Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Author Jang, Changheui

Showing results 178 to 237 of 262

178
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

179
Major components life evaluation for nuclear PLIM feasibility study

Jang, Changheui, 15th International Conference on Structural Mechanics in Reactor Technology, 1999-08-16

180
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

181
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

182
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

183
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

184
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

185
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

186
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

187
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

188
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

189
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

190
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

191
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

192
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

193
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

194
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

195
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

196
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

197
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

198
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

199
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

200
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

201
Oxidation behaviors of wrought Nickel-base superalloys in high temperature nuclear environments

Jang, Changheui, IUMRS 11th International Conference in Asia, 2010-09-28

202
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

203
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

204
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

205
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

206
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

207
Oxidation of Inconel alloy 617 at the Elevated Temperature Air Environment

Lee, Daejin; Lee, Sanggyu; Jang, Changheui, Korea Nuclear Society, Korea Nuclear Society, 2006

208
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

209
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

210
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

211
Plant Specific PTS Analysis of Kori Unit 1

Jang, Changheui, IAEA Specialist Meeting 1997, 1997-05-06

212
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

213
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

214
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

215
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

216
Pressurized Thermal Shock Evaluation of the Kori Unit 1 Nuclear Power Plant

Jang, Changheui, PVP 2000, 2000-07-24

217
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

218
Probabilistic Fracture Mechanics Application For Alloy 82/182 Welds In PWRs

Hong, Jong-Dae; Jang, Changheui, Pressure Vessels & Piping (PVP) 2010, 2010-07-20

219
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

220
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

221
Probabilistic Structural Integrity of Reactor Pressure Vessel under Pressurized Thermal Shock

Jang, Changheui, SMiRT-18, 2005-08-10

222
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

223
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

224
Role of Mechanical Factors in PWSCC of Stainless Steel

Cho, Pyungyeon; Yi, Yongsun; Zaki, Wael; Jang, Changheui, EUROCORR 2013, European Commission, 2013-09-01

225
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

226
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

227
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

228
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

229
Spatial Variation of Mechanical Properties in Alloy 82/182 Dissimilar Metal Welds

Jang, Changheui, 6th ASINCO, 2006-04-25

230
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

231
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

232
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

233
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

234
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

235
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

236
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

237
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

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