Browse by Author No, Hee Cheon
Showing results 350 to 380 of 380
| 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 |
| The Effect of Direct Contract Condensation on Passive Gravity Injection No, Hee Cheon; Lee, Sang Il, 한국원자력학회 춘계발표회, pp.435 - 440, 1995 |
| The Effect of Entrance and Exit Geometry on Flooding Phenomena No, Hee Cheon; Jeong, Ji Hwan, 한국원자력학회 춘계발표회, pp.429 - 434, 1995 |
| 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 |
| The experiment of an inclined single-tube condensation for Passive Auxiliary Feedwater System of APR+ No, Hee Cheon; Chang Wook Shin; Bong Yo Yun; Byong Guk Jeon, 2013 ANS winter meeting, 2013 ANS winter meeting, 2013-11-13 |
| The experimental investigation of tube's diameter and inclination angle in a separate effect PAFS test facility for APR Shin, Chang Wook; No, Hee Cheon; Yun, Bong Yo; Jeon, Byong Guk, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.86, pp.914 - 922, 2015-07 |
| 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 |
| The implementation of a three-field model into TRAC-M/F90 and its application to annular-mist flow Lee, SI; No, Hee Cheon, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.43, no.1, pp.88 - 97, 2006-01 |
| Thermal coupling of HTGRs and MED desalination plants, and its performance and cost analysis for nuclear desalination Kim, Ho Sik; No, Hee Cheon, DESALINATION, v.303, pp.17 - 22, 2012-10 |
| 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 |
| Thermal hydraulic behavior in the deteriorated turbulent heat transfer regime for a gas-cooled reactor Kim, Hyeonil; Lee, JeongIk; No, Hee Cheon, NUCLEAR ENGINEERING AND DESIGN, v.240, no.4, pp.783 - 795, 2010-04 |
| Thermal Hydraulic Performance of the Printed Circuit Heat Exchanger in a Helium Test Loop No, Hee Cheon, Nthas6 2008 |
| 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 |
| 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 |
| Thermal-hydraulic characteristics of the Printed Circuit Heat Exchanger (PCHE) in a Helium-Water Test Loop No, Hee Cheon, the KNS Autumn Meeting |
Thermal-hydraulic study of air-cooled passive decay heat removal system for APR plus under extended station blackout Kim, Do Yun; No, Hee Cheon; Yoon, Ho Joon; Lim, Sang Gyu, NUCLEAR ENGINEERING AND TECHNOLOGY, v.51, no.1, pp.60 - 72, 2019-02 |
| 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 |
| 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 |
| Throughflow Analysis by Newton-raphson Method for Axial Flow Gas Turbines No, Hee Cheon; Kim, Ji Hwan; Kim, Hyeun Min, 한국원자력학회 추계발표회, 한국원자력학회, 2004 |
| 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 |
| Turbulent film condensation of high pressure steam in a vertical tube Kim, SJ; No, Hee Cheon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.43, no.21, pp.4031 - 4042, 2000-11 |
| Turbulent film condensation of high pressure steam in a vertical tue No, Hee Cheon; Kim, Sang Jae, Korea Thermal Engineering Conference Autumn Meeting, 1999 |
| 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 |
| Validation of GAMMA-3D Using Inverse U-tube and HTTR-Simulated Air Ingress Experiments No, Hee Cheon; Lim, Hong Sik, 한국원자력학회 춘계발표회, 한국원자력학회, 2004 |
| Very High Temperature Gas-cooled Reactors: Progress and Challenges No, Hee Cheon, ICAPP'05 |
| 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 |
| VIBRATION MONITORING OF CORE SUPPORT BARREL BY NOISE AND STRUCTURAL-ANALYSIS IN ULJIN NUCLEAR-PLANT YUN, WY; KOH, BJ; No, Hee Cheon, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.27, no.11, pp.1058 - 1064, 1990-11 |
| Visualization of boiling structure and critical heat flux phenomenon for a narrow heating surface in a horizontal pool of saturated water Chu, In-Cheol; No, Hee Cheon; Song, Chul-Hwa, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.62, pp.142 - 152, 2013-07 |
| WALL HEAT-TRANSFER COEFFICIENT FOR CONDENSATION AND BOILING IN FORCED-CONVECTION OF SODIUM No, Hee Cheon; KAZIMI, MS, NUCLEAR SCIENCE AND ENGINEERING, v.81, no.3, pp.319 - 324, 1982 |
| Wastage and Self-Plugging by a Potential CO2 Ingress in a Supercritical CO2 Power Conversion System of an SFR Eoh, Jae-Hyuk; No, Hee Cheon; Yoo, Yong-Hwan; Jeong, Ji-Young; Kim, Jong-Man; Kim, Seong-O, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.47, no.11, pp.1023 - 1036, 2010-11 |
| 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 |
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Open Access
Date issued
- 32,945 2020 - 2024
- 100,062 2010 - 2019
- 75,675 2000 - 2009
- 44,727 1990 - 1999
- 14,360 1980 - 1989
- 62 1964 - 1969