| 1 | A Dry-Spot Model for the Prediction of Critical Heat Flux in Water Boiling in Bubbly Flow Regime No, Hee Cheon; Ha, Sang Jun, 한국원자력학회 추계발표회, pp.546 - 551, 한국원자력학회, 1997 |
| 2 | A Dry-Spot Model for Transition Boiling Heat Transfer in Pool Boiling No, Hee Cheon; Ha, SJ, Int. Conf. of 11th IHTC, 1998 |
| 3 | A dry-spot model of critical heat flux in pool and forced convection boiling No, Hee Cheon; Ha, SJ, 3rd Int. Conf. on Multiphase Flow, 1998 |
| 4 | A New Method for the Incorporation for Spectral Effects to One Group Nodal Simulator 노희천; 노재만; 박찬호, 한국원자력학회 추계학술발표회, 한국원자력학회, 1985 |
| 5 | A Non-Equilibrium Three-Region Model for Transient Analysis of PWR Pressurizer No, Hee Cheon; Baek, Seung Min, Second Intl. Topical Meeting on Nuclear Power Plant Thermal-Hydraulics and Operations, 1986 |
| 6 | A Non-Equilibrium Three-Region Model for Transient Analysis of PWR Pressurizer 노희천; 백승민, 한국원자력학회 추계발표회, 한국원자력학회, 1985 |
| 7 | A Nucleate Boiling Limitation Model for the Prediction of Pool Boiling CHF No, Hee Cheon; Chung, H.J.; Chun, S.Y.; Back, W.P., Int. Topical Meeting on Nuclear Reactor TH, Operation and Safety, 2004 |
| 8 | A review on the coupling of CFD code into system code in gas cooled reactor Kim, H.I; No, Hee Cheon, 한국원자력학회 춘계발표회, 한국원자력학회, 2008 |
| 9 | A Simple analytical Scaling Method for a Scaled-Down Test Facility Simulating SB-LOCA in a Passive PWR 노희천; 이상일, 한국원자력학회 춘계발표회, pp.437 - 446, 한국원자력학회, 1992 |
| 10 | A SIMULTANEOUS OBSERVATION OF BUBBLE GROWTH AND MICROLAYER BEHAVIOR FOR AN ISOLATED BOILING REGIME OF SATURATED WATER No Hee Cheon; Chu, In-Cheol; Song, Chul-Hwa, NURETH-14, 2011-09 |
| 11 | A two-phase mixture level in a vertical tank with largo pipe diameter Moon, Y.M.; No, Hee Cheon, American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05, v.5, pp.2767 - 2776, 2005-05-15 |
| 12 | A Two-Phase Water Level Traching Logic for the Reactor Safety Code 노희천; 정해용, 한국원자력학회 추계발표회, 1991 |
| 13 | A Two-Phase Water Level Tracking Logic for the Reactor Safety Code No, Hee Cheon, Fifth International Meeting on Reactor Thermal Hydraulics, 1992 |
| 14 | A two-stage scalin method with validation of scaling methodology for application to the SB-LOCA of a passive pressurized water reactor No, Hee Cheon; Lee, SI; Choi, HR, 4th Int. Conference on mUltiphase Flow, 2001 |
| 15 | Advanced Numerical Scheme for a Real Time Accident Simulator 노희천; 정동욱, 한국원자력학회 춘계학술발표회, 한국원자력학회, 1984 |
| 16 | An Analytical Method for Generating the Scaling Criteria of Core Uncovery and Heatup Processes 노희천; Ishii, M, 한국원자력학회 추계발표회, 한국원자력학회, 1990 |
| 17 | An Analytical Method for Generating the Scaling Criteria of Core Uncovery and Heatup Processes 노희천, 세계한민족 과학기술자 종합학술대회, 1985 |
| 18 | An Analytical Method for Generating the Scaling Criteria of Core Uncovery and Heatup Processes No, Hee Cheon; Ishii, M, ANS Proceedings, 1991 National Heat Transfer Conference, 1991 |
| 19 | An Estimation of ECC Bypass during the Reflood Phase of a Cold Keg Break LOCA in KNGR No, Hee Cheon; Park, Chan Eok; Lee, Sang Yong; Lee, Sang Il; Choi, Chul Jin; Kim, Snag Jae, 한국원자력학회 추계발표회, 한국원자력학회, 1999 |
| 20 | An experimental study and numerical simulation by RELAP5 for the Downcomer Boiling of APR1400 under LBLOCA No, Hee Cheon; Lee, Dong Won; Lee, Eu Hwak; Oh, Seung Jong; Song, Chul-Hwa, 한국원자력학회 춘계발표회, 한국원자력학회, 2004 |
| 21 | An experimental study of HI decomposition through adsorption-desorption process in the Sulfur-Iodine cycle No Hee Cheon; Choi, inyoung; Kim, Young Soo, ICAPP 2011, 2011-05 |
| 22 | An experimental study of HI decomposition through adsorption-desorption process in the Sulfur-Iodine cycle Choi, Jin Young; No, Hee Cheon; Kim, Young Soo, 한국원자력학회 추계발표회, 한국원자력학회, 2010 |
| 23 | An experimental study of high pressure steam condensation in a vertical tube of passive secondary condensation system No, Hee Cheon; Kim, SJ, Proc. of the 1st Korea-Japan Symposium on Nuclear thermal Hydraulics and Safety, pp.321 - 327, 1998 |
| 24 | An Experimental Study of Steam Condensation of an Isolation Condenser in the Presence of air in a Vertical Tube No, Hee Cheon; Park, Hyun Sik, 한국원자력학회 춘계발표회, 한국원자력학회, 1995 |
| 25 | An Experimental Study of Viscosity Effect on Flooding Phenomena 노희천; 정지환; 장순흥, 한국원자력학회 추계발표회, 한국원자력학회, 1990 |
| 26 | An Extended Numerical Calibration Method for an Electrochemical Probe in Thin Wavy Flow with Large Amplitude Waves No, Hee Cheon; Choi, Ki Yong, 한국원자력학회 춘계발표회, 한국원자력학회, 1998 |
| 27 | An Integral Response Scaling Method for a Scaled-Down Test Facility Simulating SB-LOCAs in a Passive PWR No, Hee Cheon; Lee, Sang Il, Sixth International Topical Mtg on Nuclear Reactor Thermal Hydraulics, 1993 |
| 28 | An Intellingent Controller of the Water Level of the PWR Steam Generator 노희천; 이재영, 한국원자력학회 추계발표회, 한국원자력학회, 1991 |
| 29 | Analysis of Experiments for in-tube steam condensation with noncondensable gas at low pressure using the RELAP5/MOD3.2 code modified with a non-iterative condensation model No, Hee Cheon; Park, HS; Kwon, TS; Bang, YS, 2nd Japan-Korea Sym. on Nuclear Thermal Hydaulics and Safety, 2000 |
| 30 | Analysis of Experiments for Vertical In-Tube Steam Condensation with Noncondensable Gases Using the Modified RELAP5/MOD3.2 Code No, Hee Cheon; Park, Hyun Sik, 한국원자력학회 춘계발표회, 한국원자력학회, 1999 |
| 31 | ANALYSIS OF POWER SPECTRUM DENSITY IN THE PWR FUEL ASSEMBLY USING THE 3-D LES TURBULENT MODEL OF FLUENT 6 No, Hee Cheon; Kim, Hyeun MIn, International Conference on Nuclear Engineering, 2004 |
| 32 | Analysis of power spectrum density in the PWR fuel assembly using the 3-D LES turbulent model of fluent 6 Kim, H.M.; No, Hee Cheon, 12th International Conference on Nuclear Engineering (ICONE12) - 2004, v.2, pp.295 - 304, 2004-04-25 |
| 33 | Analysis of system and economics for hydrogen production by HTES coupling with HTGR Jung, H.L.; No, Hee Cheon; Eung, S.K., 2006 Winter Meeting of the American Nuclear Society, pp.895 - 896, 2006-11-12 |
| 34 | Analysis of the Void Wave Propagations : Wave Number Independent Characteristicse No, Hee Cheon; Song, Chul Hwa; Chung, Moon Ki, Proc. of the 7th Int'l Met. on Nuclear Reactor Thermal-Hydraulics(NURETH-7), 1995 |
| 35 | Analytical and Experimental Studies of U-Tube Steam Generator in PWR in Natural Circulation, Pot-Boiling, and Tube-Uncovery Modes No, Hee Cheon; Sul, Y.S., International Conference on New Trends in Nuclear System Thermohydraulics, 1994 |
| 36 | Applicability of One-Dimensional Mechanistic Post-Dryout Prediction Model No, Hee Cheon; Jeong, Hae Yong, 한국원자력학회 춘계발표회, pp.586 - 591, 한국원자력학회, 1996 |
| 37 | Application of ultrasonic sensor technique to measurement of water film thickness in the condenser tubes of passive auxiliary feedwater system for APR1400+ No Hee Cheon; Jeon, Byong Guk; Shin, Chang Wook; Yun, Bong Yo, ANS, 2011-10 |
| 38 | Application of an Integral Scaling Methodology to an Off-take Phenomenon at the Pressurizer Surge Line and its Validation Using RELAP5/MOD3.2 No, Hee Cheon; Kim, Hyoung Tae, 한국원자력학회 추계발표회, 한국원자력학회, 1999 |
| 39 | Assesment and Improvement of Condensation Models in RELAP5/MOD3.2 No, Hee Cheon; Choi, Ki Yong; Park, Hyun Sik; Kim, Sang Jae, 한국원자력학회 추계발표회, pp.585 - 590, 한국원자력학회, 1997 |
| 40 | Assessement of HTGR He Compressor Analysis Tool based on Newton-Raphson Numerical Application to Throughflow Analysis No, Hee Cheon; Kim, JH; Kim, HM, ICONE14 Int. Conf. on Nuclear Eng., 2006 |
| 41 | Assessment and improvement of direct-contact condensation models with/without noncondensible gases in RELAP5/MOD3.2 No, Hee Cheon; Choi, KY; Bang, YS, 3rd ASME/JSME Joint Fluids Engineering Conference, 1999 |
| 42 | Assessment of an ultrasonic sensor and a capacitance probe for measurement of two-phase mixture leve No, Hee Cheon; Kim, Chang Hyun; Lee, Dong Won, 한국원자력학회 춘계발표회, 한국원자력학회, 2004 |
| 43 | Assessment of HTGR helium compressor analysis tool based on Newton-Raphson numerical application to throughflow analysis Kim, J.H.; Kim, H.M.; No, Hee Cheon, Fourteenth International Conference on Nuclear Engineering 2006, ICONE 14, 2006-07-17 |
| 44 | Assessment of RELAP5/MOD3 with Condensation Experiment for Pure Steam Condensation in a Vertical Tube No, Hee Cheon; Kim, Sang Jae, 한국원자력학회 춘계발표회, 한국원자력학회, 1998 |
| 45 | Assessment of RELAP5/MOD3.2 with Condensation Experiment in the Presence of Noncondensables in a Vertical Tube No, Hee Cheon; Park, Hyun Sik, 한국원자력학회 춘계발표회, 한국원자력학회, 1998 |
| 46 | Assessment of RELAP5/MOD3.2.2γ Against Flooding Database in Horizontal-to-Inclined Pipes No, Hee Cheon; Kim, Hyoung Tae, 한국원자력학회 춘계발표회, 한국원자력학회, 2001 |
| 47 | Catalytic kinetics of Fe2O3 in sulfuric trioxide decomposition of SI cycle No Hee Cheon; Kim, Young Soo; Choi, Jin Young; Jin, Hyung Gon, ANS, 2011-10 |
| 48 | CHF mechanism for pool boiling of R-113 on a horizontal heater No, Hee Cheon; Chung, HJ; Chun, SY; Kim, BD; Baek, WP, NURETH10, 2003 |
| 49 | Classification of flooding data According to the Type of Entrance and Exit Geometries No, Hee Cheon; Jeong, Ji Hwan, Proceedings of the International Confefence on Multiphase Flow, 1995 |
| 50 | Classification of Flooding Data According to the Type of Tube-End Geometries No, Hee Cheon; Jeong, Ji Hwan, 한국원자력학회 춘계발표회, pp.129 - 134, 한국원자력학회, 1993 |
| 51 | Comparison of an Integral Response Scaling Method with Ishii's Scaling Method and it's Validation Using RELAP5/MOD3.2 No, Hee Cheon; Kim, Hyoung Tae, 한국원자력학회 춘계발표회, 한국원자력학회, 1999 |
| 52 | Comprehensive scaling method with validation for application to SBLOCAs of a passive PWR No, Hee Cheon; Lee, Sang Il, 한국원자력학회 추계발표회, pp.263 - 269, 한국원자력학회, 1996 |
| 53 | Compressive and buckling strengths of oxidized graphite column in the lower plenum of VHTR Park, B.H.; No, Hee Cheon; Kim, E.S.; Oh, C.H., 2008 Winter Meeting and Nuclear Technology Expo: Nuclear Power-Ready, Steady, Go, pp.462 - 463, 2008-11-09 |
| 54 | Concentration and decomposition of hydrogen iodide in the IS process Yoon, H.J.; No, Hee Cheon; Kim, S.J.; Lee, B.J.; Kim, E.S., 2006 Winter Meeting of the American Nuclear Society, pp.899 - 900, 2006-11-12 |
| 55 | Conceptual Design of Axial Flow Gas Turbines for Helium-cooled Reactors No, Hee Cheon; Kim, Ji Hwan; Kim, Hyeun Min, 한국원자력학회 춘계발표회, 한국원자력학회, 2003 |
| 56 | Conceptual design of passive containment cooling system based on APR+ No, Hee Cheon; Jeon Byong Guk, 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8), AESJ, KNS, 2012-12 |
| 57 | Conceptual design of passive containment cooling system with air holdup tanks of improved APR+ No, Hee Cheon; Jeon, Byong Guk, ENC2014, ENC2014, 2014-05-14 |
| 58 | Condensation experiment of an inclined single-tube for Passive Auxiliary Feedwater System of APR+ No, Hee Cheon; Shin Chang Wook; Yun Bong Yo; Jeon Byong Guk, 2012 ANS Winter Meeting, American Nuclear Society, 2012-11 |
| 59 | Cost analysis based on physical models developed for printed circuit heat exchangers with wavy channels in HTGR No Hee Cheon; Kim, In Hun, NTHAS7, 2010-11 |
| 60 | Countercurrent flow limitation in a horizontal pipe connected to an inclined riser No, Hee Cheon; Chun, MH, Trans. of the American Nuclear Society, 1999 |
