Showing results 2301 to 2320 of 5619
Experiment on ELM mitigation control with SMBI and RMP in KSTAR Lee, HY; Hahn, SH; Lee, JH; Ko, WH; Juhn, JW; Han, H; Yoon, SW; et al, 42nd European Physical Society Conference on Plasma Physics, European Physical Society, 2015-06-22 |
Experiment on Pool and Flow Boiling CHF for the SiC Surfaces under Atmospheric Condition Kam, Dong Hoon; Lee, Jong Hyuk; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2013-10-25 |
Experiment Study of the chracteristics of pool boiling CHF enhancement using water-based magnetic fluid Lee, Taeseung; Jeong, Yong Hoon, 한국원자력학회 2011년도 춘계학술대회 (Korean Nuclear Society Spring Meeting), 한국원자력학회, 2011-05-25 |
Experiment Study on the Magnetic Field Effect of Pool Boiling CHF Enhancement in Water-based Magnetic Fluid with Lower Concentration Lee, Jong Hyuk; Jeong, Yong Hoon, International Congress on Advances in Nuclear Power Plants(ICAPP '11), SFEN,AESJ,ANS,KNS, 2011-05-02 |
Experimental Analysis of Specification Language Impact on NPP Software Diversity Yoo, Chang Sik; Seong, Poong-Hyun, 한국원자력학회 '98 추계 학술발표회, pp.76 - 76, 한국원자력학회, 1998-10 |
Experimental analysis of the flow behavior in the safety injection tank of APR1400 Jeong, Woon Ho; Jeong, Yong Hoon, 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, Association for Computing Machinery, Inc, 2017-09-07 |
Experimental analysis of the flow in the vortex chamber of the safety injection tank for APR1400 Jeong, Woonho; Jeong, Yong Hoon, The Ninth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS10), Thermal Hydraulics Divisions of AESJ, KNS, 2016-11-28 |
Experimental and Analytical Study on the Simulation of Pool Boiling CHF Based on Macrolayer Dryout Model Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2001-05-24 |
Experimental and CFD analysis of condensation with non-condensable gas in multi-tubes Kim, Do Yun; No, Hee-Cheon; Jeon, Byong Guk, ANS2016, ANS2016, 2016-11-10 |
Experimental and CFD Analysis of Printed Circuit Heat Exchanger for Supercritical CO2 Power Cycle Application Baik, Seung Joon; Kim, Hyeon Tae; Kim, Seong Gu; Lee, Je Kyoung; Lee, Jeong Ik, The Korean Nuclear Society Autumn Meeting (2015), The Korean Nuclear Society, 2015-10-29 |
Experimental and computational analysis of gas natural circulation loop Lee, JeongIk; Hejzlar,P, International Congress on Advances in Nuclear Power Plants (ICAPP 2007), French Nuclear Energy Society, 2007-05-14 |
Experimental and Numerical Analysis of S-CO2 Critical Flow for SFR Recovery System Design Kim, Mim Seok; Jung, Hwa Young; Ahn, Yoonhan; Lee, Jekyoung; Lee, Jeong Ik, The Korean Nuclear Society Spring Meeting(2016), The Korean Nuclear Society, 2016-05 |
Experimental and Numerical Investigations on S-CO2 Critical Flow with Implications in Turbomachinery Seal Design Kim, Min Seok; Jung, Hwa-Young; Ahn, Yoonhan; Lee, Jekyoung; Lee, Jeong-Ik, The 9th National Congress of Fluids Engineering, 한국가시화정보학회, 2016-08-10 |
Experimental and Numerical Studies of Supercritical CO2 Test Loop with GAMMA code Bae, Seong Jun; Oh, Bongseong; Ahn, Yoonhan; Lee, Jeong-Ik, NUTHOS-11: The 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety(2016), American Nuclear Society, 2016-10-09 |
EXPERIMENTAL AND NUMERICAL STUDY OF CRITICAL FLOW MODEL DEVELOPMENT FOR SUPERCRITICAL CO2 POWER CYCLE APPLICATION KIM, MINSEOK; Oh, Bong-seong; Jung, Hwa-Young; Bae, Seong Jun; Lee, Jeong-Ik, ASME Turbo Expo 2018: Turbomachinery Technical Conference and Exposition, ASME, 2018-06-13 |
Experimental and Numerical Study of Supercritical CO₂ Test Loop Transient Conditions Bae, Seong Jun; Oh, Bongseong; Ahn, Yoonhan; Baik, Seungjoon; Lee, Jekyoung; Lee, Jeong-Ik, The First Pacific Rim Thermal Engineering Conference(2016), American Society of Thermal and Fluids Engineers, 2016-03-13 |
Experimental Approach to Effect Estimation of Decision Support Systems 이승준; 성풍현, 한국원자력학회 2007 춘계학술발표대회, 한국원자력학회, 2007-05-10 |
Experimental Approaches on Flow Accelerated Corrosion Behavior of CANDU Feeder Piping Kim, In Sup, The 4th International Workshop on the Integrity of Nuclear Components, 2002 |
Experimental Assessment of Critical Heat Flux for the Real Condition of IVR-ERVC Strategy Park, Hae Min; Jung, Jun Yeong; Jeong, Yong Hoon, The 11th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-11), Korean Nuclear Society and American Nuclear Society, 2016-10-12 |
Experimental CHF Study on the Effect of Heater Material and Coolant Additives for the Top of the Reactor Vessel Lower Head Park, Hae Min; Jeong, Yong Hoon, 2013 International Congress on Advances in Nuclear Power Plants, Korean Nuclear Society, 2013-04-16 |
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