Showing results 228 to 263 of 263
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 |
The high temperature oxidation behaviors of several nickel base superalloys Daejin, L.; Sanggyu, L.; Jang, Changheui, 2006 Winter Meeting of the American Nuclear Society, pp.105 - 106, 2006-11-12 |
The influence of cooling rate from annealing temperature on the microstructure of Haynes 230 Sah, Injin; Hong, Sunghoon; Jang, Changheui, SMINS-3, Neclear Energy Agency (NEA), 2013-10-07 |
Thermal Aging Embrittlement of High Chromium Oxide Dispersion Strengthening Steels Lee, J.S; Kim, In Sup; Jang, Changheui; Kimura, A.; Kim, B.G.; Choo, KN; Choo, Y.S; et al, 한국원자력학회 2005년도 춘계학술발표회, pp.471 - 472, 한국원자력학회, 2005-05-26 |
Thermal Aging Embrittlement of High Cr Oxide Dispersion Strengthened Steels Jang, Changheui; Kim, In Sup; Lee, J.S.; Kimura, A., ICFRM-12, 2005-12-07 |
THERMAL PERFORMANCE OF MULTILAYER PVD TUNGSTEN COATING FOR THE FIRST WALL APPLICATION IN NUCLEAR FUSION DEVICES Kim, Hyunmyung; Lee, Ho Jung; Jang, Changheui, FUSION SCIENCE AND TECHNOLOGY, v.68, no.2, pp.378 - 382, 2015-09 |
Thermo-mechanical stability of nano-sized NbC precipitates dispersed in austenitic stainless steel = 오스테나이트계 스테인리스강에 분산된 나노 크기의 NbC 석출물의 열-역학적 안정성link Eom, Hyun Joon; Jang, Changheui; et al, 한국과학기술원, 2023 |
Treatment of the thermal-hydraulic uncertainties in the pressurized thermal shock analysis Jang, Changheui, NUCLEAR ENGINEERING AND DESIGN, v.237, no.2, pp.143 - 152, 2007-01 |
Tritium inventory prediction in a CANDU plant Song, MJ; Son, SH; Jang, Changheui, WASTE MANAGEMENT, v.15, no.8, pp.593 - 598, 1995 |
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