| 1 | 3-DIMENSIONAL 2-FLUID CODE FOR U-TUBE STEAM-GENERATOR THERMAL DESIGN ANALYSIS LEE, JY; No, Hee Cheon, NUCLEAR TECHNOLOGY, v.75, no.2, pp.205 - 214, 1986-11 |
| 2 | A CFD-based design optimization of air-cooled passive decay heat removal system Kim, Do Yun; No, Hee Cheon, NUCLEAR ENGINEERING AND DESIGN, v.337, pp.351 - 363, 2018-10 |
| 3 | A condensation experiment in the presence of noncondensables in a vertical tube of a passive containment cooling system and its assessment with RELAP5/MOD3.2 Park, HS; No, Hee Cheon, NUCLEAR TECHNOLOGY, v.127, no.2, pp.160 - 169, 1999-08 |
| 4 | A CRUD deposit model on boiling surfaces for AOA assessment = AOA 예측을 위한 비등 면에서의 CRUD 침적 모델 개발link Kim, Min Ju; 김민주; et al, 한국과학기술원, 2015 |
| 5 | A disturbance wave instability model for annular-to-intermittent flow transition in vertical two-phase flow system Lim, IC; No, Hee Cheon, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.33, no.12, pp.903 - 914, 1996-12 |
| 6 | 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 |
| 7 | A Dry-Spot Model for Transition Boiling Heat Transfer in Pool Boiling No, Hee Cheon; Ha, SJ, Int. Conf. of 11th IHTC, 1998 |
| 8 | A dry-spot model for transition boiling heat transfer in pool boiling Ha, SJ; No, Hee Cheon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.41, no.23, pp.3771 - 3779, 1998-12 |
| 9 | A dry-spot model of critical heat flux applicable to both pool boiling and subcooled forced convection boiling Ha, SJ; No, Hee Cheon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.43, no.2, pp.241 - 250, 2000-01 |
| 10 | 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 |
| 11 | A dry-spot model of critical heat flux in pool and forced convection boiling Ha, SJ; No, Hee Cheon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.41, no.2, pp.303 - 311, 1998 |
| 12 | A heat transfer model development for CHF prediction with consideration of dry patch characteristics Kam, Dong Hoon; Jeong, Yong Hoon; No, Hee Cheon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.148, 2020-02 |
| 13 | A Mixed-Averaging Homogenization Method for Temperature Distribution in the Fuel Compact of HTGRs No, Hee Cheon; Adji Achmad Jaka Bramantya, 2012 ANS Winter Meeting, American Nuclear Society, 2012-11 |
| 14 | 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 |
| 15 | A NONEQUILIBRIUM 3-REGION MODEL FOR TRANSIENT ANALYSIS OF PRESSURIZED WATER-REACTOR PRESSURIZER BAEK, SM; No, Hee Cheon; PARK, IY, NUCLEAR TECHNOLOGY, v.74, no.3, pp.260 - 266, 1986-09 |
| 16 | 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 |
| 17 | A nucleate boiling limitation model for the prediction of pool boiling CHF Chung, Heung June; No, Hee Cheon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.50, no.15-16, pp.2944 - 2951, 2007-07 |
| 18 | A Nusselt Number Correlation of the Printed Circuit Heat Exchanger Proposed by CFD Simulations No, Hee Cheon, ICAAP09 |
| 19 | A PC-BASED WATER-LEVEL CONTROLLER FOR NUCLEAR STEAM-GENERATORS NA, MG; KIM, SP; CHUNG, WK; LEE, KJ; SONG, JS; No, Hee Cheon; LEE, JY, ANNALS OF NUCLEAR ENERGY, v.21, no.10, pp.589 - 600, 1994-10 |
| 20 | A point model for the design of a sulfur trioxide decomposer for the SI cycle and comparison with a CFD model Lee, You Ho; Lee, JeongIk; No, Hee Cheon, INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, v.35, no.11, pp.5210 - 5219, 2010-06 |
| 21 | A review of helium gas turbine technology for high-temperature gas-cooled reactors No, Hee Cheon; Kim, Ji Hwan; Kim, Hyeun Min, NUCLEAR ENGINEERING AND TECHNOLOGY, v.39, no.1, pp.21 - 30, 2007-02 |
| 22 | 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 |
| 23 | A review on the coupling of CFD code into system code in gas cooled reactor No, Hee Cheon, KNS 2008 Spring |
| 24 | A simplified approach for evaluation of the burnup potential of alternative fuels Oggianu, SM; No, Hee Cheon; Kazimi, MS, NUCLEAR TECHNOLOGY, v.146, no.3, pp.221 - 229, 2004-06 |
| 25 | A system analysis tool with a 2D gas turbine modeling for the load transients of HTGRS Kim, Ji Hwan; No, Hee Cheon; Kim, Hyeun Min; Lim, Hong Sik, NUCLEAR ENGINEERING AND DESIGN, v.239, no.11, pp.2459 - 2467, 2009-11 |
| 26 | A thermo-physical model for hydrogen-iodide vapor-liquid equilibrium and decomposition behavior in the iodine-sulfur thermo-chemical water splitting cycle Yoon, Ho Joon; Kim, Seung-Jun; No, Hee Cheon; Lee, Byung Jin; Kim, Eung Soo, INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, v.33, no.20, pp.5469 - 5476, 2008-10 |
| 27 | 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 |
| 28 | A Two-Phase Water Level Tracking Logic for the Reactor Safety Code No, Hee Cheon, Fifth International Meeting on Reactor Thermal Hydraulics, 1992 |
| 29 | 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 |
| 30 | A unified model for strength degradation of oxidized IG-430 graphite column in VHTR Park, Byung Ha; No, Hee Cheon, JOURNAL OF NUCLEAR MATERIALS, v.424, no.1-3, pp.132 - 137, 2012-05 |
| 31 | Air and helium thermal hydraulic experiments for a printed circuit heat exchanger Kim, I.H.; Lee, C.S.; No, Hee Cheon, TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, v.97, no.0, pp.747 - 748, 2007 |
| 32 | 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 |
| 33 | 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 |
| 34 | An experimental and analytical study of externally condensing heat exchangers for PCCS with an air holdup tank = 공기 수집 탱크를 활용한 PCCS용 관외 응축 열교환기의 실험 및 해석적 연구link Jeon, Byong Guk; 전병국; et al, 한국과학기술원, 2015 |
| 35 | 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 |
| 36 | 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 |
| 37 | 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 |
| 38 | 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 |
| 39 | An experimental study of thermal-hydraulic phenomena in the downcomer with a direct vessel injection system of APR1400 during the LBLOCA reflood phase Lee, DW; No, Hee Cheon; Kim, HG; Oh, SJ, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v.41, no.4, pp.440 - 447, 2004-04 |
| 40 | 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 |
| 41 | AN IMPROVED NUMERICAL SCHEME WITH THE FULLY-IMPLICIT 2-FLUID MODEL FOR A FAST-RUNNING SYSTEM CODE JEONG, JJ; No, Hee Cheon, NUCLEAR ENGINEERING AND DESIGN, v.104, no.2, pp.145 - 153, 1987-10 |
| 42 | An improved RELAP5/MOD3.3 reflood model considering the effect of spacer grids Choi, Tong Soo; No, Hee Cheon, NUCLEAR ENGINEERING AND DESIGN, v.250, pp.613 - 625, 2012-09 |
| 43 | 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 |
| 44 | An integral response scaling method for reduced-height test facilities and its validation using RELAP5 for loss of RHR during midloop operation Kim, HT; No, Hee Cheon, NUCLEAR TECHNOLOGY, v.136, no.2, pp.169 - 185, 2001-11 |
| 45 | AN INVESTIGATION OF THE PHYSICAL FOUNDATIONS OF 2-FLUID REPRESENTATION OF SODIUM BOILING IN THE LIQUID-METAL FAST BREEDER REACTOR No, Hee Cheon; KAZIMI, MS, NUCLEAR SCIENCE AND ENGINEERING, v.97, no.4, pp.327 - 343, 1987-12 |
| 46 | An optimal operating window for the Bunsen process in the I-S thermochemical cycle Lee, Byung Jin; No, Hee Cheon; Yoon, Ho Joon; Kim, Seung Jun; Kim, Eung Soo, INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, v.33, no.9, pp.2200 - 2210, 2008-05 |
| 47 | Analysis of burnup and economic potential of alternative fuel materials in thermal reactors Oggianu, SM; No, Hee Cheon; Kazimi, MS, NUCLEAR TECHNOLOGY, v.143, no.3, pp.256 - 269, 2003-09 |
| 48 | Analysis of CHF enhancement by heater surface fin structure ranging from micrometer-fin scale No, Hee Cheon; Choi, Jin Young; Yeo, Dong Yeol, 2013 International Congress on Advances in Nuclear Power Plants (ICAPP 2013), Korean Nuclear Society, 2013-04 |
| 49 | Analysis of experiments for in-tube steam condensation in the presence of noncondensable gases at a low pressure using the RELAP5/MOD3.2 code modified with a non-iterative condensation model Park, HS; No, Hee Cheon; Bang, YS, NUCLEAR ENGINEERING AND DESIGN, v.225, no.2-3, pp.173 - 190, 2003-11 |
| 50 | 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 |
| 51 | 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 |
| 52 | Analysis of geometrical effects on graphite oxidation through measurement of internal surface area Kim, ES; Lee, KW; No, Hee Cheon, JOURNAL OF NUCLEAR MATERIALS, v.348, no.1-2, pp.174 - 180, 2006-01 |
| 53 | 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 |
| 54 | 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 |
| 55 | 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 |
| 56 | 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 |
| 57 | 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 |
| 58 | Analytical work of nuclear reactor pressure vessel rupture size enlargement during severe accidents = 중대사고시 원자로 압력 용기 파손 크기 확장에 관한 해석적 연구link Song, Mun Won; No, Hee Cheon; et al, 한국과학기술원, 2018 |
| 59 | Applicability of One-Dimensional Mechanistic Post-Dryout Prediction Model No, Hee Cheon; Jeong, Hae Yong, 한국원자력학회 춘계발표회, pp.586 - 591, 한국원자력학회, 1996 |
| 60 | 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 |
