 ApplicationsSung Hwan Kim, Chaewon Kim, Gokul Obulan Subramanian, Changheui JangLINK -
272
Supercritical CO2 round robin test program
The 6th International Supercritical CO2 Power Cycles SymposiumJulie D Tucker, Benjamin Adam, Mark Anderson, Bruce Pint, Gordon R Holcomb, CS Carney, H Saari, L Teeter, J Mahaffey, O Dogan, C Jang, S KungLINK -
271
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-24Ho-Sub Kim, WY Joo, Myeong-Gyu Seo, CH Jang, SJ OhLINK -
270
Influence of microstructure on hydrothermal corrosion of chemically vapor processed SiC composite tubes
Journal of Nuclear MaterialsDaejong Kim, Ho Jung Lee, Changheui Jang, Hyeon-Geun Lee, Ji Yeon Park, Weon-Ju KimLINK -
269
Investigation of the electrical conductivity of sintered monoclinic zirconia (ZrO2)
Ceramics InternationalOh Hyun Kwon, Changheui Jang, Junho Lee, Hu Young Jeong, Young-il Kwon, Jong Hoon Joo, Hongjin KimLINK -
268
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 PipingHyeon Bae Lee, Ho-Sub Kim, Taesoon Kim, Changheui JangLINK -
267
Evaluation of Mechanical Properties and Microstructure of Thermally Aged 308 and 316L Stainless Steel Welds
Transactions of the Korean Society of Pressure Vessels and PipingByeong Seo Kong, Sunghoon Hong, Changheui Jang, Maan-Won KimLINK -
266
Corrosion and carburization behavior of Al-rich surface layer on Ni-base alloy in supercritical-carbon dioxide environment
Applied Surface ScienceHo Jung Lee, Sung Hwan Kim, Hyunmyung Kim, Changheui JangLINK -
265
Low cycle fatigue behavior of hot-bent 347 stainless steel in a simulated PWR water environment
Journal of Mechanical Science and TechnologyJunho Lee, Myung-Gyu Seo, Jong-Dae Hong, Tae Soon Kim, Changheui JangLINK -
264
Microstructure and creep resistance of a diffusionally aluminized Ni-base superalloy
Metals and Materials InternationalInjin Sah, Sung Hwan Kim, Changheui JangLINK -
263
Plasma thermal performance of a dual-process PVD/PS tungsten coating on carbon-based panels for nuclear fusion application
Fusion Engineering and DesignHyunmyung Kim, Ho Jung Lee, Sung Hwan Kim, Changheui JangLINK -
262
Performance of a dual-process PVD/PS tungsten coating structure under deuterium ion irradiation
Fusion Engineering and DesignHyunmyung Kim, Ho Jung Lee, Sung Hwan Kim, Jae-Min Song, Changheui JangLINK -
261
Fatigue Life of Stainless Steel in PWR Environments with Strain Holding
Transactions of the Korean Nuclear Society Autumn MeetingMyeonggyu Seo, Changheui JangLINK -
260
Creep behavior of Alloy 617 in high temperature air and helium environments–effect of oxidation damage
Journal of Mechanical Science and TechnologyChangheui Jang, Sung Hwan Kim, Injin Sah, Daejong KimLINK -
259
Passivity breakdown of 316L stainless steel during potentiodynamic polarization in NaCl solution
Corrosion ScienceSara Al Saadi, Yongsun Yi, Pyungyeon Cho, Changheui Jang, Philip BeeleyLINK -
258
Effect of pressure on the corrosion and carburization behavior of chromia-forming heat-resistant alloys in high-temperature carbon dioxide environments
Corrosion ScienceHo Jung Lee, Gokul Obulan Subramanian, Sung Hwan Kim, Changheui JangLINK -
257
Effect of thermal ageing on mechanical properties of a high-strength ODS alloy
Journal of Mechanical Science and TechnologySunghoon Hong, Sung Hwan Kim, Tae Kyu Kim, Changheui JangLINK -
256
Intergranular oxidation of Ni-based Alloy 600 in a simulated PWR primary water environment
Corrosion ScienceYun Soo Lim, Sung Woo Kim, Seong Sik Hwang, Hong Pyo Kim, Changheui JangLINK -
255
Oxidation Behavior of Surface-modified Stainless Steel 316LN in Supercritical-CO2 Environment
Transactions of the Korean Nuclear Society Spring MeetingSung Hwan Kim, Jin Woo Heo, Hyunmyung Kim, Changheui JangLINK -
254
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 MeetingGokul Obulan Subramanian, Ho Jung Lee, Ji Ho Shin, Changheui JangLINK -
253
Mechanical factors in primary water stress corrosion cracking of cold-worked stainless steel
Nuclear Engineering and DesignRashid Al Hammadi, Yongsun Yi, Wael Zaki, Pyungyeon Cho, Changheui JangLINK -
252
Effects of mixed strain rates on low cycle fatigue behaviors of austenitic stainless steels in a simulated PWR environment
International Journal of FatigueJong-Dae Hong, Changheui Jang, Tae Soon KimLINK -
251
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 MeetingFaisal Shafiqul Islama, Suk-Chull Kangb, Changheui JangaLINK -
250
A comparison of PFM codes for analyzing structural reliability of components
Transactions of the Korean Nuclear Society Autumn MeetingMd Nasimul Goni, Seung Hyun Kim, Yoon-Suk Chang, Changheui JangLINK -
249
Corrosion and carburization behavior of chromia-forming heat resistant alloys in a high-temperature supercritical-carbon dioxide environment
Corrosion ScienceHo Jung Lee, Hyunmyung Kim, Sung Hwan Kim, Changheui JangLINK -
248
Thermal performance of multilayer PVD tungsten coating for the first wall application in nuclear fusion devices
Fusion Science and TechnologyHyunmyung Kim, Ho Jung Lee, Changheui JangLINK -
247
Microstructure evolution of a Ni–Cr–W superalloy during long-term aging at high temperatures
Materials CharacterizationHo Jung Lee, Hyunmyung Kim, Donghoon Kim, Changheui JangLINK -
246
The effects of dissolved hydrogen on the corrosion behavior of Alloy 182 in simulated primary water
Corrosion ScienceJian Xu, Tetsuo Shoji, Changheui JangLINK -
245
Evaluation of the recovery of thermal aging embrittlement of CF8M cast stainless steels after reversion heat treatments
International Journal of Pressure Vessels and PipingChangheui Jang, Hun Jang, Sunghoon Hong, Jae Gon LeeLINK -
244
The hold-time effects on the low cycle fatigue behaviors of 316 SS in PWR primary environment
IAEA | 50 years of INISJunho Lee, Jong-Dae Hong, Myung-Gyu Seo, Changheui JangLINK -
243
In-situ oxide layer analysis of alloy 182 using electrochemical impedance spectroscopy in high dissolved hydrogen condition in PWR environment
IAEA | 50 years of INISHo-Sub Kim, Gokul Obulan Subramanian, Jong-Dae Hong, Junho Lee, Changheui JangLINK -
242
The Effects of CO 2 Pressure on Corrosion and Carburization Behaviors of Chromia-forming Austenitic Alloys
IAEA | 50 years of INISHo Jung Lee, Sung Hwan Kim, Changheui JangLINK -
241
Mechanical Properties of Thermally Aged Austenitic Stainless Steel Welds and Cast Austenitic Stainless Steel
Transactions of the Korean Nuclear Society Spring MeetingSunghoon Honga, Myeong-Gyu Seoa, Changheui Janga, Kyoung Soo LeebLINK -
240
Creep-rupture Behaviors of a Diffusionally Aluminized Alloy 617
Transactions of the Korean Nuclear Society Spring MeetingInjin Sah, Sung Hwan Kimb, Changheui JangLINK -
239
Critical conditions for pit initiation and growth of austenitic stainless steels
Corrosion ScienceM Al Ameri, Y Yi, P Cho, S Al Saadi, C Jang, P BeeleyLINK -
238
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 AHo-Wan Ryu, Jae-Jun Han, Yun-Jae Kim, Jong-Sung Kim, Jeong-Hyeon Kim, Chang-Heui JangLINK -
237
Complex Leakage Probability Evaluation of Nuclear Pipes by Fatigue and Stress Corrosion Cracking
Transactions of the Korean Society of Pressure Vessels and PipingSeung Hyun Kim, Nasimul Goni, Yoon-Suk Chang, Changheui JangLINK -
236
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 PipingInjin Sah, Sunghwan Kim, Sunghoon Hong, Changheui JangLINK -
235
Evaluation of the effects of thermal aging of austenitic stainless steel welds using small punch test
Procedia EngineeringSH Hong, M-G Seo, CH Jang, K-S LeeLINK -
234
Mechanical properties of Ni-base superalloys in high temperature steam environments
IAEA | 50 years of INISChangheui Jang, Donghoon Kim, Injin Sah, Ho Jung LeeLINK -
233
The effect of post-bond heat treatment on tensile property of diffusion bonded austenitic alloys
Transactions of the Korean Society of Mechanical Engineers ASunghoon Hong, Sung Hwan Kim, Changheui Jang, Injin SahLINK -
232
The influence of cooling rate from annealing temperature on the microstructure of Haynes 230
IAEA | 50 years of INISInjin Sah, Sunghoon Hong, Changheui JangLINK -
231
Oxidation characteristics of the electron beam surface-treated Alloy 617 in high temperature helium environments
Journal of Nuclear MaterialsHo Jung Lee, Injin Sah, Donghoon Kim, Hyunmyung Kim, Changheui JangLINK -
230
Oxide characterization for the mechanistic understanding of the initiation behaviors of Alloy 182 weld in various water chemistry conditions
IAEA | 50 years of INISJong-Dae Hong, Junho Lee, Ho-Sup Kim, Changheui Jang, Ji Hyun Kim, Yun Soo Lim, Masashi Watanabe, Jian Xu, Tetsuo ShojiLINK -
229
The Effects of Hot Bending on the Low Cycle Fatigue Behaviors of 347 SS in PWR Primary Environment
IAEA | 50 years of INISHo-Sub Kim, Jong-Dae Hong, Junho Lee, Changheui JangLINK -
228
The Effects of Dissolved Hydrogen on PWSCC Initiation Behavior and Oxide Characteristics of Alloy 182 Weld
IAEA | 50 years of INISJong-Dae Hong, Ho-Sub Kim, Junho Lee, Myeong-Gyu Seo, Changheui JangLINK -
227
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 INISSunghoon Hong, Jong-Dae Hong, Changheui Jang, Kyoung Soo LeeLINK -
226
Corrosion resistances of alloys in high temperature hydrogen iodide gas environment for sulfur–iodine thermochemical cycle
International journal of hydrogen energyJin Young Choi, Young Soo Kim, Injin Sah, Hee Cheon No, Changheui JangLINK -
225
Compatibility of candidate structural materials in high-temperature S-CO2 environment
4th International Symposium-Supercritical CO2 Power Cycles, Pittsburgh, PAHo Jung Lee, Hyunmyung Kim, Changheui JangLINK -
224
Low cycle fatigue behavior of alloy 690 in simulated PWR water—Effects of dynamic strain aging and hydrogen
Materials Science and Engineering: AJong-Dae Hong, Junho Lee, Changheui Jang, Tae Soon KimLINK -
223
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222
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 INISInjin Sah, Sunghoon Hong, Changheui JangLINK -
221
Carbide Transformation in Haynes 230 during Long-term Exposure at High Temperature
IAEA | 50 years of INISHo Jung Lee, Hyunmyung Kim, Sunghoon Hong, Changheui JangLINK -
220
Development of an aluminide coating layer on Alloy 617 by Al sputtering and inter-diffusion heat treatments
Surface and Coatings TechnologyDonghoon Kim, Injin Sah, Ho Jung Lee, Sunghoon Hong, Changheui JangLINK -
219
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 LeeLINK -
218
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 ASunghoon Hong, Injin Sah, Changheui JangLINK -
217
Environmental Fatigue Behaviors of CF8M Stainless Steel in 310℃ Deoxygenated Water-Effects of Hydrogen and Microstructure
Transactions of the Korean Society of Mechanical Engineers AHun Jang, Pyungyeon Cho, Changheui Jang, Tae Soon KimLINK -
216
Development and oxidation resistance evaluation of Al-rich surface layer on Alloy 617
Surface and Coatings TechnologyInjin Sah, Donghoon Kim, Ho Jung Lee, Changheui JangLINK -
215
Environmental fatigue of metallic materials in nuclear power plants–a review of Korean test programs
Nuclear Engineering and TechnologyChangheui Jang, Hun Jang, Jong-Dae Hong, Hyunchul Cho, Tae Soon Kim, Jae-Gon LeeLINK -
214
Study on Alloy 600/690 oxide layer characteristic with Dissolved Hydrogen Concentration Variation and Zinc Injection
2013 ISRSMEun-Sub Yun, Sung-Ho Lee, Jae-Gon Lee, Jong-Il Yun, Changheui JangLINK -
213
Mechanical Properties of the Diffusion-bonded Ni-and Fe-base Alloys
MST 2013 Conference and ExhibitionInjin Sah, Sunghoon Hong, Changheui JangLINK -
212
Corrosion characteristics of Ni-base superalloys in high temperature steam with and without hydrogen
Journal of nuclear materialsDonghoon Kim, Daejong Kim, Ho Jung Lee, Changheui Jang, Duk Joo YoonLINK -
211
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: AHun Jang, Jeong-Hyeon Kim, Changheui Jang, Jae Gon Lee, Tae Soon KimLINK -
210
Effect of strain hardened microstructures on the electrochemical behaviour of 316L stainless steel
EUROCORR 2013Ahmed Al Zaabi, Yongsun Yi, Pyungyeon Cho, Changheui JangLINK -
209
Role of Mechanical Factors in PWSCC of Stainless Steel
EUROCORR 2013Pyungyeon Cho, Yongsun Yi, Wael Zaki, Changheui JangLINK -
208
Evaluation of the sensitization of 316L stainless steels after the post weld heat treatment
IAEA | 50 years of INISChangheui Jang, Hun JangLINK -
207
Potentiodynamic polarization behaviour of AISI type 316 stainless steel in NaCl solution
Corrosion ScienceY Yi, P Cho, A Al Zaabi, Y Addad, Changheui JangLINK -
206
Low Cycle Fatigue Behaviors of Alloy 690 and 52M in PWR Primary Water Condition
16th EDMChangheui Jang, Jong-Dae Hong, Tae Soon Kim, Yong Sung LeeLINK -
205
Environmentally Assisted Fatigue of Alloy 690/52M in PWR Environments
2013 EPRI EAF WorkshopTae Soon Kim, Jong-Dae Hong, Changheui JangLINK -
204
Hydrogen effects on oxidation behaviors of Haynes 230 in high temperature steam environments
Solid State IonicsDonghoon Kim, Injin Sah, Ho Jung Lee, Changheui JangLINK -
203
Environmental fatigue behaviors of Ni-base alloys in PWR primary water environments
2013 ICG-EACJong-Dae Hong, Tae Soon Kim, Yong Sung Lee, Changheui JangLINK -
202
Mechanical Property Characteristics of Butt-Fusion Joint of High Density Polyethylene Pipe for NPP Safety Class Application
IAEA | 50 years of INISYoungjin Oh, Kyoungsu Kim, Seunggun Lee, Heungbae Park, Jeongho Yu, Jongsung Kim, Jeonghyun Kim, Changheui Jang, Sunwoong ChoiLINK -
201
Effect of Ferrite Morphology on Sensitization of 316L Austenitic Stainless Steels
IAEA | 50 years of INISHun Jang, Jun Ho Lee, Changheui JangLINK -
200
Microstructural characteristics and mechanical properties of a mechanically alloyed 15Cr ODS ferritic steel
IAEA | 50 years of INISInjin Sah, Changheui Jang, Tae Kyu Kim, Sanghoon NohLINK -
199
Low cycle fatigue of Alloy 690 and welds in a simulated PWR primary water environment
IAEA | 50 years of INISJongdae Hong, Pyungyeon Cho, Changheui Jang, Tae Soon Kim, Yong Sung LeeLINK -
198
Long-Term Aging Effects on Microstructure and Tensile Properties of Ni-base Superalloys
IAEA | 50 years of INISHo Jung Lee, Dong Hoon Kim, Hyun Myung Kim, Chang Heui JangLINK -
197
The recovery of tensile ductility in diffusion-bonded Ni-base alloys by post-bond heat treatments
Materials & DesignInjin Sah, Donghoon Kim, Ho Jung Lee, Changheui JangLINK -
196
Korean Status Of Environmental Fatigue Tests Of Structural Materials In A Simulated Primary Coolant System Water
Proceedings of ICAPP 2013Changheui Jang, Hun Jang, Jong-Dae Hong, Tae Soon KimLINK -
195
Correlation of metallurgical analysis & higher harmonic ultrasound response for long term isothermally aged and crept FM steel for USC TPP turbine rotors
NDT & E InternationalJaeseok Park, Minsu Kim, Byungha Chi, Changheui JangLINK -
194
Corrosion resistance of surface treated Alloy 617 in high temperature HI and H2SO4 environments
MRS Online Proceedings Library ArchiveDonghoon Kim, Injin Sah, Jin Young Choi, Young Soo Kim, Hee Cheon No, Changheui JangLINK -
193
PFM application for the PWSCC integrity of Ni-base alloy welds—Development and application of PINEP-PWSCC
Nucl. Eng. TechnolJong-Dae Hong, Changheui Jang, Tae Soon KimLINK -
192
Corrosion Resistance of Surface treated Alloy 617 in High Temperature HI and H2SO4 Environments
Materials Research SocietyChangheui Jang, Injin Sah, Jin Young Choi, Young Soo Kim, Hee Cheon NoLINK -
191
Diffusion bonding of Ni-base superalloys for the application of VHTR intermediate heat exchanger
International Welding Joining Conference-Korea 2012Changheui Jang, Injin Sah, Donghoon KimLINK -
190
Corrosion Resistance of Materials at High Temperature Under Gas Phase of Sulfuric Acid for IS Cycle
TransactionsYoung Soo Kim, Jin Young Choi, In Jin Sah, Hee Cheon No, Chang Heui JangLINK -
189
Creep Behaviors of Alloy 617 in High Temperature Steam Environments
NFSM 2012Changheui Jang, Donghoon Kim, Injin Sah, Jahyun KooLINK -
188
Effects Al Contents in the Surface Micro-Alloying Region on the High Temperature Oxidation Behaviors of Alloy 617
NFSM 2012Changheui Jang, Ho Jung Lee, Donghoon Kim, Injin SahLINK -
187
Effects Al Contents in the Surface Micro-Alloying Region on the High Temperature Oxidation Behaviors of Alloy 617
TransactionsHo Jung Lee, Injin Sah, Donghoon Kim, Changheui JangLINK -
186
Creep Behaviors of Alloy 617 in High Temperature Steam Environments
TransactionsDonghoon Kim, Injin Sah, Jahyun Koo, Changheui JangLINK -
185
Creep resistance of Alloy 617 in high temperature helium environments
Asia Pacific Conference on Fracture Strength-Machanical and materials 2012Changheui Jang, Ho Jung Lee, Injin Sah, Jahyun Koo, Dae Jong KimLINK -
184
Diffusion Bonding of Ni-base Superalloys for the Application of VHTR Intermediate Heat Exchanger
대한용접학회 특별강연 및 학술발표대회 개요집Injin Sah, Donghoon Kim, Changheui JangLINK -
183
Metal corrosion resistances in high temperature hydriodic acid gas environment for SI cycle
2012 ANS Winter MeetingHee Cheon No, Choi Jin Young, Kim Young Soo, In Jin SahLINK -
182
Fatigue crack growth behaviors of SA508 Gr. 3 Cl. 2 base and weld material in 290℃ water environment
Corrosion Science and TechnologyPyungyeon Cho, Jeong Hyeon Kim, Changheui Jang, Hyunchul ChoLINK -
181
Analysis of oxidation behavior of Ni-base superalloys by laser-induced breakdown spectroscopy
Journal of Analytical Atomic SpectrometryTae-Hyeong Kim, Dong-Hyoung Lee, Donghoon Kim, Changheui Jang, Jong-Il YunLINK -
180
Corrosion resistance of materials at high temperature under gas phase of sulfuric acid for IS cycle
2012 American Nuclear Society Winter MeetingsChangheui Jang, Young Soo Kim, Jin Young Choi, In Jin Sah, Hee Cheon NoLINK -
179
Metal corrosion resistances in high temperature hydriodic aicd gas environment for SI cycle
2012 American Nuclear Society Winter MeetingsChangheui Jang, Jin Young Choi, Young Soo Kim, In Jin Sah, Hee Cheon NoLINK -
178
Oxidation behaviors of wrought nickel-based superalloys in various high temperature environments
Transactions of nonferrous metals society of ChinaJANG Changheui, KIM Daejong, KIM Donghoon, SAH Injin, RYU Woo-Seog, Young-sung YooLINK -
177
Diametral creep prediction of the pressure tubes in CANDU reactors using a bundle position-wise linear model
Nuclear Engineering and TechnologySung-Han Lee, Dong-Su Kim, Sim-Won Lee, Young-Gyu No, Man-Gyun Na, Jae-Yong Lee, Donghoon Kim, Changheui JangLINK -
176
High temperature oxidation characteristics of surface treated by alloy 617 by Al sputtering and inter-diffusion heat treatment
IAEA | 50 years of INISDonghoon Kim, Jahyun Koo, Injin Sah, Changheui JangLINK -
175
Evaluation of Accelerated Graphitic Corrosion Test of Gray Cast Iron
IAEA | 50 years of INISJeong Hyeon Kim, Jong Dae Hong, Heui Chang, Kyung Hwan Na, Jae Gon LeeLINK -
174
Oxidation behaviors of Ni-base Superalloys for Nuclear Hydrogen production in Steam with and without Hydrogen Environments
IAEA | 50 years of INISDong Hoon Kim, Ja Hyun Koo, Chang Heui Jang, Dae Jong Kim, Young Sung YooLINK -
173
Fatigue Crack Growth Rate and Fracture Resistance of Heat Affected Zone of Stainless Steel Narrow Gap Welds
Transactions of the Korean Nuclear Society Spring MeetingHoJung Leea, Changheui Janga, Sun-Young Chob, Jun-Seog YangcLINK -
172
Creep Properties of Alloy 617 at 900. deg. C in Helium Environments with Various Oxygen Concentrations
IAEA | 50 years of INISJa Hyun Koo, Dong Hoon Kim, In Jin Sah, Chang Heui JangLINK -
171
Application of Electron Beams for Surface Modification of Nickel-base Superalloys
IAEA | 50 years of INISIn Jin Sah, Dong Hoon Kim, Ja Hyun Koo, Chang Heui JangLINK -
170
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 INISHun Jang, Jeong Hyeon Kim, Chang Heui Jang, Tae Soon KimLINK -
169
Microstructure and hydride embrittlement of zirconium model alloys containing niobium and tin
Materials Science and Engineering: ASeung Jin Oh, Changheui Jang, Jun Hwan Kim, Yong Hwan JeongLINK -
168
High temperature oxidation behavior of alloy 617 and Haynes 230 in impurity-controlled helium environments
Oxidation of metalsDaejong Kim, Injin Sah, Donghoon Kim, Woo-Seog Ryu, Changheui JangLINK -
167
Effects of aging in high temperature helium environments on room temperature tensile properties of nickel-base superalloys
Materials Science and Engineering: ADaejong Kim, Injin Sah, Changheui JangLINK -
166
Oxidation Behaviors of Nickel-Base Superalloys in High Temperature Steam Environments
Transactions of the Korean Society of Pressure Vessels and PipingDonghoon Kim, Jahyun Koo, Daejong Kim, Young-Sung Yoo, Changheui JangLINK -
165
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 PipingJahyun Koo, Daejong Kim, Changheui JangLINK -
164
Environmental fatigue behaviors of wrought and cast stainless steels in 310. deg. C Deoxygenated Water
IAEA | 50 years of INISPyung Yeon ChoLINK -
163
Fatigue Crack Growth Rate and Fracture Resistance of Heat Affected Zone of Type 316L Stainless Steel with Narrow Gap Welds
Pressure Vessels and Piping ConferenceHo-Jung Lee, Minu Kim, Changheui Jang, Sun-Young Cho, Jun-Seog YangLINK -
162
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 ChinaChangheui JANG, Daejong KIM, Donghoon KIM, Injin SAH, Woo-Seog RYU, Young-sung YOOLINK -
161
An Assessment of the Integrity of the PWR Vessels An Assessment of the Integrity of the PWR Vessels, 1982
Journal of nuclear science and technologyMyung Jo Jhung, Seok Hun Kim, Young Hwan Choi, Yoon Suk CHANG, Xiangyuan XU, Jong Min KIM, Jong Wook KIM, Changheui JANGLINK -
160
Stress Intensity Factors for Circumferential Surface Cracks in Pipes and Rods under Tension and Bending Loads
Journal of nuclear science and technologyMyung Jo Jhung, Seok Hun Kim, Young Hwan Choi, Yoon Suk CHANG, Xiangyuan XU, Jong Min KIM, Jong Wook KIM, Changheui JANGLINK -
159
Boiler and Pressure Vessel Code Boiler and Pressure Vessel Code Section XI, 2004
Journal of nuclear science and technologyMyung Jo Jhung, Seok Hun Kim, Young Hwan Choi, Yoon Suk CHANG, Xiangyuan XU, Jong Min KIM, Jong Wook KIM, Changheui JANGLINK -
158
VISA-II : A Computer Code for Predicting the Probability of Reactor Vessel Failure
Journal of nuclear science and technologyMyung Jo Jhung, Seok Hun Kim, Young Hwan Choi, Yoon Suk CHANG, Xiangyuan XU, Jong Min KIM, Jong Wook KIM, Changheui JANGLINK -
157
Documentation of Probabilistic Fracture Mechanics Codes Used for Reactor Pressure Vessels Subjected to Pressurized Thermal Shock Loading
Journal of nuclear science and technologyMyung Jo Jhung, Seok Hun Kim, Young Hwan Choi, Yoon Suk CHANG, Xiangyuan XU, Jong Min KIM, Jong Wook KIM, Changheui JANGLINK -
156
Probabilistic fracture mechanics round robin analysis of reactor pressure vessels during pressurized thermal shock
Journal of nuclear science and technologyMyung Jo Jhung, Seok Hun Kim, Young Hwan Choi, Yoon Suk Chang, Xiangyuan Xu, Jong Min Kim, Jong Wook Kim, Changheui JangLINK -
155
Effects of high temperature aging in an impure helium environment on low temperature embrittlement of Alloy 617 and Haynes 230
Journal of Nuclear MaterialsDaejong Kim, Injin Sah, Changheui JangLINK -
154
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 JangLINK -
153
Integrity of Ni-base superalloys for advanced nuclear systems application-environment and materials interaction
Structural Materials for Innovative Nuclear System (SMINS)-2Changheui Jang, D Kim, M Kim, I Sah, WS Ryu, DJ YoonLINK -
152
Hot Steam Corrosion Characteristics of Ni-Base Superalloys for Intermediate Heat Exchangers of HTSE System
TransactionsDonghoon Kim, Daejong Kim, Jahyun Koo, Duk Joo Yoon, Changheui JangLINK -
151
Diametral creep prediction of pressure tube using statistical regression methods
31st Annual Conference of the Canadian Nuclear Society and 34th CNS/CNA Student Conference 2010D Kim, JY Lee, MG Na, Changheui JangLINK -
150
Diametral Creep Prediction of the Pressure Tubes in CANDU Reactors Using a Genetic Optimized Linear Model
IAEA | 50 years of INISSung Han Lee, Young Gyu No, Man Gyun Na, Jae Yong Lee, Chang Heui Jang, Dong Hoon KimLINK -
149
Effects of microstructure and residual stress on fatigue crack growth of stainless steel narrow gap welds
Materials & DesignChangheui Jang, Pyung-Yeon Cho, Minu Kim, Seung-Jin Oh, Jun-Seog YangLINK -
148
Effect of Nb on hydride embrittlement of Zr–xNb alloys
Materials Science and Engineering: ASeungjin Oh, Changheui Jang, Jun Hwan Kim, Yong Hwan JeongLINK -
147
Hot Steam Corrosion Behavior of Ni-based Superalloys at High Temperature Steam Environments
TMS 2010 Spring MeetingDonghoon Kim, Minu Kim, Hyun Min Lee, Daejong Kim, Changheui Jang, Duk-Joo YoonLINK -
146
Probabilistic fracture mechanics application for Alloy 600 components in PWRs
IAEA | 50 years of INISJong-Dae Hong, Changheui JangLINK -
145
Effects of Crack Measurement Methods on The Determination of Fracture Toughness of IG-110 Isotropic Graphite
IAEA | 50 years of INISSe Hwan Chi, Dae Jong Kim, Chang Heui JangLINK -
144
Prediction of the Fundamental Mode Lamb Wave Reflection from a Crack-Like Discontinuity Using Eigen-Mode Expansion
Journal of the Korean Society for Nondestructive TestingJae-Seok Park, Chang-Heui Jang, Jong-Po LeeLINK -
143
Incorporation of Materials’ Sensitive Simulation Technique Into the PINTIN-CAM Code for Integrity of Nuclear Piping System
Pressure Vessels and Piping ConferenceDebashis Datta, Changheui JangLINK -
142
Probabilistic Fracture Mechanics Application for Alloy 82/182 Welds in PWRs
Pressure Vessels and Piping ConferenceJong-Dae Hong, Changheui JangLINK -
141
Effects of the Helium Environment on Degradation of Nickel-Base Superalloys
U.S. Department of Energy Office of Scientific and Technical InformationCH Jang, DJ Kim, D Datta, MW Kim, JH Kwon, A Arief, JY ChoLINK -
140
Diametral Creep Prediction of the Pressure Tubes in CANDU Reactors Using Fuzzy Neural Networks
IAEA | 50 years of INISSung Han Lee, Young Gyu No, Man Gyun Na, Jae Yong Lee, Chang Heui Jang, Dong Hoon KimLINK -
139
Effects of Carburization and Decarburization on Mechanical Properties of Nickel-Base Superalloys
Proceeding of the 12th International Conference on Pressure Vessel TechnologyD Kim, I Sah, Changheui JangLINK -
138
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 2009H Jang, J-D Hong, JG Lee, Changheui JangLINK -
137
Korean PMMD: Approach and Prospect
TransactionsIl Soon Hwang, Suk Chull Kang, Jun Hwa Hong, Ho Sang Shin, Changheui Jang, Young Suk KimLINK -
136
Effect of thermo-mechanical processing on microstructure and creep properties of the foils of alloy 617
Journal of nuclear materialsSK Sharma, Changheui Jang, KJ KangLINK -
135
Oxidation characteristics and oxide layer evolution of alloy 617 and Haynes 230 at 900°C and 1100°C
Oxidation of MetalsDaejong Kim, Changheui Jang, Woo Seog RyuLINK -
134
Diametral Compressive Strength and Elastic Modulus of Flattened Disc using Diametral Compressive Test
IAEA | 50 years of INISDong Hoon Kim, Byung Jun Kim, Chang Heui Jang, Se Hwan ChiLINK -
133
Environmental Fatigue Behaviors of Type 316LN Stainless Steels in Simulated PWR Water with Different Dissolved Hydrogen Contents
IAEA | 50 years of INISHun Jang, Pyung Yeon Jo, Chang Heui JangLINK -
132
The Effect of Inspection Model on the Probability of Vessel Failure due to Pressurized Thermal Shock
IAEA | 50 years of INISMyung Jo Jhung, Young Hwan Choi, Chang Heui JangLINK -
131
Irradiation hardening and embrittlement in high-Cr oxide dispersion strengthened steels
Journal of nuclear materialsS Oh, JS Lee, Changheui Jang, A KimuraLINK -
130
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 TechnologyChangheui JangLINK -
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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 technologyMyung Jo Jhung, Young Hwan Choi, Changheui JangLINK -
127
Format and Content of Plant-Specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactor
Journal of nuclear science and technologyMyung Jo Jhung, Young Hwan Choi, Changheui JangLINK -
126
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 technologyMyung Jo Jhung, Young Hwan Choi, Changheui JangLINK -
125
Boiler and Pressure Vessel Code Boiler and Pressure Vessel Code, 2004
Journal of nuclear science and technologyMyung Jo Jhung, Young Hwan Choi, Changheui JangLINK -
124
Reactor Probabilistic Integrity Evaluation (RPIE) Code: User's Guide Reactor Probabilistic Integrity Evaluation (RPIE) Code: User's Guide, 2008
Journal of nuclear science and technologyMyung Jo Jhung, Young Hwan Choi, Changheui JangLINK -
123
Radiation Embrittlement of Reactor Vessel Materials Radiation Embrittlement of Reactor Vessel Materials, 1988
Journal of nuclear science and technologyMyung Jo Jhung, Young Hwan Choi, Changheui JangLINK -
122
Structural integrity of reactor pressure vessel for small break loss of coolant accident
Journal of nuclear science and technologyMyung Jo Jhung, Young Hwan Choi, Changheui JangLINK -
121
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 PipingMinu Kim, Dong Hoon Kim, Changheui Jang, Duk-Joo YoonLINK -
120
Corrosive Wear of Alloy 690 Tubes in Alkaline Water
Corrosion Science and TechnologySeung Mo Hong, Changheui Jang, In Sup KimLINK -
119
Failure assessment of nuclear piping components due to combined degradation mechanisms by an advanced probabilistic fracture mechanics code
ASME Pressure Vessels and Piping ConferenceDebashis Datta, Changheui JangLINK -
118
Application of fracture mechanics for the integrity analysis of reactor pressure vessel
16th Pacific Basin Nuclear Conference (16PBNC)Changheui Jang, Bong-Sang LeeLINK -
117
Leak failure analysis for reactor coolant loop in a nuclear power plant
Proceedings of the 16th Pacific Basin Nuclear Conference (16PBNC), Aomori, Japan, P16P1153Debashis Datta, Changheui Jang, Jun-Seog YangLINK -
116
Microstructural Damages of Alloy 617 under Creep Stress at Elevated Temperature
IAEA | 50 years of INISDaejong Kim, Changheui Jang, Wooseog RyuLINK -
115
The Effect of Heat Treatment on Mechanical Properties and Microstructures of Alloy 690
IAEA | 50 years of INISPyeongyeon Jo, Hun Jang, Changheui Jang, Hyunchul Cho, Byeongwook NohLINK -
114
Effect of niobium content on hydride embrittlement of zirconium alloys
IAEA | 50 years of INISSeung Jin Oh, Chang Heui Jang, Jun Hwan Kim, Yong Hwan JeongLINK -
113
Mechanical property variation within Inconel 82/182 dissimilar metal weld between low alloy steel and 316 stainless steel
International Journal of Pressure Vessels and PipingChangheui Jang, Jounghoon Lee, Jong Sung Kim, Tae Eun JinLINK -
112
Structural integrity assessment of reactor pressure vessels during pressurized thermal shock
Journal of mechanical science and technologyMyung 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 KangLINK -
111
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 2007Changheui Jang, Daejin Lee, Daejong KimLINK -
110
Creep behaviors of alloy 617 at temperatures between 800 and 1000℃
International Conference on Advances in Nuclear Power Plants, ICAPP 2008Daejong Kim, Changheui Jang, WS RyuLINK -
109
Oxidation behaviour of an Alloy 617 in very high-temperature air and helium environments
International Journal of Pressure Vessels and PipingChangheui Jang, Daejin Lee, Daejong KimLINK -
108
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 TechnologyHun Jang, HYUNCHUL Cho, CHANGHEUI Jang, Tae Soon Kim, Chan Kook MoonLINK -
107
Low cycle fatigue behaviors of type 316LN austenitic stainless steel in 310° C deaerated water–fatigue life and dislocation structure development
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106
Prediction of Streamflow and the Effect of Input Parameters in Small Urban Catchments
iEMSsHJ Kim, SJ Noh, CH Jang, YJ LeeLINK -
105
A Study on the Structural Integrity Assessment of Dissimilar Welds on Nuclear Power Plant
Journal of Welding and JoiningJong-Sung Kim, Tae-Eun Jin, Yun-Jae Kim, Chang-Heui JangLINK -
104
Feasibility of Ultrasonic Inspection for Nuclear Grade Graphite
Journal of the Korean Society for Nondestructive TestingJae-Seok Park, Byung-Sik Yoon, Chang-Heui Jang, Jong-Po LeeLINK -
103
Creep-Environment Interactions of Alloy 617 at Elevated Temperature
ASME Pressure Vessels and Piping ConferenceDaejong Kim, Changheui Jang, Woo Seog RyuLINK -
102
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'08D Kim, C Jang, WS RyuLINK -
101
Development of Probabilistic Fracture Mechanics Code for Primary System Pipes and Application for RI-ISI
ASME Pressure Vessels and Piping ConferenceChangheui Jang, Debashis Datta, Jun-Seog YangLINK -
100
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, ChinaD Datta, C JangLINK -
99
Effect of Niobium on hydride embrittlement of zirconium alloys
IAEA | 50 years of INISSeungjin Oh, Changheui Jang, Junhwan Kim, Yonghwan JeongLINK -
98
Leak Failure Analysis of the Stainless Steel Narrow Gap Welds in Nuclear Power Plant Piping
Debashis Datta, Changheui JangLINK -
97
Environmental Effect on the Characteristics of the Structural Materials of the New Advanced Power Plant
IAEA | 50 years of INISTaesoon Kim, Chankook Moon, Changheui Jang, Hyunchul ChoLINK -
96
Creep and Oxidation Behaviors of Alloy 617 in Air and He Environment
IAEA | 50 years of INISDaejong Kim, Changheui Jang, Daejin Lee, Wooseog RyuLINK -
95
Mechanical Properties Evaluation in Inconel 82/182 Dissimilar Metal Welds
IASMiRTJounghoon Lee, Changheui Jang, Jong Sung Kim, Tae Eun JinLINK -
94
Embrittlement and hardening during thermal aging of high Cr oxide dispersion strengthened alloys
Journal of nuclear materialsJS Lee, CH Jang, In Sup Kim, A KimuraLINK -
93
ASME Boiler and Pressure Vessel Code III Division 1-Appendices ASME Boiler and Pressure Vessel Code III Division 1-Appendices, 1986
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92
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
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91
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 …
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90
Hydrogen Effects on Material Behavior and Corrosion Deformation Interactions Hydrogen Effects on Material Behavior and Corrosion Deformation Interactions, 2003
Journal of nuclear science and technologyHyunchul Cho, Byoung Koo Kim, In Sup Kim, Changheui JANG, Dae Yul JUNGLINK -
89
Oxidation characteristics of nickel-base superalloys at high temperature in air and helium atmospheres
U.S. Department of Energy Office of Scientific and Technical InformationLee Daejin, Kim Daejong, Jang ChangheuiLINK -
88
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 InformationJoung Hoon Lee, Chang Heui Jang, Jong Sung Kim, Tae Eun JinLINK -
87
Effect of alloying elements on the tensile properties of hydrided zirconium alloys
U.S. Department of Energy Office of Scientific and Technical InformationSeungjin Oh, Changheui Jang, Jun Hwan Kim, Yong Hwan JeongLINK -
86
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 InformationHun Jang, Hyun Chul Cho, Byoung Koo Kim, In Sup Kim, Chang Heui Jang, Byoung Koo KimLINK -
85
Fatigue life and crack growth mechanisms of the type 316LN austenitic stainless steel in 310° C deoxygenated water
Journal of nuclear science and technologyHyunchul Cho, Byoung Koo Kim, In Sup Kim, Changheui Jang, Dae Yul JungLINK -
84
The effect of corrosion product on the corrosion resistance of the galvanized steel in NaCl solutions
ISRSM2007Changheui Jang, SM Hong, SJ Lee, JM Kim, SH LeeLINK -
83
Evaluation of Mechanical Properties in Inconel 82/182 Dissimilar Metal Welds
Proceedings of the KSME ConferenceJoung-Hoon Lee, Chang-Heui Jang, Jong-Sung Kim, Tae-Eun JinLINK -
82
VLBI monitoring of OVV 1633+ 382 after mm flare-22GHz preliminary results
The Bulletin of The Korean Astronomical SocietyByeong-Won Son, T Krichbaum, SS Lee, A Witzel, A ZensusLINK -
81
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 MaterialsHC Cho, H Jang, BK Kim, IS Kim, CH JangLINK -
80
Effect of cyclic strain rate on environmental fatigue behaviors of SA508 Gr. 1a low alloy steel in 310° C deoxygenated water
Advanced Materials ResearchHyun Chul Cho, Hun Jang, Byoung Koo Kim, In Sup Kim, Chang Heui JangLINK -
79
Environmental Fatigue Behaviors of SA508 Gr. 1a Low Alloy Steel in 310° C Deoxygenated Water
Key Engineering MaterialsHyun Chul Cho, Hun Jang, Byoung Koo Kim, In Sup Kim, Chang Heui JangLINK -
78
Environmental Fatigue Tests in the Deaerated High Temperature Water
2007 KEPIC WeekChangheui Jang, Hyunchul Cho, Hun Jang, In Sup Kim, Chan Kook MoonLINK -
77
Treatment of the thermal–hydraulic uncertainties in the pressurized thermal shock analysis
Nuclear engineering and designChangheui JangLINK -
76
The high temperature oxidation behaviors of several nickel base superalloys
2006 Winter Meeting of the American Nuclear SocietyL Daejin, L Sanggyu, Changheui JangLINK -
75
Fracture toughness of IG-11 graphite with crack size measurement methods
TransactionsDaejong Kim, Changheui Jang, Se-Hwan ChiLINK -
74
Study on Low Cycle Fatigue Behavior of Type 316 Stainless Steel in a 310C Water Environment
International Conference on Water Chemistry of Nuclear Reactor SystemsChangheui JangLINK -
73
Oxidation of Inconel alloy 617 at the Elevated Temperature Air Environment
Korea Nuclear SocietyDaejin Lee, Sanggyu Lee, In Sup Kim, Changheui JangLINK -
72
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 InformationHyun Chul Cho, Byoung Koo Kim, Chang Heui Jang, In Sup Kim, Byong Sup Kim, Seong Cheol ByeonLINK -
71
Corrosive Wear Test of Alloy 690 in Water Chemistry Environment at Room Temperature
Korean Nuclear SocietySeung Mo Hong, Changheui Jang, Sang Gyu Lee, In Sup KimLINK -
70
Evaluation of the corrosion resistance of the galvanized SS400 steel in NaCl solutions
U.S. Department of Energy Office of Scientific and Technical InformationSeung Mo Hong, Changheui Jang, In Sup Kim, Kyung Ho Lee, Byung Il ChoiLINK -
69
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 SpChangheui Jang, Joung Hoon Lee, Sung Yup Jung, Jong Sung Kim, Tae Eun JinLINK -
68
Spatial variation of mechanical properties in alloy 82/182 dissimilar metal welds
6th ASINCOChangheui JangLINK -
67
Fracture Toughness and Crack Growth Resistance of the Fine Grain Isotropic Graphite
Carbon lettersDaejong Kim, Seung Jin Oh, Changheui Jang, In Sup Kim, Se-Hwan ChiLINK -
66
Approximation method for the calculation of stress intensity factors for the semi-elliptical surface flaws on thin-walled cylinder
Journal of mechanical science and technologyChangheui JangLINK -
65
Effects of hydrogen on the fatigue crack growth rate of low alloy steels
PROCEEDINGS OF THE 2006 INTERNATIONAL CONGRESS ON ADVANCES IN NUCLEAR POWER PLANTSSang Gyu Lee, Changheui Jang, IS KimLINK -
64
Reduction in fatigue life of SA508 Gr. 1a low alloy steel in 310C low oxygen-containing water
한국압력기기공학회 학술대회Hyunchul Cho, Byoung Koo Kim, Changheui Jang, In Sup Kim, Hun JangLINK -
63
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 EngineeringHyunchul Cho, Byoung Koo Kim, Changheui Jang, In Sup Kim, Seung Mo HongLINK -
62
Irradiation embrittlement of cladding and HAZ of RPV steel
Nuclear Engineering and TechnologyCH JANG, In Sup Kim, A KIMURA, JS LEELINK -
61
475℃ Embrittlement in High Chromium Oxide Dispersion Strengthened Steels
한국원자력학회 2005 년도 추계학술발표회JS Lee, In Sup Kim, CH Jang, A Kimura, BG Kim, KN Choo, YS Choo, YH KangLINK -
60
Probabilistic Structural Integrity of Reactor Pressure Vessel under Pressurized Thermal Shock
Changheui JangLINK -
59
Probabilistic structural integrity of reactor vessel under pressurized thermal shock
IASMiRTMyung Jo Jhung, Young Hwan Choi, Hho Jung Kim, Changheui JangLINK -
58
475. deg. C embrittlement in high chromium oxide dispersion strengthened steels
U.S. Department of Energy Office of Scientific and Technical InformationJS Lee, IS Kim, CH Jang, A Kimura, BG Kim, KN Choo, YS Choo, YH KangLINK -
57
X-ray diffraction measurements of ion-irradiated graphite
Proceedings of the Korean Nuclear Society ConferenceDae Jong Kim, Chang Heui Jang, In Sup Kim, Eung Seon Kim, Se Hwan ChiLINK -
56
Cyclic Deformation Behavior of SA508 Gr. 1a Low Alloy Steel under Low Cycle Fatigue Loading in 310 ℃ Low Oxygen-Contained Water
한국원자력학회 2005 년도 춘계학술발표회Hyunchul Cho, Byoung Koo Kim, Changheui Jang, In Sup Kim, Dae Yul Jung, Seong-Cheol ByeonLINK -
55
Round robin analysis for probabilistic structural integrity of reactor pressure vessel under pressurized thermal shock
Journal of mechanical science and technologyMyung 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 ParkLINK -
54
Low Cycle Fatigue Behaviors of Type 316 Stainless Steel in 310℃ Water Environment
Proceedings of the Korean Nuclear Society ConferenceByoung-Koo Kim, Hyun-Chul Cho, In-Sup Kim, Chang-Heui Jang, Dae-Yul Jung, Seong-Cheol ByeonLINK -
53
Thermal aging embrittlement of high chromium oxide dispersion strengthened steels
Proceedings of the Korean Nuclear Society ConferenceJS Lee, In Sup Kim, CH Jang, A Kimura, BG Kim, KN Choo, YS Choo, YH KangLINK -
52
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 ConferenceHyun-Chul Cho, Byoung-Koo Kim, Chang-Heui Jang, In-Sup Kim, Dae-Yul Jung, Seong-Cheol ByeonLINK -
51
Development of Experimental Method to Simulate the Corrosion Products in the Primary System of Nuclear Power Plant
Proceedings of the Korean Nuclear Society ConferenceSang-Hyun Kim, In-Sup Kim, Chang-Heui JangLINK -
50
Cyclic Stress Response and Fatigue Life of Type 316LN Stainless Steel in 310℃ Low Oxygen-containing Water
Proceedings of the Korean Nuclear Society ConferenceHyun-Chul Cho, Byoung-Koo Kim, Chang-Heui Jang, In-Sup Kim, Byong-Sup Kim, Seong-Cheol ByeonLINK -
49
Mechanical Property Changes during Accelerated Thermal Aging Embrittlement Heat Treatment of Cast Stainless Steel, CF-8A
Proceedings of the Korean Nuclear Society ConferenceKorean Nuclear SocietyLINK -
48
Maintenance Technology Status of Korean Nuclear Power Plants; A Questionnaire Survey
Proceedings of the Korean Nuclear Society ConferenceJun-Seok Lee, Poong-Hyun Seong, Chang-Heui Jang, Hyuk-Soon Lim, Jang-Hwan Na, Seong-Jong OhLINK -
47
Comparative Study on the Technical Standards for the In-Service Inspection of Nuclear Power Plant Components in Several Countries
Korean Society for Nondestructive TestingHo-Sang Shin, Kyung-Jo Kim, Chang-Heui Jang, Suk-Chull KangLINK -
46
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 EngineersChang-Heui Jang, Myung-Jo Jhung, Suk-Chull Kang, Young-Hwan ChoiLINK -
45
The effects of the stainless steel cladding in pressurized thermal shock evaluation
Nuclear engineering and designChangheui Jang, Suk-Chull Kang, Ho-Rim Moonn, Ill-Seok Jeong, Tae-Ryong KimLINK -
44
Corrosion fatigue cracking of low alloy steel in high temperature water
Corrosion Science and TechnologySG Lee, IS Kim, CH Jang, IS JeongLINK -
43
Comparision and prediction of mechnical properties for the thermally aged cast stainless steels
IAEA | 50 years of INISSY Cho, CH Jang, IS JungLINK -
42
PT limit curve construction for the reactor pressure vessel: heatup curve
IAEA | 50 years of INISCH Jang, HR Mun, IS Jeong, TR KimLINK -
41
Strain-life curve of SA508Cl. 3 pressure vessel steel in high temperature water environment
IAEA | 50 years of INISHC Cho, SK Lee, IC Kim, CH Jang, IS JeongLINK -
40
Experience of the integrity assessment of the highly embrittled reactor pressure vessel for the life extension
Nuclear engineering and designSY Hong, C Jang, IS JeongLINK -
39
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 EngineersCH JangLINK -
38
An Economic Assessment Methodology for Replacement of the Components of Nuclear Power Plant
ASME Pressure Vessels and Piping ConferenceHo-Rim Moonn, Changheui Jang, Jun-Hyun Park, Ill-Seok Jeong, Tae-Ryong KimLINK -
37
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 AChang-Heui Jang, Ho-Rim Moon, Ill-Seok Jeong, Tae-Ryong KimLINK -
36
Initial RTNDT Re-evaluation of WF-233 weld for Kori unit 1 using master curve technology
IAEA | 50 years of INISChang Heui Jang, Ill Seok Jeong, Tae Ryong Kim, Bong Sang Lee, Jun Hwa HongLINK -
35
The effect of hydrogen behavior on environmentally assisted cracking of vessel steel SA508C1. 3 in high temperature water environment
IAEA | 50 years of INISJW Kim, CH Jang, IS Jung, SG Lee, IS KimLINK -
34
Assessment of PWR reactor vessel internals and aging management program for lifetime management
IAEA | 50 years of INISSK Jeong, TE Jin, CH Jang, IS JeongLINK -
33
Development of the improved probabilistic fracture mechanics analysis code: VINTIN
IAEA | 50 years of INISCH Jang, HL Mun, IS Jeong, SY HongLINK -
32
Initial RT(NDT) Re-evaluation of WF-233 Weld of Kori Unit 1 using Master Curve Technology
Proceedings of the Korean Nuclear Society ConferenceJang Changheui, Ill-Seok Jeong, Tae-Ryong Kim, Bong-Sang Lee, Jun-Hwa HongLINK -
31
Fatigue management considering LWR coolant environments
Proceedings of the Korean Nuclear Society ConferenceHeung-Bae Park, Tae-Eun Jin, Jang Changheui, Ill-Seok JeongLINK -
30
Comparison of Stress Intensity Factors for Longitudinal Semi-elliptical Surface Cracks in Cyclindrical Pressure Vessels
Proceedings of the KSME ConferenceHR Moonn, CH JangLINK -
29
Stress Intensity Factor Calculation For The Semi-Elliptical Surface Flaws On The Thin-Wall Cylinder Using Influence Coefficients
Proceedings of the KSME ConferenceChang-Heui Jang, Ho-Rim Moonn, Ill-Seok JeongLINK -
28
Treatment of stainless steel cladding in pressurized thermal shock evaluation: deterministic analyses
Nuclear Engineering and TechnologyJang Changheui, Sung-Yull HongLINK -
27
Integrity assessment of the Kori Unit 1 reactor pressure vessel
Proc. of Korean Nuclear Society Autumn meetingIll-Seok Jeong, Changheui Jang, Sung-Yull HongLINK -
26
Methodology to decide optimum replacement term for components of nuclear power plants using decision analysis
IAEA | 50 years of INISHL Moon, CH Jang, JH Park, IS JungLINK -
25
Activities to Attain Integrity of Embrittled Reactor Pressure Vessel for Plant Lifetime Management Program
PVP 2000Changheui JangLINK -
24
The Effect of Reference Flaw Size on PT Limit Curves for Pressurized Water Reactor
PVP 2000Changheui JangLINK -
23
Probabilistic risk assessment of the pt limit curves for pressurized water reactors: cooldown curves
Changheui Jang, Ill-Seok Jeong, Sung-Yull HongLINK -
22
Fracture toughness master curve characterization of the low toughness linde 80 weld by small ABI and PCVN specimens
IAEA | 50 years of INISBS Lee, WJ Yang, JH Hong, CH Jang, SY HongLINK -
21
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 YuemLINK -
20
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 InformationHL Moon, CH Jang, JH Park, IS JungLINK -
19
The effect of flaw orientation on the integrity of PWR pressure vessel at the events of pressurized thermal shock
Nuclear engineering and designChangheui Jang, Ill-Seok Jeong, Sung-Yull HongLINK -
18
A Probabilistic Fracture Mechanics Analysis for PTS Evaluation of Kori Unit 1 RPV
ASMESG Jung, HS Kim, TE Jin, CH Jang, IS JeongLINK -
17
A study on the integrity evaluation for PWR vessel by PTS
IAEA | 50 years of INISSK Jung, TE Jin, CH Jang, IS JungLINK -
16
Pressurized thermal shock analyses of a reactor pressure vessel using critical crack depth diagrams
International journal of pressure vessels and pipingMJ Jhung, YW Park, C JangLINK -
15
The Estimation of Critical RTNDT and Probability of Failure for PWR vessels
IASMiRTSung-Gyu Jung, Hyun-Su Kim, Tae-Eun Jin, Chang-Heui Jang, Il-Seok JeongLINK -
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13
Comparative study of probabilistic fracture mechanics codes
IAEA | 50 years of INISCH Jang, IS Jung, SK Jung, TE JinLINK -
12
Fatigue life evaluation of major components for nuclear power plant lifetime management
Changheui Jang, IS Jeong, SY Hong, TE Jin, SG JungLINK -
11
Korean nuclear power plant lifetime improvement study and future plan
IAEA | 50 years of INISIS Jeong, CH Jang, SY HongLINK -
10
Plant specific PTS analysis of Kori Unit 1
IAEA | International Nuclear Information SystemSung-Yull Hong, Changheui Jang, Ill-Seok Jeong, Tae-Eun JinLINK -
9
Nuclear Power Plant Lifetime Management Study (I)
U.S. Department of Energy Office of Scientific and Technical InformationSung Yull Hong, Ill Seok Jeong, Chang Heui Jang, Taek Ho Song, Woo Young Song, Tae Eun Jin, Woo Chul KimLINK -
8
Fatigue tests and life estimation of Incoloy alloy 908
Advances in Cryogenic Engineering MaterialsJ Feng, LS Toma, CH Jang, MM SteevesLINK -
7
Characterization of simulated production welds in alloy 908
Advances in Cryogenic Engineering MaterialsCH Jang, DC Grundy, RG Ballinger, MM SteevesLINK -
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5
Development of a high toughness weld for Incoloy alloy 908
Advances in Cryogenic Engineering MaterialsCH Jang, IS Hwang, RG Ballinger, MM SteevesLINK -
4
US conductor R&D and small scale experiments for the ITER magnets
15th IEEE/NPSS Symposium. Fusion EngineeringJV Minervini, MM Steeves, DB Montgomery, R Randall, MK TakayasuLINK -
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1
A study on the microscopic fracture characteristics of A533B-1 nuclear pressure vessel steels
Nuclear Engineering and TechnologyCH Jang, IS Kim, SP ParkLINK