Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author Jang, Changheui
Showing results 137 to 196 of 262
| Failure assessment of nuclear piping components due to combined degradation mechanisms by an advanced probabilistic fracture mechanics code Datta, D.; Jang, Changheui, 2009 ASME Pressure Vessels and Piping Conference, PVP 2009, pp.687 - 694, 2009-07-26 |
| Failure probability assessment of a PWR Primary System Piping subcomponents under different loading conditions Jang, Changheui; Datta, D., Second Int. Symp. on Nuclear Power Plant Life Management, 2007 |
| Fatigue Crack Growth and Fracture Resistance of the Stainless Steel Narrow Gap Welds in Nuclear Piping System Jang, Changheui, 7th ASINCO, 2008-07-03 |
| Fatigue life and crack growth mechanisms of the type 316LN austenitic Stainless Steel in 310 degrees C deoxygenated water Cho, Hyunchul; Kim, Byoung Koo; Kim, In Sup; Jang, Changheui; Jung, Dae Yul, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.44, no.7, pp.1007 - 1014, 2007-07 |
| Fatigue Life Evaluation of Major Components for Nuclear Power Plant Lifetime Management Jang, Changheui, 14th International Conference on Structural Mechanics in Reactor Technology, 1997-08-20 |
| Fatigue Test and Life Estimation of Incoloy 908 Jang, Changheui, Advances on Cryogenic Engineering, 1996-07-15 |
| Feasibility assessment of the alumina-forming duplex stainless steels as accident tolerant fuel cladding materials for light water reactors Kim, Chaewon; Kim, Hyunmyung; Jang, Changheui; Kim, Kangsan; Kim, Yonghee; Lee, Seungjae; Jang, Hun, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.44, no.10, pp.8074 - 8088, 2020-08 |
| Fracture Behaviors of Isotropic Nuclear Graphite Jang, Changheui, CARBON 2006, 2006-07-18 |
| Fracture property degradation in cast stainless steels after long-term thermal aging Byun, TS; Lach, TG; Collins, DA; Jang, Changheui, 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019, pp.294 - 302, American Nuclear Society, 2019-08 |
| Fracture toughness of IG-11 graphite with crack size measurement methods Kim, D.; Jang, Changheui; Chi, S.-H., 2006 Winter Meeting of the American Nuclear Society, pp.101 - 102, 2006-11-12 |
| High Temperature Oxidation Characteristics of Surface Treated Alloy 617 by Al Sputtering and Inter-Diffusion Heat Treatment Kim, Donghoon; Koo, Jahyun; Jang, Changheui, International Congress on Advances in Nuclear Power Plants (ICAPP 2011), 2011-05-03 |
| High-strength Fe-Cr-Ni-Al multiplex stainless steel and manufacturing method therefor Jang, Changheui; Kim, Hyun-Myung; Gokul Obulan Subramanian; Heo, Jin-Woo; Lee, Ho-Jung; Hong, Sung-Hoon; Kim, Chae-Won |
| High-strength Fe—Cr—Ni—Al multiplex stainless steel and manufacturing method therefor Jang, Changheui; Kim, Hyunmyung; Subramanian, Gokul Obulan; Heo, Jin Woo; Lee, Ho Jung; Hong, Sunghoon; Kim, Chaewon |
| High-temperature steam oxidation behavior of alumina-forming duplex FeNiCrAl and ferritic FeCrAl alloys at 800 degrees C to 1050 degrees C Kim, Chaewon; Kim, Hyunmyung; Heo, Woong; Jang, Changheui; Lee, Sung Yong; Lee, Seungjae; Lee, Jin-Soo, CORROSION SCIENCE, v.190, pp.109658, 2021-09 |
| Hot Steam Corrosion Behavior of Ni-based Superalloys at High Temperature Steam Environments Kim, Donghoon; Kim, Minu; Lee, Hyun Min; Kim, Daejong; Jang, Changheui; Yoon, Duk-Joo, TMS 2010 Spring Meeting, 2010-02-15 |
| Hot steam corrosion characteristics of Ni-base superalloys for intermediate heat exchangers of HTSE system KIM, Donghoon; KIM, Daejong; KOO, Jahyun; DUK, JOO YOON; Jang, Changheui, 2010 ANS Annual Meeting and Embedded Topical Meetings, pp.863 - 864, 2010-06-13 |
| Hydrogen Production Using High Temperature Steam Electrolysis - Status of Research Jang, Changheui; No, Hee Cheon; Jeong, Yong Hoon; Bae, Joongmyeon; Yoon, Duk-Joo, 24th KAIF/KNS Annual Conference, KAIF/KNS, 2009-04-10 |
| Incorporation of materials’ sensitive simulation technique into the PINTIN-CAM code for integrity of nuclear piping system Jang, Changheui, Pressure Vessels & Piping 2010, 2010-07-20 |
| Influence of delta-Ferrite Content on Thermal Aging Induced Mechanical Property Degradation in Cast Stainless Steels Byun, Thak Sang; Lach, Timothy G.; Yang, Ying; Jang, Changheui, 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, pp.613 - 624, SPRINGER INTERNATIONAL PUBLISHING AG, 2017-08 |
| Influence of microstructure on hydrothermal corrosion of chemically vapor processed SiC composite tubes Kim, Daejong; Lee, Ho Jung; Jang, Changheui; Lee, Hyeon-Geun; Park, Ji Yeon; Kim, Weon-Ju, JOURNAL OF NUCLEAR MATERIALS, v.492, pp.6 - 13, 2017-08 |
| Integrity of Alumina Catalytic Support Prepared by Anodization in a High Temperature Steam Environment Kim, Chaewon; Kim, Sung Hwan; Subramanian, Gokul Obulan; Jang, Changheui; Park, Keun Man, METALS AND MATERIALS INTERNATIONAL, v.25, no.2, pp.324 - 332, 2019-03 |
| Integrity of Ni-base superalloys for advanced nuclear systems application - environment and materials interaction Jang, Changheui; Kim, D; Kim, D; Kim, M; Sah, I; Ryu, WS; Yoon, DJ, Structural Materials for Innovative Nuclear System (SMINS)-2, 2010-09-01 |
| Intergranular oxidation of Ni-based Alloy 600 in a simulated PWR primary water environment Lim, Yun Soo; Kim, Sung Woo; Hwang, Seong Sik; Kim, Hong Pyo; Jang, Changheui, CORROSION SCIENCE, v.108, pp.125 - 133, 2016-07 |
| Investigation of the electrical conductivity of sintered monoclinic zirconia (ZrO2) Kwon, Oh Hyun; Jang, Changheui; Lee, Junho; Jeong, Hu Young; Kwon, Young-il; Joo, Jong Hoon; Kim, Hongjin, CERAMICS INTERNATIONAL, v.43, no.11, pp.8236 - 8245, 2017-08 |
| Investigation on corrosion mechanism of Nb-added Zirconium alloy by analysis of electrical conductivity = 전기전도도 분석을 통한 니오비움 첨가 지르코늄합금 부식기구 연구link Kwon, Ohhyun; Jang, Changheui; et al, 한국과학기술원, 2019 |
INVESTIGATION ON THE THERMAL BUTT FUSION PERFORMANCE OF THE BURIED HIGH DENSITY POLYETHYLENE PIPING IN NUCLEAR POWER PLANT Kim, Jong-Sung; Oh, Young-Jin; Choi, Sun-Woong; Jang, Changheui, NUCLEAR ENGINEERING AND TECHNOLOGY, v.51, no.4, pp.1142 - 1153, 2019-07 |
| Irradiation Embrittlement of Cladding and HAZ of RPV Steel Jang, Changheui; Kim, In Sup; Lee, J.S.; Kimura, A., International Symposium on Research Reactor and Neutron Science, 2005-04-15 |
| IRRADIATION EMBRITTLEMENT OF CLADDING AND HAZ OF RPV STEEL Lee J.S; Kim I.S; Jang, Changheui; Kimura A, NUCLEAR ENGINEERING AND TECHNOLOGY, v.38, no.5, pp.405 - 410, 2006-08 |
| Irradiation hardening and embrittlement in high-Cr oxide dispersion strengthened steels Oh, S; Lee, JS; Jang, Changheui; Kimura, A, JOURNAL OF NUCLEAR MATERIALS, v.386-88, pp.503 - 506, 2009-04 |
| 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 |
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