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

Showing results 242 to 263 of 263

242
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

243
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

244
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

245
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

246
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

247
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

248
The Effect of Reference Flaw Size on P-T Limit Curves for Pressurized Water Reactor

Jang, Changheui, PVP 2000, 2000-07-25

249
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

250
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

251
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

252
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

253
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

254
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

255
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

256
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

257
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

258
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

259
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

260
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

261
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

262
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

263
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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