Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Title
Showing results 2601 to 2620 of 10267
| Creep Behaviors of Alloy 617 in High Temperature Steam Environments Jang, Changheui; Donghoon Kim; Injin Sah; Jahyun Koo, NFSM 2012, American Nuclear Society, 2012-06-26 |
| Creep Behaviors of Nickel-Base Superalloys Alloy 617 and Haynes 230 at High Temperature Jang, Changheui, 2009 International Congress on Advances in Nuclear Power Plants, 2009-05-12 |
| Creep behaviour of advanced nuclear materials measured by the SPS system Faris, Sweidan; Ryu, Ho Jin, The Nuclear Materials Conference, NUMAT 2018, 2018-10-15 |
| Creep resistance of Alloy 617 in high temperature helium environments Jang, Changheui; Ho Jung Lee; Injin Sah; Jahyun Koo; Dae Jong Kim, Asia Pacific Conference on Fracture Strength-Machanical and materials 2012, Korean Society of Mechanical Engineering(KSME), 2012-05-14 |
| Creep-environment interactions of Alloy 617 at elevated temperature Kim, D.; Jang, Changheui; Ryu, W.S., ASME 2008 Pressure Vessels and Piping Conference, PVP2008, pp.1215 - 1220, 2008-07-27 |
| Criteria for near-surface disposal of wastes from peacer reactor Sung I.K.; Lee, Kun Jai, American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05, v.4, pp.2309 - 2317, 2005-05-15 |
| Critical Assessment of Transuranic Element Storage Facility with Wet Conditions: Monte Carlo Study 고길영; 김진환; 이민주; 김우섭; 안승규; 박세환; 조규성, 2018 한국원자력학회 춘계학술발표회, 한국원자력학회, 2018-05-17 |
| Critical conditions for pit initiation and growth of austenitic stainless steels Al Ameri, M.; Yi, Y.; Cho, P.; Al Saadi, S.; Jang, Chang-Heui; Beeley, P., CORROSION SCIENCE, v.92, pp.209 - 216, 2015-03 |
| Critical Flow Rates of Subcooled Water Through Short Pipes with Small Diameters Chun, Moon Hyun, Proc. of the 8th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), pp.759 - 766, 1997 |
| Critical heat flux and flow pattern for water flow in annular geometry Park, JW; Baek, WP; Chang, Soon-Heung, NUCLEAR ENGINEERING AND DESIGN, v.172, no.1-2, pp.137 - 155, 1997 |
| Critical heat flux and onset of nucleate boiling tests in a finned rod bundle Chae, HT; Park, JH; Kim, H; Chang, Soon-Heung, NUCLEAR TECHNOLOGY, v.148, no.3, pp.287 - 293, 2004-12 |
| Critical heat flux characteristic of magnetite-water nanofluid in pool boiling Lee, Jong Hyuk; Lee, Taeseung; Jeong, Yong Hoon, The 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8), Thermal Hydraulics Divisions of AESJ, KNS, 2012-12 |
| Critical Heat Flux during Flow Boiling Experiment with Surfactant Solutions Sarwar, Mohammad Sohail; Jeong, Yong Hoon; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2007-05-11 |
| CRITICAL HEAT FLUX ENHANCEMENT Chang, Soon-Heung; Jeong, Yong Hoon; Shin, Byung-Soo, NUCLEAR ENGINEERING AND TECHNOLOGY, v.38, no.8, pp.753 - 762, 2006-11 |
| Critical heat flux enhancement of nuclear fuel cladding with a nano-porous oxide film by anodization 유형석; 정용훈, 2018 한국원자력학회 춘계학술발표회, 한국원자력학회, 2018-05-18 |
| Critical heat flux enhancement of nuclear fuel cladding with nano-porous oxide film by surface anodization = 표면 양극산화법으로 제조된 나노 다공성 산화막을 가진 핵연료 피복관의 임계열유속 증진link Yu, Hyoung Suk; Jeong, Yong Hoon; et al, 한국과학기술원, 2018 |
| Critical Heat Flux Enhancement: Nano-fluids and Others Chang, Soon-Heung; Jeong, Yong Hoon, International Workshop on New Horizons in Nuclear Reactor Thermal Hydraulics, 2008-01-07 |
| Critical Heat Flux Experiments for In-Vessel Retention External Reactor Vessel Cooling Strategy using 2-D Slice Test Section Park, Hae Min; Kim, Taeil; Heo, Sun; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, 2010-10-21 |
| Critical Heat Flux Experiments for In-Vessel Retention External Reactor Vessel Cooling Strategy using 2-D Slice Test Section Park, Hae Min; Kim, Taeil; Heo, Sun; Jeong, Yong Hoon, The 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8), 2010-10-12 |
| Critical Heat Flux Experiments for In-Vessel Retention External Reactor Vessel Cooling Strategy Using 2-D Slice Test Section Park, Hae Min; Kim, Taeil; Heo, Sun; Jeong, Yong Hoon, The 7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7), 2010-11-17 |
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