Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author Jang, Changheui
Showing results 166 to 225 of 262
| Korean Nuclear Power Plant Lifetime Improvement Study and Future Plan Jang, Changheui, 12th KAIF/KNS Annual Conference, 1997-04-03 |
| Korean PMMD: Approach and prospect Hwang, I.S.; Kang, S.C.; Hong, J.H.; Jang, Changheui, ANS 2009 Spring Meeting, v.100, pp.411 - 412, 2009-06-14 |
| Korean Status Of Environmental Fatigue Tests Of Structural Materials In A Simulated Primary Coolant System Water Jang, Changheui; Jang, Hun; Hong, Jong-Dae; Kim, Tae Soon, Proceedings of ICAPP 2013, Korea Atomic Energy Research Institute (KAERI), 2013-04-14 |
| Leak Failure Analysis for Reactor Coolant Loop in a Nuclear Power Plant Jang, Changheui, 16th Pacific Basin Nuclear Conference (16PBNC), 2008-10-15 |
| Lessons learned from the plant-specific pressurized thermal shock integrity analysis on an embrittled reactor pressure vessel Jeong, IS; Jang, Changheui; Park, JH; Hong, SY; Jin, TE; Yuem, HG; Jeong, SG, INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, v.78, no.2-3, pp.99 - 109, 2001 |
| Life beyond 60 years: Korean perspectives Jang, Changheui; Hwang, II S., 714th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009, v.2, pp.1557 - 1570, 2009-08-23 |
| Low cycle fatigue behavior of alloy 690 in simulated PWR water-Effects of dynamic strain aging and hydrogen Hong, Jongdae; Lee, Junho; Jang, Changheui; Kim, Tae Soon, MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, v.611, pp.37 - 44, 2014-08 |
| Low cycle fatigue behavior of hot-bent 347 stainless steel in a simulated PWR water environment Lee, Junho; Seo, Myung-Gyu; Hong, Jong-Dae; Kim, Tae Soon; Jang, Changheui, JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY, v.30, no.11, pp.4931 - 4936, 2016-11 |
| Low cycle fatigue behavior of hot-bent 347 stainless steels in a simulated PWR environments = 가동 원전 환경에서의 고주파유도가열 배관 벤딩을 적용한 347 스테인리스강의 저주기 피로 거동link Lee, Junho; 이준호; et al, 한국과학기술원, 2016 |
| Low Cycle Fatigue Behaviors of Alloy 690 and 52M in PWR Primary Water Condition Jang, Changheui; Hong, Jong-Dae; Kim, Tae Soon; Lee, Yong Sung, 16th EDM, American Nuclear Society, 2013-08-11 |
| Low Cycle Fatigue Behaviors of Low Alloy Steels and Stainless Steels in Deoxygenated High Temperature Water Jang, Changheui, the 12th International Conference on Pressure Vessel Technology, 2009-09-21 |
| Low cycle fatigue behaviors of type 316LN austenitic stainless steel in 310 degrees C deaerated water-fatigue life and dislocation structure development Cho, Hyunchul; Kim, Byoung Koo; Kim, In Sup; Jang, Changheui, MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, v.476, no.1-2, pp.248 - 256, 2008-03 |
| Maintenance Technology Status of Korean Nuclear Power Plants: A Questionnaire Survey Seong, Poong-Hyun; Jang, Changheui; Lee, Jun Seok; Lim, Hyuk Soon; Na, Jang Hwan; Oh, Seong Jong, 한국원자력학회 2005 추계학술대회, 한국원자력학회, 2005-10 |
| Major components life evaluation for nuclear PLIM feasibility study Jang, Changheui, 15th International Conference on Structural Mechanics in Reactor Technology, 1999-08-16 |
| Mechanical factors in primary water stress corrosion cracking of cold-worked stainless steel Al Hammadi, Rashid; Yi, Yongsun; Zaki, Wael; Cho, Pyungyeon; Jang, Changheui, NUCLEAR ENGINEERING AND DESIGN, v.301, pp.24 - 31, 2016-05 |
| Mechanical Properties Evaluation in Inconel 82/182 Dissimilar Metal Welds Jang, Changheui, 19th International Conference on Structural Mechanics in Reactor Technology (SMiRT 19), 2007-08-13 |
| Mechanical properties of ion-irradiated stainless steel determined by nanoindentation tests and finite element analyses Sim, Jae Min; Chang, Yoon-Suk; Kong, ByeongSeo; Jang, Changheui, ASME 2020 Pressure Vessels and Piping Conference, PVP 2020, American Society of Mechanical Engineers (ASME), 2020-08-03 |
| Mechanical Properties of Ni-base Superalloys in High Temperature Steam Environments Jang, Changheui; Kim, Donghoon; Sah, Injin; Lee, Ho Jung, SMINS-3, Nuclear Energy Agency (NEA), 2013-10-07 |
| Mechanical Properties of the Diffusion-bonded Ni- and Fe-base Alloys Sah, Injin; Hong, Sunghoon; Jang, Changheui, MST 2013 Conference and Exhibition, The Minerals, Metals & Materials Society (TMS), 2013-10-27 |
| Mechanical Property Changes During Accelerated Thermal Aging Embrittlement Heat Treatment of Cast Stainless Steel, CF-8A Wann, KhingMay; Lee, Joo Suk; Jang, Changheui, 한국원자력학회 2005년도 추계학술발표회 , pp.993 - 994, 한국원자력학회, 2005-10 |
| Mechanical property variation within Inconel 82/182 dissimilar metal weld between low alloy steel and 316 stainless steel Jang, Changheui; Lee, Jounghoon; Kim, Jong Sung; Jin, Tae Eun, INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, v.85, no.9, pp.635 - 646, 2008-09 |
| Metal corrosion resistances in high temperature hydriodic aicd gas environment for SI cycle Jang, Changheui; Jin Young Choi; Young Soo Kim; In Jin Sah; No, Hee Cheon, 2012 American Nuclear Society Winter Meetings, American Nuclear Society, 2011-11-14 |
| Microstructure and creep resistance of a diffusionally aluminized Ni-base superalloy Sah, Injin; Kim, Sung Hwan; Jang, Changheui, METALS AND MATERIALS INTERNATIONAL, v.22, no.6, pp.1033 - 1040, 2016-11 |
| Microstructure and hydride embrittlement of zirconium model alloys containing niobium and tin Oh, Seung Jin; Jang, Changheui; Kim, Jun Hwan; Jang, Changheui, MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, v.528, no.10-11, pp.3771 - 3776, 2011-04 |
Microstructure and Tensile Properties of Diffusion Bonded Austenitic Fe-Base Alloys-Before and After Exposure to High Temperature Supercritical-CO2 Kim, Sung Hwan; Cha, Ji-Hwan; Jang, Changheui; Sah, Injin, METALS, v.10, no.4, 2020-04 |
| Microstructure evolution of a Ni-Cr-W superalloy during long-term aging at high temperatures Lee, Ho Jung; Kim, Hyunmyung; Kim, Donghoon; Jang, Changheui, MATERIALS CHARACTERIZATION, v.106, pp.283 - 291, 2015-08 |
| Microstructures, tensile properties and corrosion behaviors of Fe20Cr25NiNb stainless steels with different Al contents in supercritical carbon dioxide Chen, Hongsheng; Luo, Jiandong; Zhang, Tengfei; Jang, Changheui; Tang, Rui; Dong, Baojun; Li, Jin; et al, JOURNAL OF MATERIALS RESEARCH AND TECHNOLOGY-JMR&T, v.23, pp.5246 - 5259, 2023-03 |
| Multiscale simulations for estimating mechanical properties of ion irradiated 308 based on microstructural features Kwak, Dong-Hyeon; Sim, Jae Min; Chang, Yoon-Suk; Kong, Byeong Seo; Jang, Changheui, NUCLEAR ENGINEERING AND TECHNOLOGY, v.55, no.8, pp.2823 - 2834, 2023-08 |
| Nano-scale characterization of microstructure and deformation behavior for δ-ferrite in thermally aged/irradiated stainless steel weld = 열취화 및 조사취화된 스테인리스강 용접부 페라이트에 대한 나노스케일 미세조직 특성 및 변형거동에 대한 연구link Kong, Byeong Seo; Jang, Changheui; et al, 한국과학기술원, 2023 |
| Nano-Structured Columnar Tungsten Coating for Plasma Facing Component in Nuclear Fusion Application Lee, Ho Jung; Kim, Hyunmyung; Jang, Changheui, 2013 AEPSE, AJC-APSE (Asian Joint Committee for Applied Plasma Science and Engineering), 2013-08-25 |
| On the feasibility of duplex stainless steel 2205 as an accident tolerant fuel cladding material for light water reactors Xiao, Qian; Kim, Chaewon; Jang, Changheui; Jeong, Chaewon; Kim, Hyunmyung; Chen, Junjie; Heo, Woong, JOURNAL OF NUCLEAR MATERIALS, v.557, 2021-12 |
| On the use of non-destructive, gigahertz ultrasonics to rapidly screen irradiated steels for swelling resistance Almousa, Nouf; Dacus, Benjamin; Woller, Kevin B.; Shin, Ji Ho; Jang, Changheui; Shao, Lin; Garner, Frank A.; et al, MATERIALS CHARACTERIZATION, v.174, pp.111017, 2021-04 |
| Oxidation behavior of alumina-forming duplex stainless steels in high temperature steam environments = 고온 수증기 환경에서 알루미나 형성 듀플렉스 스테인리스강의 산화 거동link Kim, Chaewon; Jang, Changheui; et al, 한국과학기술원, 2019 |
| Oxidation behavior of Fe-20Cr-25Ni-Nb austenitic stainless steel in high-temperature environment with small amount of water vapor Chen, Hongsheng; Wang, Haibo; Sun, Qingzhu; Long, Chongsheng; Wei, Tianguo; Kim, Sung Hwan; Chen, Junjie; et al, CORROSION SCIENCE, v.145, pp.90 - 99, 2018-12 |
| Oxidation behavior of high-strength FeCrAl alloys in a high-temperature supercritical carbon dioxide environment Chen, Hongsheng; Kim, Sung Hwan; Long, Chongsheng; Kim, Chaewon; Jang, Changheui, PROGRESS IN NATURAL SCIENCE-MATERIALS INTERNATIONAL, v.28, no.6, pp.731 - 739, 2018-12 |
| Oxidation behaviors of wrought Nickel-base superalloys in high temperature nuclear environments Jang, Changheui, IUMRS 11th International Conference in Asia, 2010-09-28 |
| Oxidation behaviour of an Alloy 617 in very high-temperature air and helium environments Jang, Changheui; Lee, Daejin; Kim, Daejong, INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, v.85, no.6, pp.368 - 377, 2008-06 |
| Oxidation Characteristics and Oxide Layer Evolution of Alloy 617 and Haynes 230 at 900 A degrees C and 1100 A degrees C Kim, Daejong; Jang, Changheui; Ryu, Woo Seog, OXIDATION OF METALS, v.71, no.5-6, pp.271 - 293, 2009-06 |
| Oxidation characteristics of Nickel-base superalloys at high temperature in air and helium atmospheres Lee, D.; Kim, D.; Jang, Changheui, Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, The Nuclear Renaissance at Work, pp.2360 - 2365, 2007-05-13 |
| Oxidation Effects on the Strength and Fracture Toughness of the Selected Nuclear Graphite Grades at 600 ¡ÆC Kim, Byung Jun; Kim, Daejong; Jang, Changheui; Chi, Se-Hwan, CARBON 2007, 2007-07-18 |
| Oxidation mechanism and kinetics of nuclear-grade FeCrAl alloys in the temperature range of 500-1500 degrees C in steam Kim, Chaewon; Tang, Chongchong; Grosse, Mirco; Maeng, Yunhwan; Jang, Changheui; Steinbrueck, Martin, JOURNAL OF NUCLEAR MATERIALS, v.564, 2022-06 |
| Oxidation of Inconel alloy 617 at the Elevated Temperature Air Environment Lee, Daejin; Lee, Sanggyu; Jang, Changheui, Korea Nuclear Society, Korea Nuclear Society, 2006 |
| Passivity breakdown of 316L stainless steel during potentiodynamic polarization in NaCl solution Al Saadi, Sara; Yi, Yongsun; Cho, Pyungyeon; Jang, Changheui; Beeley, Philip, CORROSION SCIENCE, v.111, pp.720 - 727, 2016-10 |
| Performance of a dual-process PVD/PS tungsten coating structure under deuterium ion irradiation Kim, Hyunmyung; Lee, Ho Jung; Kim, Sung Hwan; Song, Jae-Min; Jang, Changheui, FUSION ENGINEERING AND DESIGN, v.109, pp.353 - 358, 2016-11 |
| PFM APPLICATION FOR THE PWSCC INTEGRITY OF Ni-BASE ALLOY WELDS - DEVELOPMENT AND APPLICATION OF PINEP-PWSCC Hong, Jong-Dae; Jang, Changheui; Kim, Tae Soon, NUCLEAR ENGINEERING AND TECHNOLOGY, v.44, no.8, pp.961 - 970, 2012-12 |
| Plant Specific PTS Analysis of Kori Unit 1 Jang, Changheui, IAEA Specialist Meeting 1997, 1997-05-06 |
| Plasma thermal performance of a dual-process PVD/PS tungsten coating on carbon-based panels for nuclear fusion application Kim, Hyunmyung; Lee, Ho Jung; Kim, Sung Hwan; Jang, Changheui, FUSION ENGINEERING AND DESIGN, v.109, pp.590 - 595, 2016-11 |
| Potentiodynamic polarization behaviour of AISI type 316 stainless steel in NaCl solution Yi, Y.; Cho, P.; Al Zaabi, A.; Addad, Y.; Jang, Changheui, CORROSION SCIENCE, v.74, pp.92 - 97, 2013-09 |
| Prediction of PT diametral creep for candu reactors using fuzzy neural networks Lee, J.Y.; Na, M.G.; Yang, H.Y.; Lee, S.H.; Jang, Changheui; Kim, D., 6th American Nuclear Society International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies 2009, v.2, pp.1133 - 1143, 2009-04-05 |
| Pressurized thermal shock analyses of a reactor pressure vessel using critical crack depth diagrams Jhung, MJ; Park, YW; Jang, Changheui, INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, v.76, no.12, pp.813 - 823, 1999-10 |
| Pressurized Thermal Shock Evaluation of the Kori Unit 1 Nuclear Power Plant Jang, Changheui, PVP 2000, 2000-07-24 |
| Probabilistic fracture mechanics application for Alloy 600 components in PWRS Hong, J.-D.; Jang, Changheui, International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010, pp.1973 - 1978, 2010-06-13 |
| Probabilistic Fracture Mechanics Application For Alloy 82/182 Welds In PWRs Hong, Jong-Dae; Jang, Changheui, Pressure Vessels & Piping (PVP) 2010, 2010-07-20 |
| Probabilistic Fracture Mechanics Application for PWSCC Risk Evaluation of Ni-base alloy welds in PWR Jang, Changheui; Jong-Dae Kim, ICG-EAC 2012, IGCEAC, 2012-05-14 |
| Probabilistic Fracture Mechanics Round Robin Analysis of Reactor Pressure Vessels during Pressurized Thermal Shock Jhung, Myung Jo; Kim, Seok Hun; Choi, Young Hwan; Chang, Yoon Suk; Xu, Xiangyuan; Kim, Jong Min; Kim, Jong Wook; et al, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.47, no.12, pp.1131 - 1139, 2010-12 |
| Probabilistic Structural Integrity of Reactor Pressure Vessel under Pressurized Thermal Shock Jang, Changheui, SMiRT-18, 2005-08-10 |
| Reduction in fatigue life of SA508 Gr.1a low alloy steel in 310C low oxygen-containing water Cho, Hyunchul; Kim, Byoung Koo; Jang, Changheui; Kim, In Sup; Jang, Hun, 한국압력기기공학회 학술대회, 한국압력기기공학회, 2006 |
| Reduction in fatigue life of type 316LN stainless steel in 310 C low oxygen-containing water Cho, Hyun-Chul; Kim, Byoung-Koo; Jang, Changheui; Kim, In Sup; Kim, Byong-Sup; Byeon, Seong-Cheol, 한국원자력학회 2005년도 추계학술발표회, 한국원자력학회, 2005-10-27 |
| Role of Mechanical Factors in PWSCC of Stainless Steel Cho, Pyungyeon; Yi, Yongsun; Zaki, Wael; Jang, Changheui, EUROCORR 2013, European Commission, 2013-09-01 |
| Role of residual ferrites on crevice SCC of austenitic stainless steels in PWR water with high-dissolved oxygen Sinjlawi, Abdullah; Chen, Junjie; Kim, Ho-Sub; Lee, Hyeon Bae; Jang, Changheui; Lee, Sanghoon, NUCLEAR ENGINEERING AND TECHNOLOGY, v.52, no.11, pp.2552 - 2564, 2020-11 |
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