Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author Jang, Changheui
Showing results 196 to 255 of 263
| 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 |
| Phase stability and thermal aging behavior in high-strength Fe-Ni-Cr-Al alloys = 고강도 Fe-Ni-Cr-Al 합금 내 상 안정성 및 열 시효 특성link Kim, Chaewon; 김채원; et al, 한국과학기술원, 2023 |
| 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 |
| Round robin analysis for probabilistic structural integrity of reactor pressure vessel under pressurized thermal shock Jhung, MJ; Jang, Changheui; Kim, SH; Choi, YH; Kim, HJ; Jung, S; Kim, JM; et al, JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY, v.19, no.2, pp.634 - 648, 2005-02 |
| Semiconducting properties of surface oxides formed on austenitic stainless steel Saadi, Sara Al; Yi, Yongsun; Cho, Pyungyeon; Jang, Changheui; Beeley, Philip, European Corrosion Congress, EUROCORR 2015, pp.575 - 584, Austrian Society for Metallurgy and Materials (ASMET), 2015-09 |
| Short communication: "Effect of Nb on the electrical resistivity of ZrO2 layer formed on Zr alloys" Kwon, Oh Hyun; Shin, Ji Ho; Jang, Changheui; Yoo, Jong-Sung; Kim, Ho-Sub; Kwon, Young-il; Kim, Hyun Gil, JOURNAL OF NUCLEAR MATERIALS, v.536, 2020-08 |
| Spatial Variation of Mechanical Properties in Alloy 82/182 Dissimilar Metal Welds Jang, Changheui, 6th ASINCO, 2006-04-25 |
| Stability and strengthening effect of aging induced-nanofeatures in d-ferrite in an austenitic stainless-steel weld Kong, Byeong Seo; Shin, Ji Ho; Jeong, Chaewon; Jang, Changheui; Kang, Sung-Sik, JOURNAL OF MATERIALS RESEARCH AND TECHNOLOGY-JMR&T, v.23, pp.4990 - 5003, 2023-03 |
| Strain-Rate Dependence of Tensile Behavior in Commercial-Grade Tungsten-Effect of Recrystallization Condition Kong, Byeong Seo; Shin, Ji Ho; An, Taejeong; Jang, Changheui; Kim, Hyoung Chan, MATERIALS, v.15, no.17, 2022-09 |
| Structural integrity assessment of reactor pressure vessels during pressurized thermal shock Jhung, Myung Jo; Kim, Seok Hun; Choi, Young Hwan; Jung, Sunggyu; Kim, Jong Min; Kim, Ji Ho; Kim, Jong Wook; et al, JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY, v.22, no.8, pp.1451 - 1459, 2008-08 |
| Structural Integrity of Reactor Pressure Vessel for Small Break Loss of Coolant Accident Jhung, Myung Jo; Choi, Young Hwan; Jang, Changheui, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.46, no.3, pp.310 - 315, 2009-03 |
| Study on Alloy 600/690 oxide layer characteristic with Dissolved Hydrogen Concentration Variation and Zinc Injection Yun, Eun-Sub; Lee, Sung-Ho; Lee, Jae-Gon; Yun, Jong-Il; Jang, Changheui, 2013 ISRSM, Korea Hydro & Nuclear Power Co., Ltd., 2013-11-06 |
| Study on corrosion behavior of a nano carbide advanced radiation resistant austenitic stainless steels (NC-ARES) = 조사저항성을 갖는 원자로 내부 구조물용 오스테니틱 스테인레스 부식 거동 연구link Shu, Meng; Jang, Changheui; et al, 한국과학기술원, 2021 |
| 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 |
| Study on Microstructure and Thermal Cycling Performance of the Plasma-sprayed YSZ Coating in Simulated Turbine Environment Muthu, S. M.; Arivarasu, M.; Jang, Changheui; Viknesh, S.; Reddy, K. Surya Prakash; Venkateshkannan, M.; Siddharth, V. D. Vishnu; et al, HIGH TEMPERATURE CORROSION OF MATERIALS, v.100, no.3-4, pp.227 - 250, 2023-10 |
| Supercritical-CO2 corrosion behavior of alumina- and chromia-forming heat resistant alloys with Ti Subramanian, Gokul Obulan; Kim, Sung Hwan; Chen, Junjie; Jang, Changheui, CORROSION SCIENCE, v.188, 2021-08 |
| Surface modification of austenitic stainless steel for corrosion resistance in high temperature supercritical-carbon dioxide environment Kim, Sung Hwan; Subramanian, Gokul Obulan; Kim, Chaewon; Jang, Changheui; Park, Keun Man, SURFACE & COATINGS TECHNOLOGY, v.349, pp.415 - 425, 2018-09 |
| Swelling resistance of an austenitic stainless steel with uniformly distributed nanosized NbC precipitates under heavy ion irradiation Shin, Ji Ho; Kong, Byeong Seo; Jeong, Chaewon; Eom, Hyun Joon; Jang, Changheui; AlMousa, Nouf; Woller, Kevin B.; et al, JOURNAL OF NUCLEAR MATERIALS, v.564, 2022-06 |
| The carburization behavior of alloy 800HT in high temperature supercritical-CO2 Subramanian, Gokul Obulan; Kim, Sung Hwan; Jang, Changheui, MATERIALS LETTERS, v.299, pp.130067, 2021-09 |
| The corrosion behaviour of alloy 690 tube in simulated PWR secondary water with the effect of solid diffusing hydrogen Chen, Junjie; Lu, Zhanpeng; Meng, Fanjiang; Xu, Xuelian; Xiao, Qian; Kim, Ho-Sub; Jang, Changheui, JOURNAL OF NUCLEAR MATERIALS, v.517, pp.179 - 191, 2019-04 |
| 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 flaw orientation on the integrity of PWR pressure vessel at the events of pressurized thermal shock Jang, Changheui; Jeong, IS; Hong, SY, NUCLEAR ENGINEERING AND DESIGN, v.197, no.3, pp.249 - 264, 2000-05 |
| 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 Post-Bond Heat Treatment on Tensile Property of Diffusion Bonded Austenitic Alloys Hong, Sunghoon; Kim, Sung Hwan; Jang, Changheui; Sah, Injin, TRANSACTIONS OF THE KOREAN SOCIETY OF MECHANICAL ENGINEERS A, v.39, no.12, pp.1221 - 1227, 2015-12 |
| The Effect of Reference Flaw Size on P-T Limit Curves for Pressurized Water Reactor Jang, Changheui, PVP 2000, 2000-07-25 |
| The Effect of the material variability on the fatigue life of low alloy steels in 310oC deoxygenated water Jang, Changheui, 2008 ICG-EAC Meeting, 2008-04-22 |
| The effect of zinc addition on corrosion behavior of stainless steels with different phases in simulated PWR primary water Park, Su Hyun; Lee, Hyeon Bae; Kim, Chaewon; Okonkwo, Bright O.; Jang, Changheui; Xiao, Qian, CORROSION SCIENCE, v.209, 2022-12 |
| The Effects of Dissolved Hydrogen Contents on the Low Cycle Fatigue Behaviors of a 316LN Stainless Steel in Simulated PWR Condition Jang, Changheui; Cho, Pyung-Yeon; Hong, Jong-Dae; Jang, Hun; Kim, Tae-Soon; Lee, Jae-Gon, Nuclear Plant Chemistry Conference 2010, 2010-10-05 |
| The effects of dissolved hydrogen on the corrosion behavior of Alloy 182 Cross Mark in simulated primary water Xu, Jian; Shoji, Tetsuo; Jang, Changheui, CORROSION SCIENCE, v.97, pp.115 - 125, 2015-05 |
| The effects of reversion heat treatment on the recovery of thermal aging embrittlement of CF8M cast stainless steels Jang, Hun; Hong, Sunghoon; Jang, Changheui; Lee, Jae Gon, MATERIALS & DESIGN, v.56, pp.517 - 521, 2014-04 |
| The effects of the stainless steel cladding in pressurized thermal shock evaluation Jang, Changheui; Kang, SC; Moonn, HR; Jeong, IS; Kim, TR, NUCLEAR ENGINEERING AND DESIGN, v.226, no.2, pp.127 - 140, 2003-12 |
| The estimation if critical RTNDT and probability of failure for PWR vessels Jang, Changheui, 15th International Conference on Structural Mechanics in Reactor Technology, 1999-08-17 |
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