Browse "NE-Conference Papers(학술회의논문)" by Author 240
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| De-entrainment Efficiency of Vertical Rods in the Upper Plenum No, Hee Cheon; Lee, Kyung-Won; Song, Chul-Hwa, KNS Spring Meeting, pp.543 - 544, Korean Nuclear Society, 2005-05-26 |
| De-entrainment Efficiency of Vertical Rods in the Upper Plenum No, Hee Cheon; Lee, Kyung-Won; Song, Chul-Hwa, 한국원자력학회 춘계발표회, 한국원자력학회, 2005 |
| De-entrainment of Droplets on a Staggered Array of Vertical Rods in th Upper Plenum No, Hee Cheon; Lee, Kyung-Won; Song, Sung-Chu; Song, Chul-Hwa, KNS Autumn Meeting, Korean Nuclear Society, 2005-10-27 |
| De-entrainment of Droplets on a Staggered Array of Vertical Rods in th Upper Plenum No, Hee Cheon; Lee, Kyung-Won; Song, Sung Chu; Song, Chul-Hwa, 한국원자력학회 추계발표회, 한국원자력학회, 2005 |
| Deposition Rate of Droplets in a Horizontal Pipe Lee, Kyung-Won; No, Hee Cheon; Song, Chul-Hwa, 한국원자력학회 춘계발표회, 한국원자력학회, 2006 |
| Depressurization Accident Analysis of MPBR by PBR_SIM with Chemical Reaction Model No, Hee Cheon; Kadak, A, C,, 한국원자력학회 춘계발표회, 한국원자력학회, 2002 |
| Design of Single-tube Condensation Experiment Facility for Passive Auxiliary Feedwater System of APR1400+ No Hee Cheon; Shin, Chang Wook; Yun, Bong Yo; Jeon, Byong Guk, ANS, 2011-10 |
| Design of Dedicated Nuclear Desalination System - Low pressure Inherent heat sink Nuclear Desalination plant (LIND) 노희천; 김호식; 조유권; 이정익; 정용훈; 조남진; 최진영, 한국원자력학회 추계발표회, 한국원자력학회, 2012-10 |
| Design of the intermediate heat exchanging-depressurizing loop Kim, Young Soo; No, Hee Cheon; Yoon, Ho Joon; Choi, Jin Young, 한국원자력학회 추계발표회, 한국원자력학회, 2010 |
| Desingn of Model Reference Adaptive Control System for Steam Genrators No, Hee Cheon; Na, Man Gyun, Proc. of Third Intl. Topical Meeting on Nuclear Power Plant thermal-Hydraulics and Operatins, 1988 |
| Development and Validation of 3-D Multi-component Mixture Analysis Tool (GAMMA) for Air Ingress in HTGRs No, Hee Cheon; Lim, H.S., International Topical Meeting on High Temperature Reactor Technology, 2004 |
| Development of 3-D muliticomponent Mixture Analysis (GAMMA) Code for Pebble-bed Safety Analysis in a HTGR No, Hee Cheon; Lim, Hong Sik, 한국원자력학회 춘계발표회, 한국원자력학회, 2004 |
| Development of a Compact Real-Time Simulator for Two-Loop PWR Plant, FISA-2/PC No, Hee Cheon; Jeong, Jae Jun, Proc. of Third Intl. Topical Meeting on Nuclear Power Plant Thermal-Hydraulics and Operations , 1988 |
| Development of a Scaling Methodology for a Spent Fuel Assembly No, Hee Cheon; Yoo, Seung Hun; Kim, Hyeun Min, 한국원자력학회 추계발표회, 한국원자력학회, 2007 |
| Development of a scaling methodology for a spent fuel assembly Yoo, S.H.; Kim, H.M.; No, Hee Cheon, 2007 Winter Meeting on International Conference on Making the Renaissance Real, pp.103 - 104, 2007-11-11 |
| Development of a Software for the Micro-Simulator for Ko-Ri Nuclear Power Plant Unit 2 No, Hee Cheon, Proc. of the 1992 SCS Eastern Simulation Multiconference, 1992 |
| Development of a Three-field Model for Two-phase Annular-mist Flow No, Hee Cheon; Lee, Sang-Ik, KNS Spring Meeting, Korean Nuclear Society, 2005-05-26 |
| Development of a Three-field Model for Two-phase Annular-mist Flow No, Hee Cheon; Lee, Sang Ik, 한국원자력학회 춘계발표회, 한국원자력학회, 2005 |
| Development of a Two-Fluid, Three-Dimensional Sodium Boiling Code, THERMIT-6s for LMFBR Accident Analysis 노희천, 한국원자력학회 춘계학술발표회, 한국원자력학회, 1983 |
| DEVELOPMENT OF CONCRETE ABLATION MODELS FOR GAMMA ASSESSMENT OF TOTAL RCCS FAILURE WITH AN AIR-INGRESS ACCIDENT IN HTGRS Yoon, Seung Hyun; No, Hee-Cheon; Park, Byung Ha, European Nuclear Conferece 2014 (ENC2014), European Nuclear Society, 2014-05-13 |
| Development of GAMMA code and evaluation for a very high temperature gas-cooled reactor Oh, C.; No, Hee Cheon; Lim, H.S.; Kim, E.S.; Kim, J.H., 2007 International Topical Meeting on Safety and Technology of Nuclear Hydrogen Production, Control, and Management, pp.277 - 286, 2007-06-24 |
| Development of the Microcomputer-basect Adaptive Control System for Steam Generator Level Control 노희천; 배병환, 한국원자력학회 추계학술발표회, 한국원자력학회, 1985 |
| Development of the Ultrasonic Method for Two-Phase Mixture Level Measurement No, Hee Cheon; Lee, DW, 2nd Japan-Korea Sym. on Nuclear thermal Hydraulics and Safety, 2000 |
| Development of the ultrasonic method for two-phase mixture level measurement No, Hee Cheon; Lee, Dong Won, 한국원자력학회 춘계발표회, 한국원자력학회, 1999 |
| Development of Throughflow Calculation Code for Axial Flow Compressors No, Hee Cheon; Kim, Ji-Hwan; Kim, Hyeun-Min, KNS Spring Meeting, pp.39 - 40, Korean Nuclear Society, 2005-05-26 |
| Development of Throughflow Calculation Code for Axial Flow Compressors No, Hee Cheon; Kim, Ji Hwan; Kim, Hyeun Min, 한국원자력학회 춘계발표회, 한국원자력학회, 2005 |
| Direct Numerical Technique of Mathematical Programming for Optimal Control of Xenon Oscillation in Load Following Operation 노희천; 윤명현, 한국원자력학회 추계학술발표회, 한국원자력학회, 1984 |
| Direct-contact condensation models of steam and a steam/air mixture in RELAP5/MOD3.2 for horizontally stratified subcooled flow No, Hee Cheon; Choi, KY; Kwon, TS, 2nd Japan-Korean Sym. on Nucl. Thermal Hydraulics and Safety, 2000 |
| Downcomer boiling during LBLOCA with direct vessel injection of APR1400 Lee, E.H.; No, Hee Cheon; Lee, D.W.; Song, C.-H., Fourteenth International Conference on Nuclear Engineering 2006, ICONE 14, 2006-07-17 |
| Droplet Breakup by Impacting upon Dry and Wet Spacer Grids during Reflood No, Hee Cheon; Park Byung Ha; Moon Sang Gi, NTAHS8, NTAHS8, 2012-12 |
| Droplet de-entrainment on vertical rods in air-droplet mixture flow Lee, K.-W.; No, Hee Cheon; Song, C.-H., 2005 Annual Meeting - American Nuclear Society, v.92, pp.485 - 486, 2005-06-05 |
| Dynamic Modelling and Optimum Level Controller Design for Steam Generators in PWRs 노희천; 서규원, 한국원자력학회 추계학술발표회, 한국원자력학회, 1984 |
| Dynamic Scaling Method for Testing the performance of the Water Level Controller of Nuclear Steam Generators No, Hee Cheon; Lee, Jae Yong, Proc. of Third Intl. topical Meeting on Nuclear Power Plant Thermal-Hydraulics and Operations, 1988 |
| ECC Water Bypass in the Downcomer with DVI of APR1400 under LBLOCA No, Hee Cheon; Lee, Dong Won, 한국원자력학회 춘계발표회, 한국원자력학회, 2002 |
| ECC Water bypass in the Downcomer with DVI of APR1400 under LBLOCA No, Hee Cheon; Lee, DW, Proc. of the Int. Conf. on the New Frontiers of Nuclear Technology, 2002 |
| ECC Water Film Spreading, ECC Water Bypass and Sweep-out Phenomena in the Downcomer with DVI of APR1400 under LBLOCA No, Hee Cheon; Lee, DW, Proc. of the Int. Congress on Advanced Nuclear Power Plant, 2002 |
| Effect of Heat Flux on Concentration Feactor in Crevices of Tube Support Plates of Nuclear Steam Generators 노희천; 신상운, 한국원자력학회 춘계학술발표회, 한국원자력학회, 1984 |
| Effect of Interfacial Drag Force on the Numerical Stability of the Two-Fluid Model 노희천; 이재영, 한국원자력학회 추계발표회, 한국원자력학회, 1988 |
| EFFECTS OF ONSET TIME OF NATURAL CIRCULATION ON SAFETY IN THE AIR-INGRESS ACCIDENT OF HTGRS No Hee Cheon; Jin, Hyung Gon, NTHAS7, 2010-11 |
| Estimation of graphite density and mechanical strength of VHTR during air-ingress accident Kim, E.S.; Oh, C.H.; No, Hee Cheon; Kim, B.J., 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12, 2007-09-30 |
| Evaluation of Fuel Performance in PWR After Cladding Defect 노희천; 송성일, 한국원자력학회 춘계학술발표회, 한국원자력학회, 1984 |
| Experiment and model development on the effect of burn-off for graphite oxidation Kim, E.S.; No, Hee Cheon, 2006 Annual Meeting - American Nuclear Society, pp.670 - 671, 2006-06-04 |
| Experiment and RELAP5 analysis for the downcomer boiling of APR1400 under LBLOCA Lee, D.W.; No, Hee Cheon; Lee, E.H.; Oh, S.J.; Song, C.-H., Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04, pp.1612 - 1617, 2004-06-13 |
| Experimental Studies of Bunsen section for over-azeotropic condition in I-S cycle Yoon, Ho Joon; No, Hee Cheon; Kim, Young Soo; Jin, Hyung Gon; Lee, Jeong-Ik; Lee, Byung Jin, 한국원자력학회 춘계발표회, 한국원자력학회, 2009 |
| Experimental Studies of Flooding in Nearly Horizontal Pipes No, Hee Cheon; Choi, Ki Yong, 한국원자력학회 춘계발표회, pp.107 - 113, 한국원자력학회, 1993 |
| Experimental study of liquid holdup in pressurizer in case of loss-of-residual heat removal during mid-loop operation No, Hee Cheon; MOON, Young Min, 한국원자력학회 추계발표회, 한국원자력학회, 2001 |
| Experimental Study on Fracture of Oxidized Support Column in VHTR No Hee Cheon; Park, Byung Ha, ANS, 2011-06 |
| Experimental study on the film spreading, sweep-out of ECC water in the downcomer with DVI under LBLOCA No, Hee Cheon; Lee, Dong Won, 한국원자력학회 추계발표회, 한국원자력학회, 2001 |
| Experimental Sutdies of Flooding in Nearly Horizontal Pipes No, Hee Cheon; Choi, KY, Proceedings of the International Confefence on Multiphase Flow, 1995 |
| Experimental validation of an optimal operating window of bunsen section in iodine-sulfur thermo-chemical water splitting cycle Yoon, H.J.; No, Hee Cheon; Kim, Y.S.; Jin, H.G., 2nd International Topical Meeting o`n Safety and Technology of Nuclear Hydrogen Production, Control, and Management 2010, pp.63 - 67, 2010-06-13 |
| Experiments on the onset of water accumulation and CCFL through a multi-hole plate in a vertical tank No, Hee Cheon; Lee, Kyung-Won; Song, Chul-Hwa, 한국원자력학회 춘계발표회, 한국원자력학회, 2004 |
| Failure of oxidized graphite support column in VHTR Park, B.H.; No, Hee Cheon, International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010, pp.342 - 349, 2010-06-13 |
| Flash distillation of overazeotropic HIx phase based on optimal Bunsen reaction in I-S cycle Yoon, H.J.; No, Hee Cheon; Kim, Y.S.; Jin, H.G., 2009 ANS Annual Meeting and Embedded Topical Meeting: Nuclear and Emerging Technologies for Space, NETS 2009, v.100, pp.722 -, 2009-06-14 |
| Fluent의 삼차원 LES 난류 모델을 이용한 가압 경수로 연료봉 다발에서 멱 스펙트럼 밀도의 해석 노희천; 김현민, 한국원자력학회 춘계발표회, 한국원자력학회, 2003 |
| Full_scale simulation of a dry storage cask by computational fluid dynamics No, Hee Cheon; Yoo, Seung Hun; Kim, Hyeun Min, 한국원자력학회 춘계발표회, 한국원자력학회, 2010 |
| GAMMA Air Ingress Analysis for a Pebble-Bed Gas-Cooled Reactor No, Hee Cheon; Lim, Hong-Sik, KNS Spring Meeting, Korean Nuclear Society, 2005-05-26 |
| GAMMA Air Ingress Analysis for a Pebble-Bed Gas-Cooled Reactor No, Hee Cheon; Lim, Hong Sik, 한국원자력학회 춘계발표회, 한국원자력학회, 2005 |
| GAMMA Validation with the HTTR RCCS Mockup Test for the Assesment of Decay Heat Removal of GCRs Under Accident Conditions No, Hee Cheon; Lim, Hong Sik, 한국원자력학회 추계발표회, 한국원자력학회, 2004 |
| Gravity injection experiments and direct contact condensation regime map for passive high-pressure injection system No, Hee Cheon; Lee, Sang Il, Proc. of the 5th International Topical Meeting on Nuclear Thermal Hydraulics, Operation,a nd safety, 1997 |
| Helium Hydraulic Tests in the Printed Circuit Heat Exchanger 노희천; Kim, In Hun; Lee, Cheol Shin, 한국원자력학회 춘계발표회, 한국원자력학회, 2008 |
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