| 314 | 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 |
| 315 | QUANTITATIVE-EVALUATION OF SWELLING OR SHRINKING LEVEL CONTRIBUTIONS IN STEAM-GENERATORS USING SPECTRUM ANALYSIS NA, MG; No, Hee Cheon, ANNALS OF NUCLEAR ENERGY, v.20, no.10, pp.659 - 666, 1993-10 |
| 316 | Reevaluation of safety criteria of Zircaloy oxidation embrittlement for improvement of safety margin under accident conditions = 사고 시 안전여유도 증대를 위한 지르칼로이 산화 취화 관련 안전 기준의 재평가link Kim, Bokyung; No, Hee Cheon; et al, 한국과학기술원, 2017 |
| 317 | REGULATORY ISSUES ON THE SAFETY DISTANCE BETWEEN A VHTR AND A H-2 PRODUCTION FACILITY AND AN OVERPRESSURE PREDICTION USING CORRELATIONS AND A CFD ANALYSIS FOR THE JAEA EXPLOSION TEST IN AN OPEN SPACE Kang, Hyung Seok; Kim, Sang Baik; Kim, Min-Hwan; Lee, Won-Jae; No, Hee Cheon, NUCLEAR TECHNOLOGY, v.166, no.1, pp.86 - 100, 2009-04 |
| 318 | 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 |
| 319 | Reply to the letter to the editor: A new three-dimensional finite element analysis model of high-speed train-bridge interactions Song, MK; No, Hee Cheon, ENGINEERING STRUCTURES, v.26, no.11, pp.1659 - 1660, 2004-09 |
| 320 | Safety Analysis of VHTRs with MED Desalination Plants No, Hee Cheon; Kim, Ho Sik; Jin, Hyung Gon, American Nuclear Society, v.104, 2011-06 |
| 321 | 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 |
| 322 | 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 |
| 323 | Scaling and parametric studies of condensation oscillation in an in-containment refueling water storage tank Lee, JH; No, Hee Cheon, NUCLEAR SCIENCE AND ENGINEERING, v.144, no.1, pp.74 - 85, 2003-05 |
| 324 | Scaling Methodology for a single spent fuel assembly No, Hee Cheon; Yoo, Seung Hun; Kim, Hyeun Min, 한국원자력학회 춘계발표회, 한국원자력학회, 2007 |
| 325 | Scaling Methodology for a single spent fuel assembly No, Hee Cheon, KNS 2007 Spring |
| 326 | 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 |
| 327 | SCALING STUDY OF IN-CORE BOIL-OFF AND HEATING PROCESS No, Hee Cheon; ISHII, M, NUCLEAR ENGINEERING AND DESIGN, v.143, no.2-3, pp.265 - 283, 1993-09 |
| 328 | Second-order model for free surface convection and interface reconstruction Kim, SO; No, Hee Cheon, INTERNATIONAL JOURNAL FOR NUMERICAL METHODS IN FLUIDS, v.26, no.1, pp.79 - 100, 1998-01 |
| 329 | Simulation works with a 1/7 scaled-down DVI experimental facility using TRAC-P No, Hee Cheon; Lee, Sang Ik, 한국원자력학회 춘계발표회, 한국원자력학회, 2002 |
| 330 | 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 |
| 331 | Simultaneous visualization of dry spots and bubbles for pool boiling of R-113 on a horizontal heater Chung, HJ; No, Hee Cheon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.46, no.12, pp.2239 - 2251, 2003-06 |
| 332 | Size effect of nanometer vacuum gap thermionic power conversion device with CsI coated graphite electrodes Lee, JeongIk; Jeong, Yong Hoon; No, Hee Cheon; Hannebauer, Rob; Yoo, Sang-Keun, APPLIED PHYSICS LETTERS, v.95, no.22, 2009-11 |
| 333 | 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 |
| 334 | SODIUM-CO2 INTERACTION IN A SUPERCRITICAL CO2 POWER CONVERSION SYSTEM COUPLED WITH A SODIUM FAST REACTOR Eoh, Jae-Hyuk; No, Hee Cheon; Yoo, Yong-Hwan; Kim, Seong-O, NUCLEAR TECHNOLOGY, v.173, no.2, pp.99 - 114, 2011-02 |
| 335 | 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 |
| 336 | Special issue on the 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics Foreword No, Hee Cheon; Merzari, Elia, NUCLEAR ENGINEERING AND DESIGN, v.312, pp.1 - 1, 2017-02 |
| 337 | Stability of nickel catalyst supported by mesoporous alumina for hydrogen iodide decomposition and hybrid decomposer development in sulfur-iodine hydrogen production cycle Choi, Jinyoung; No, Hee Cheon; Kim, Young Soo, INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, v.39, no.8, pp.3606 - 3616, 2014-03 |
| 338 | 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 |
| 339 | Step-by-Step Integral Scaling Method No, Hee Cheon; Ishii, M, 한국원자력학회 춘계발표회, 한국원자력학회, 1991 |
| 340 | 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 |
| 341 | STEPWISE INTEGRAL SCALING METHOD FOR SEVERE ACCIDENT ANALYSIS AND ITS APPLICATION TO CORIUM DISPERSION IN DIRECT CONTAINMENT HEATING ISHII, M; ZHANG, G; No, Hee Cheon; ELTWILA, F, NUCLEAR ENGINEERING AND DESIGN, v.151, no.1, pp.223 - 234, 1994-11 |
| 342 | 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 |
| 343 | Strength Degradation of Oxidized Graphite Support Column in VHTR Park, Byung Ha; No, Hee Cheon, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.47, no.11, pp.998 - 1004, 2010-11 |
| 344 | 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 |
| 345 | Studies of Water Packing Phenomenon in Safety Analysis Code No, Hee Cheon, Third Intl. Topical Meeting on Reactor Thermal Hydraulics, 1985 |
| 346 | Study of the RETRAN Code for Upper Plenum Analysis in Small LOCA No, Hee Cheon, NUCLEAR ENGINEERING AND TECHNOLOGY , v.16, no.3, pp.125 - 130, 1984-01 |
| 347 | Study on oxidation model at high temperature under DEC using SPACE = SPACE코드를 이용한 설계확장조건에서의 고온산화모델 연구link Lee, Dong-Kyu; No, Hee Cheon; et al, 한국과학기술원, 2018 |
| 348 | Subcooled water critical pressure and critical flow rate in a safety valve Kim, SW; No, Hee Cheon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.44, no.24, pp.4567 - 4577, 2001-12 |
| 349 | 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 |
| 350 | 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 |
| 351 | The Effect of Direct Contract Condensation on Passive Gravity Injection No, Hee Cheon; Lee, Sang Il, 한국원자력학회 춘계발표회, pp.435 - 440, 1995 |
| 352 | The Effect of Entrance and Exit Geometry on Flooding Phenomena No, Hee Cheon; Jeong, Ji Hwan, 한국원자력학회 춘계발표회, pp.429 - 434, 1995 |
| 353 | 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 |
| 354 | 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 |
| 355 | 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 |
| 356 | 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 |
| 357 | 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 |
| 358 | 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 |
| 359 | 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 |
| 360 | 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 |
| 361 | Thermal Hydraulic Performance of the Printed Circuit Heat Exchanger in a Helium Test Loop No, Hee Cheon, Nthas6 2008 |
| 362 | 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 |
| 363 | 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 |
| 364 | Thermal-hydraulic characteristics of the Printed Circuit Heat Exchanger (PCHE) in a Helium-Water Test Loop No, Hee Cheon, the KNS Autumn Meeting |
| 365 | 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 |
| 366 | 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 |
| 367 | 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 |
| 368 | Throughflow Analysis by Newton-raphson Method for Axial Flow Gas Turbines No, Hee Cheon; Kim, Ji Hwan; Kim, Hyeun Min, 한국원자력학회 추계발표회, 한국원자력학회, 2004 |
| 369 | 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 |
| 370 | 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 |
| 371 | Turbulent film condensation of high pressure steam in a vertical tue No, Hee Cheon; Kim, Sang Jae, Korea Thermal Engineering Conference Autumn Meeting, 1999 |
| 372 | 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 |
| 373 | Validation of GAMMA-3D Using Inverse U-tube and HTTR-Simulated Air Ingress Experiments No, Hee Cheon; Lim, Hong Sik, 한국원자력학회 춘계발표회, 한국원자력학회, 2004 |
