Browse "NE-Conference Papers(학술회의논문)" by Title
Showing results 1381 to 1400 of 5619
| 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 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 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 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: 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 |
| Critical heat flux for downward flow boiling in a vertical narrow rectangular channel Lee, Juhyung; Daesung Jo; Heetaek Chae; Chang, Soon-Heung, 2013 ANS Winter Meeting and Technology Expo, American Nuclear Society, 2013-11-11 |
| Critical Heat flux for Natural-Circulation of Water Under Low Pressure Kim, YI; Chang, Soon-Heung, The 2nd International Conference on Multiphase Flow, pp.1 - 6, 1995 |
| Critical Heat Flux Measurement for downward facing flat plates (SUS 304, SA 508) under atmospheric and pool boiling conditions Kam, Dong Hoon; Park, Hae Min; Choi, Young Jae; Jeong, Yong Hoon, The Seventh China-Korea Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-7), Nuclear Power Institute of China, Korea Atomic Energy Research Institute, 2015-10-15 |
| Critical Heat Flux Measurement of SiC- and Cr-coated Plates, Bare Stainless Steel Plate and Zircaloy-4 Plate Under Atmospheric and Pool Boiling Conditions Kam, Dong Hoon; Lee, Jong Hyuk; Lee, Taeseung; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29 |
| Critical Heat Flux Measurement of SiC- and Cr-coated surfaces with reference surfaces for pool boiling and α-SiC tube for flow boiling under atmospheric conditions, Surface change of SiC-coated surface Kam, Dong Hoon; Jeong, Yong Hoon, International Workshop on Nuclear Safety and Severe Accident, The International Atomic Energy Agency, 2014-09-03 |
| Critical Heat Flux of Water in Vertical Round Tube at Low Pressure and Low Flow Conditions Kim, HC; Baek, WP; Chang, Soon-Heung, The 1st Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, 1998 |
| Critical Heat Flux of Water in Vertical Round Tubes at Low-Pressure and Low-Flow Conditions Park, JW; Kim, HC; Baek, WP; Chang, Soon-Heung, The 8th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, 1997 |
| Critical Pressure Ratio and Critical Flow Rate in a Safety Valve No, Hee Cheon; Kim, Se Won, 한국원자력학회 추계발표회, 한국원자력학회, 1999 |
| Critical 소프트웨어의 신뢰도 예측에 관한 연구 손한성; 성풍현, '94 추계학술발표회, pp.175 - 180, 1994-05 |
| Criticality Analysis for the Conceptual Spent Fuel Dry Storage with Burnup Credit Kim, Jong Woon; Cho, Nam-Zin; Lee, Sang-Jin; Jang, Hyun Kie, Proceedings of International Symposium on Radiation Safety Management, pp.619 - 628, 2007-11 |
| Criticality Calculation for Cluster Fuel Bundles Using Monte Carlo Generated Grey Dancoff Factor Kim, H.H; Cho, Nam-Zin, Proc. of the Korean Nuclear Society Spring Meeting, v.1, pp.17 -, 1999 |
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