| 184 | Quantitative Evaluation of Reverse Dynamic Effects in steam Generators Using Spectrum Analysis No, Hee Cheon; Na, Man Gyun, 한국원자력학회 춘계발표회, pp.403 - 408, 한국원자력학회, 1993 |
| 185 | Regulatory issues on the safety distance due to a gas explosion and an overpressure prediction by correlations for the JAEA explosion test in an open space Kang, H.S.; Kim, S.B.; Kim, M.-H.; Lee, W.-J.; No, Hee Cheon, 2007 International Topical Meeting on Safety and Technology of Nuclear Hydrogen Production, Control, and Management, pp.295 - 300, 2007-06-24 |
| 186 | Safety Analysis of VHTRs with MED Desalination Plants No Hee Cheon; Kim, Ho Sik; Jin, Hyung Gon, American Nuclear Society, 2010-06 |
| 187 | Safety Analysis of VHTRs with MED Desalination Plants No, Hee Cheon; Kim, Ho Sik; Jin, Hyung Gon, American Nuclear Society, v.104, 2011-06 |
| 188 | Scaling and Experimental Studies of Condensation Oscillation in Subcooled Water of the in-containment Refueling Water Storage Tank No, Hee Cheon; Lee, Jun Hyung, 한국원자력학회 춘계발표회, 한국원자력학회, 1999 |
| 189 | Scaling and parametric studies of condensation oscilation in an in-containment refueling water storage tank No, Hee Cheon; LEE, Jun Hyung, 한국원자력학회 추계발표회, 한국원자력학회, 2001 |
| 190 | Scaling Methodology for a single spent fuel assembly No, Hee Cheon; Yoo, Seung Hun; Kim, Hyeun Min, 한국원자력학회 춘계발표회, 한국원자력학회, 2007 |
| 191 | Scaling studies on spreading of molten corium in MARK-1 boiling water reactors No, Hee Cheon; Mamoru, Ishii, 27th National Heat Transfer Conference, v.87, no.283, pp.74 - 85, 1991-07-28 |
| 192 | Sigular Points and Hyperbolicity Breaking in Two-Phase Flow 노희천; 이재영, 한국원자력학회 추계발표회, 한국원자력학회, 1990 |
| 193 | Simulation works with a 1/7 scaled-down DVI experimental facility using TRAC-P No, Hee Cheon; Lee, Sang Ik, 한국원자력학회 춘계발표회, 한국원자력학회, 2002 |
| 194 | Simulation works with a 1/7 scaled-dwon DVI experimental facility using TRAP-P No, Hee Cheon; Lee, SI; Lee, DW, Proc. of the Int. Congress on Advanced Buclear Power Plant, 2002 |
| 195 | Single-tube condensation experiment in Passive Auxiliary Feedwater System of APR1400+ 노희천; 신창욱; 윤봉요; 전병국, 한국원자력학회 2012 춘계학술대회, 한국원자력학회, 2012-05 |
| 196 | Size measurements of droplets entrained in a stagnant bubbling liquid column No, Hee Cheon; Jeong, Hae Yong; Song, Chul Hwa; Chung, Moon Ki, 한국원자력학회 추계발표회, pp.254 - 259, 한국원자력학회, 1996 |
| 197 | Some Observations on the Structual Developments of Bubbly Flow : Channel Size Effects No, Hee Cheon; Song, CH; Chun, SY; Chung, MK, 한국원자력학회 추계발표회, pp.321 - 326, 한국원자력학회, 1995 |
| 198 | Statistical model to describe boiling phenomena for high heat flux nucleate boiling and critical heat flux No, Hee Cheon; Ha, Sang June, 한국원자력학회 추계발표회, 한국원자력학회, 1996 |
| 199 | Step-by-Step Integral Scaling Method No, Hee Cheon; Ishii, M, 한국원자력학회 춘계발표회, 한국원자력학회, 1991 |
| 200 | Stepwise Integral Scaling Method for Severe Accident analysis and its Application to Corium Dispersion in Direct Containment Heating No, Hee Cheon; Ishii, M.; Zhang, G, Sixth International Topical Mtg on Nuclear Reactor Thermal Hydraulics, 1993 |
| 201 | Stratified flow induced air-ingress accident assessment of GAMMA code Jin, H.G.; No, Hee Cheon; Kim, H.I., International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010, pp.1225 - 1233, 2010-06-13 |
| 202 | Structural Analysis of Surface-Modified Oxidation-Resistant Zirconium Alloy Cladding for Light Water Reactors 노희천; 이유호; 이정익, KNS Spring, KNS Spring, 2014-05-29 |
| 203 | Structural strength of oxidized graphite column during the air-ingress accident in VHTR Park, B.H.; No, Hee Cheon; Kim, E.S.; Oh, C.H., 2009 ANS Annual Meeting and Embedded Topical Meeting: Nuclear and Emerging Technologies for Space, NETS 2009, v.100, pp.473 - 474, 2009-06-14 |
| 204 | Studies of Virtual Mass 노희천, 한국원자력학회 추계학술발표회, 한국원자력학회, 1983 |
| 205 | Studies of Water Packing Phenomenon in Safety Analysis Code No, Hee Cheon, Third Intl. Topical Meeting on Reactor Thermal Hydraulics, 1985 |
| 206 | Study of the RETRAN Code for Upper Plenum Analyis in Very Small LOCA 노희천, 국내외 한국과학기술자 종합학술대회, 1984 |
| 207 | Sweep-out Phenomena in the Downcomer with DVI of APR1400 under LBLOCA No, Hee Cheon; Lee, DW, Proc. of the 17th KAIF/KNS Annual Conf., 2002 |
| 208 | The Effect of Bubble Flow Structures on the void Wave Propagations in a Large Diameter Pope No, Hee Cheon; Song, CH; Chung, MK, Proceedings of the International Confefence on Multiphase Flow, 1995 |
| 209 | The Effect of Direct Contract Condensation on Passive Gravity Injection No, Hee Cheon; Lee, Sang Il, 한국원자력학회 춘계발표회, pp.435 - 440, 1995 |
| 210 | The Effect of Entrance and Exit Geometry on Flooding Phenomena No, Hee Cheon; Jeong, Ji Hwan, 한국원자력학회 춘계발표회, pp.429 - 434, 1995 |
| 211 | The Effects on-Condensible Gas on the Critical Pressure Ratio and Critical Flow Rate in a Safety Valve No, Hee Cheon; Kim, Se Won, 한국원자력학회 춘계발표회, 한국원자력학회, 2001 |
| 212 | The implementation of 3-field modeling into TRAC-M/F90 Lee, S.I.; No, Hee Cheon, 2005 Annual Meeting - American Nuclear Society, v.92, pp.444 - 445, 2005-06-05 |
| 213 | Thermal coupling of HTGRs and MED desalination plants, and its performance and cost analysis for nuclear desalination Kim, Ho Sik; No, Hee Cheon, Barcelona 2012, 2012-04 |
| 214 | Thermal hydraulic analysis of a full_scope dry storage cask No Hee Cheon; Yoo, Seung Hun; Kim, Hyeun Min, ANS 2010 Winte, 2010 |
| 215 | Thermal-hydraulic characteristics evaluations of the printed circuit heat exchanger in a helium-water test loop Kim, I.H.; No, Hee Cheon, International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010, pp.1749 - 1757, 2010-06-13 |
| 216 | Thermal-hydraulic characteristics of the Printed Circuit Heat Exchanger (PCHE) in a Helium-Water Test Loop No, Hee Cheon; Kim, In Hun, 한국원자력학회 추계발표회, 한국원자력학회, 2009 |
| 217 | Thermal-hydraulic evaluation of passive containment cooling system of improved APR+ during LOCAs 노희천; 전병국, KNS Spring, KNS Spring, 2014-05-29 |
| 218 | Thermal-Hydraulic Performance Tests of PCHE Using Mixture-Gas for HTGRs No Hee Cheon; Kim, In Hun, American Nuclear Society, 2011-06 |
| 219 | Three-Dimensional Two-Fluid Code for U-Tube Steam Generator Thermal Design Analysis No, Hee Cheon; Lee, Jae Young, Second Intl. Topical Meeting on Nuclear Power Plant Thermal-Hydraulics and Operations, 1986 |
| 220 | Throughflow analysis by Newton-Raphson method for axial flow gas turbines Kim, J.H.; Kim, H.M.; No, Hee Cheon, American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05, v.3, pp.1808 - 1813, 2005-05-15 |
| 221 | Throughflow Analysis by Newton-raphson Method for Axial Flow Gas Turbines No, Hee Cheon; Kim, Ji Hwan; Kim, Hyeun Min, 한국원자력학회 추계발표회, 한국원자력학회, 2004 |
| 222 | Thumal-Hydraulic Analysis of the Containment for Design of Passive Containment Cooling System 노희천; 박종하, 한국원자력학회 추계발표회, 한국원자력학회, 1991 |
| 223 | TRANSIENT ANALYSIS OF A HYDROGEN-DESALINATION COGENERATION NUCLEAR POWER PLANT : ACCIDENT SCENARIOS WITHIN THE HYDROGEN PRODUCTION PLANT No Hee Cheon; Jin, Hyung Gon; Kim, Young Soo; Kim, Ho Sik, NURETH-14, 2011-09 |
| 224 | Transient Analysis of a Hydrogen-Desalination Cogeneration Power Plant Overcooling Undercooling Accident Scenarios No Hee Cheon; Jin, Hyung Gon; Kim, Young Soo; Kim, Ho Sik, ICANSE-2011, 2011-11 |
| 225 | Transient Multicomponent Mixture Analysis Based on an ICE Numerical Scheme for Predicting an Air Ingress Phenomena in a HTGR No, Hee Cheon; Lim, HS, NURETH10, 2003 |
| 226 | Turbulent film condensation of high pressure steam in a vertical tue No, Hee Cheon; Kim, Sang Jae, Korea Thermal Engineering Conference Autumn Meeting, 1999 |
| 227 | Validation Experiments and code development for passive safety systems of CP-1300 No, Hee Cheon, Proc. of the Int. Conf. on Future Nuclear Systems, GLOBAL '99, 1999 |
| 228 | Validation of GAMMA-3D Using Inverse U-tube and HTTR-Simulated Air Ingress Experiments No, Hee Cheon; Lim, Hong Sik, 한국원자력학회 춘계발표회, 한국원자력학회, 2004 |
| 229 | Very High Temperature Gas-cooled Reactors: Progress and Challenges No, Hee Cheon, ICAPP'05 |
| 230 | Very-high-temperature gas-cooled reactors: Progress and challenges No, Hee Cheon; Oh, C.H.; Kim, J.H.; Park, G.-C.; Lee, J.C.; Martin, W.R.; Lim, H.S.; et al, American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05, v.2, pp.748 - 758, 2005-05-15 |
| 231 | Visualization of Droplet Breakup with Unquenched Spacer Grid During Reflood Phase of APR1400 No Hee Cheon; Lee, Eo Hwak; Song, Chul-Hwa; Shin, Chang Wook, ANS2010, 2010-11 |
| 232 | Water Accumulation and Countercurrent Flow Limitation in the Upper Plenum with a Multi-Hole Plate No, Hee Cheon; Lee, K.W., Int. Topical Meeting on Nuclear Reactor TH, Operation and Safety, 2004 |
| 233 | 수직관 벽면을 통한 열유속 측정 및 보정 방법 노희천; 주인철; 전문헌; 성창경; 김성호, 한국원자력학회 추계발표회, 한국원자력학회, 1999 |
