Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author 1266
Showing results 21 to 80 of 92
| Determination of the Initial RTNDT using Master Curve Technology and Implication to RPV Integrity Assessment for Life Extension Jang, Changheui, IAEA specialists Meeting on Master Curve Technology, 2001-09-18 |
| Development of a probabilistic fracture mechanics code for primary system pipes and application for RI-ISI Jang, Changheui; Datta, D.; Yang, J.-S., ASME 2008 Pressure Vessels and Piping Conference, PVP2008, pp.439 - 446, 2008-07-27 |
| Development of High Toughness Weld for Incoloy Alloy 908 Jang, Changheui, Advances on Cryogenic Engineering, 1994-07-15 |
| Diametral creep prediction of pressure tube using statistical regression methods Kim, D.; Lee, J.Y.; Na, M.G.; Jang, Changheui, 31st Annual Conference of the Canadian Nuclear Society and 34th CNS/CNA Student Conference 2010, pp.514 - 520, 2010-05-24 |
| Diffusion bonding of Ni-base superalloys for the application of VHTR intermediate heat exchanger Jang, Changheui; Injin Sah; Donghoon Kim, International Welding Joining Conference-Korea 2012, The Korean Welding and Joining Society, 2012-11-23 |
| Effect of Niobium content on hydride embrittlement of zirconium alloys Jang, Changheui, 2008 Water Reactor Fuel Performance Meeting(WRFPM), 2008-10-20 |
| Effects of Carburization and Decarburization on Mechanical Properties of Nickel-Base Superalloys Kim, D; Sah, I; Jang, Changheui, Proceeding of the 12th International Conference on Pressure Vessel Technology, 2009-09-22 |
| Effects Of Carburization and Decarburization On The Mechanical Properties Of Nickel-Base Superalloys For VHTR Applications Kim, D; Sah, I; Jang, Changheui, Structural Materials for Innovative Nuclear System(SMINS) -2, 2010-09-01 |
| Effects of hydrogen on the fatigue crack growth rate of low alloy steels Lee, S.G.; Jang, Changheui; Kim, I.S., American Nuclear Society Embedded Topical Meeting - 2006 International Congress on Advances in Nuclear Power Plants, ICAPP'06, pp.2124 - 2128, 2006-06-04 |
| Effects of Material Variability and Dissolved Hydrogen Content on LCF of 316LN Jang, Changheui, ICG-EAC 2010, 2010-04-13 |
| Environmental Fatigue Behaviors of Type 316LN Stainless Steels in Simulated PWR Water with Different Dissolved Hydrogen Contents Jang, Changheui, Proceeding of the 12th International Conference on Pressure Vessel Technology, 2009-09-22 |
| Environmental Fatigue Behaviors of Wrought and Cast Stainless Steels in 310oC Deoxygenated Water Cho, P; Jang, H; Jeong, I; Lee, J; Jang, Changheui, 2009 International Congress on Advances in Nuclear Power Plants, ICAPP 2009, 2009-05-12 |
| Environmental Fatigue Tests in the Deaerated High Temperature Water Jang, Changheui; Cho, Hyunchul; Jang, Hun; Kim, In Sup; Moon, Chan Kook, 2007 KEPIC Week, 2007 |
| Estimation of Pressure Tube Diametral Creep for CANDU Reactors Using Fuzzy Neural Networks Jang, Changheui, 6th International Topical Meeting on Nuclear Plant Instrumentation Control and Human Machine Interface Technology, 2009-04-07 |
| Evaluation Of Creep Resistance And Dynamic Recrystallization Of Alloy 617 At Elevated Temperatures Jang, Changheui, HTMTC Workshop on Mechanical Testing for Next Generation Nuclear Systems: Requirements, Testing Methodologies and Data Applications, 2008-04-17 |
| Evaluation of Fracture Toughness, Chemistry and Microstructural Factors of the Linde 80 WF-233 Weldment Jang, Changheui, IAEA specialists Meeting on Methodology and Supporting Research for Pressurized Thermal Shock Evaluation, 2000-07-19 |
| Evaluation of the Microstructure and Mechanical Properties of the Stainless Steel Narrow Gap Welds in Piping Jang, Changheui, World Conference on Safety of Oil and Gas Industry 2007 (WCOGI 2007), 2007-04-12 |
| 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 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 |
| Fracture Behaviors of Isotropic Nuclear Graphite Jang, Changheui, CARBON 2006, 2006-07-18 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| Leak Failure Analysis for Reactor Coolant Loop in a Nuclear Power Plant Jang, Changheui, 16th Pacific Basin Nuclear Conference (16PBNC), 2008-10-15 |
| 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 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 |
| 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 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 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 |
| 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 |
| Oxidation behaviors of wrought Nickel-base superalloys in high temperature nuclear environments Jang, Changheui, IUMRS 11th International Conference in Asia, 2010-09-28 |
| 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 of Inconel alloy 617 at the Elevated Temperature Air Environment Lee, Daejin; Lee, Sanggyu; Jang, Changheui, Korea Nuclear Society, Korea Nuclear Society, 2006 |
| Plant Specific PTS Analysis of Kori Unit 1 Jang, Changheui, IAEA Specialist Meeting 1997, 1997-05-06 |
| 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 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 Structural Integrity of Reactor Pressure Vessel under Pressurized Thermal Shock Jang, Changheui, SMiRT-18, 2005-08-10 |
| PWR 운전환경이 Alloy 690의 피로수명에 미치는 영향 장창희; 홍종대, 2012 KPVP Annual meeting, 한국압력기기공학회, 2012-11-23 |
| 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 |
| SA508 Gr.3 Cl2 저합금강 모재와 용접부의 290oC 순수 환경에서 피로균열거동 분석 장창희; 김정현; 홍종대; 나경환; 이재곤, 2012 한국부식방식학회 춘계학술대회, 사단법인 한국부식방식학회, 2012-05-18 |
| Spatial Variation of Mechanical Properties in Alloy 82/182 Dissimilar Metal Welds Jang, Changheui, 6th ASINCO, 2006-04-25 |
| Study on Low Cycle Fatigue Behavior of Type 316 Stainless Steel in a 310C Water Environment Jang, Changheui, International Conference on Water Chemistry of Nuclear Reactor Systems, 2006-10-24 |
| The effect of corrosion product on the corrosion resistance of the galvanized steel in NaCl solutions Jang, Changheui; Hong, S. M.; Lee, S. J.; Kim, J. M.; Lee, S. H., ISRSM2007, 2007 |
| The effect of material variability on low cycle fatigue resistance of low alloy steels in a 310oC deoxygenated water Jang, H.; Hong, J.-D.; Lee, J.G.; Jang, Changheui, 714th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009, v.2, pp.945 - 951, 2009-08-23 |
| The Effect of Reference Flaw Size on P-T Limit Curves for Pressurized Water Reactor Jang, Changheui, PVP 2000, 2000-07-25 |
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