Showing results 1 to 60 of 116
A Case Study of Risk Informed Asset Management (RIAM) for Nuclear Power Plant Lee,Gyoung Cheol; Jeong, Yong Hoon; Chang, Soon-Heung; Chung, Dae-Wook, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2006-11-02 |
A feasibility study of application in NPPs using magnetite-water nanofluid Lee, Jong Hyuk; Kam, Dong Hoon; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29 |
A Methodology for Assessment of External Vessel Cooling During Severe Accidents in PWRs Park, Jae Hong; Baek, Won Pil; Jeong Yong Hoon; Chang, Soon-Heung, Second Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS2), v.Volume 1, pp.494 - 500, 2000-10-15 |
A Parametric Study for Designing Capacitive Deionization System Lee Taeseung; Lee, JeongIk; Jeong Yong Hoon, 2010 Australia's International Water Conference and Exhibition (OZWATER '10), Australian Water Association, 2010-03-08 |
A Study on the Correlations Development for Film boiling Heat Transfer on Spheres Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1998-05-01 |
A Study on the Development of On-Line Source Term Estimation System for PWRs Kim, TW; Jeong, Yong Hoon; Choi, SS; Cho, GW; Shin, HG; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2001-05-24 |
A Study on the Non-Heating CHF Experiments Using Drilled Plates Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1999-05-28 |
A Study on the Non-Heating Simulation ofPool Boiling CHF on Flat Plates Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2000-10-26 |
An axiomatic design approach of nanofluid-engineered nuclear safety features for generation III+ reactors Bang, I.C.; Heo, G.; Jeong, Yong Hoon; Heo, S., The 7th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-7), v.41, pp.1157 - 1170, NUTHOS, 2008-10-05 |
An Experimental Study on the Convective Heat Transfer in Narrow Rectangular Channels for Downward Flow to Predict Onset of Nucleate Boiling Song, Jung Hyun; Lee, Juhyung; Chang, Soon Heung; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29 |
Analysis of CHF enhancement by magnetite nanoparticle coating in subcooled boiling region Choi, Young Jae; KAM, DONG HOON; Jeong, Yong Hoon, The 11th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-11), Korean Nuclear Society and American Nuclear Society, 2016-10-11 |
Analysis of Flow Instabilities in Multi-channel Loop Type Thermosyphon You, Byung-Hyun; Jeong, Yong Hoon, 2014 22nd International Conference on Nuclear Engineering (ICONE22), ASME, 2014-07-11 |
Analysis of Hydrogen Economy using Vensim Jun, Eunju; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Fall Meeting, Korean Nuclear Society, 2005-10-28 |
Analysis of World Nuclear Market and Strategy of Korean NPP’s Competitiveness Improvement for Exportation Choi, Jae Young; Roh, Seungkook; Chang, Soon Heung; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2016-10-27 |
Analysis on Fission Products Diffusion using Finite Difference Method Jeong, Hyedong; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2007-05-10 |
Assessment of Dryout Heat Flux Correlations for Particle Beds Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 1997-05-01 |
Assessment of pool boiling CHF enhancement using magnetite and alumina water nanofluids at higher pressure Lee, Jong Hyuk; Lee, Taeseung; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, KNS, 2012-10 |
CFD Analysis of Dry Storage System for CANDU Spent Fuel using Fluent 6.2 Shin, Byungsoo; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2006-05-25 |
CHF Enhancement in Flow Boiling at low mass flux using Al2O3 Nano-fluid Kim, Tae Il; Jeong, Yong Hoon; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2009-05 |
CHF Experiments for IVR-EVC using 2-D Slice Test Section Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2002-05-23 |
CHF Experiments on the Reactor Vessel Wall using 2-D Slice Test Section Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2003-10-05 |
CHF Measurement for Flat Plates Considering Dimensional Effects (Length & Width) under Atmospheric and Pool Boiling Conditions KAM, DONG HOON; Choi, Young Jae; Jeong, Yong Hoon; Park, Hae Min, The 11th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-11), Korean Nuclear Society and American Nuclear Society, 2016-10-10 |
Comparative Study on the Power Generation Options in Korea using Multi Criteria Decision Analysis Jun, Eunju; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2005-05-27 |
Conceptual Design of a Nuclear Reactor Dedicated for Desalination Jung, Yong Hun; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29 |
Conceptual Design of a Nuclear Reactor for Desalination Jung, Yong Hun; Moon, Jangsik; Jeong, Yong Hoon, The 29th KAIF/KNS Annual Conference, KAIF/KNS, 2014-04-17 |
Conceptual Design of Additional Injection Tank for Heat Load Reduction on Reactor Vessel Lower Head during Severe Accident Hu, Ji Young; Park, Hae Min; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, KNS, 2012-10-25 |
Conceptual Design of NaN3 Inflator for Safety Injection Tanks Heo, Gyunyoung; Jeong, Yong Hoon; Kim, Tae Mi, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2007-10-26 |
Conceptual Design of Safety Injection Tanks Using Saturated Water Park, Hae Min; Jeong, Yong Hoon; Chang, Won Joon, The Fourth Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-4), WORTH, 2009-05 |
Conceptual Design of the Primary Loop of Pool-Type Natural Circulating Nuclear Reactor Dedicated to Seawater Desalination Jeong, Woonho; Jeong, Yong Hoon, The 11th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-11), Korean Nuclear Society and American Nuclear Society, 2016-10-12 |
Condensation Experiment for a Desalination System Using the Waste Heat of Nuclear Power Plants and Solar Energy Systems Khasawneh, Khalid; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2016-10-27 |
Continued Operation and Public Acceptance in Korea Jeong, Yong Hoon; Chang, Soon-Heung, The 27th JAIF-KAIF Seminar on Nuclear Industry, 2005-10-24 |
Cost-benefit Analysis Based on PSA for Additional Passive Safety System and Alternative AC Power Source Kim, Sang Ho; Kang, Hyun Gook; Chang, Soon-Heung; Jeong, Yong Hoon, International Workshop on Nuclear Safety and Severe Accident, The International Atomic Energy Agency, 2014-09-04 |
Critical heat flux characteristic of magnetite-water nanofluid in pool boiling Lee, Jong Hyuk; Lee, Taeseung; Jeong, Yong Hoon, The 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8), Thermal Hydraulics Divisions of AESJ, KNS, 2012-12 |
Critical Heat Flux during Flow Boiling Experiment with Surfactant Solutions Sarwar, Mohammad Sohail; Jeong, Yong Hoon; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2007-05-11 |
Critical Heat Flux Enhancement: Nano-fluids and Others Chang, Soon-Heung; Jeong, Yong Hoon, International Workshop on New Horizons in Nuclear Reactor Thermal Hydraulics, 2008-01-07 |
Critical Heat Flux Experiments for In-Vessel Retention External Reactor Vessel Cooling Strategy using 2-D Slice Test Section Park, Hae Min; Kim, Taeil; Heo, Sun; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, 2010-10-21 |
Critical Heat Flux Experiments for In-Vessel Retention External Reactor Vessel Cooling Strategy using 2-D Slice Test Section Park, Hae Min; Kim, Taeil; Heo, Sun; Jeong, Yong Hoon, The 8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-8), 2010-10-12 |
Critical Heat Flux Experiments for In-Vessel Retention External Reactor Vessel Cooling Strategy Using 2-D Slice Test Section Park, Hae Min; Kim, Taeil; Heo, Sun; Jeong, Yong Hoon, The 7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7), 2010-11-17 |
Critical Heat Flux Measurement for downward facing flat plates (SUS 304, SA 508) under atmospheric and pool boiling conditions Kam, Dong Hoon; Park, Hae Min; Choi, Young Jae; Jeong, Yong Hoon, The Seventh China-Korea Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-7), Nuclear Power Institute of China, Korea Atomic Energy Research Institute, 2015-10-15 |
Critical Heat Flux Measurement of SiC- and Cr-coated Plates, Bare Stainless Steel Plate and Zircaloy-4 Plate Under Atmospheric and Pool Boiling Conditions Kam, Dong Hoon; Lee, Jong Hyuk; Lee, Taeseung; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-29 |
Critical Heat Flux Measurement of SiC- and Cr-coated surfaces with reference surfaces for pool boiling and α-SiC tube for flow boiling under atmospheric conditions, Surface change of SiC-coated surface Kam, Dong Hoon; Jeong, Yong Hoon, International Workshop on Nuclear Safety and Severe Accident, The International Atomic Energy Agency, 2014-09-03 |
Design of Graphic Aggregation Model for Evaluation of Energy Systems An, Sang Ha; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2006-05-25 |
Design of Nuclear Power Plant Online Monitoring System An, Sang-ha; Lee, Song-kyu; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2007-05-10 |
Design of Safety Injection Tanks Using Axiomatic Design and TRIZ Heo, Gynu Young; Jeong, Yong Hoon, 5th International Youth in Nuclear Congress, 2008-09-20 |
Development of nuclear power plant online monitoring system using statistical quality control An, Sang Ha; Jeong, Yong Hoon; Chang, Soon-Heung, 2006 Winter Meeting of the American Nuclear Society, pp.932 - 934, American Nuclear Society, 2006-11-12 |
Effect of Geometry, Heater Material and Coolant Additives on CHF of Curved Inclined Surface Park, Hae Min; Jeong, Yong Hoon, International Workshop on Nuclear Safety and Severe Accident, The International Atomic Energy Agency, 2012-09 |
Effect of Magnetite Nanoparticle Deposition Kinetics on the Flow Boiling CHF Characteristics of Magnetite-Water Nanofluid Lee, Taeseung; Lee, Jong Hyuk; Jeong, Yong Hoon, The 5th China-Korea Workshop on Nuclear Reactor Thermal Hydraulics (WORTH-5), KNS,CNS, 2011-10-10 |
Effects of Magnetic Field on Flow Boiling CHF in Fe3O4 Ferrofluid Lee, Taeseung; Park, Hae Min; Lee, Jong Hyuk; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, 2010-10-21 |
Effects of Magnetic Field on Flow Boiling CHF in Magnetite-water Nanofluid Lee, Taeseung; Lee, Jong Hyuk; Park, Hae Miin; Jeong, Yong Hoon, International Congress on Advances in Nuclear Power Plants(ICAPP '11), SFEN,AESF,ANS,KNS, 2011-05-02 |
Effects of Magnetic Fields on the Flow Boiling CHF of Magnetic Nanofluids Lee, Taeseung; Jeong, Yong Hoon, 한국원자력학회 2011년도 춘계학술대회 (Korean Nuclear Society Spring Meeting), 한국원자력학회, 2011-05-25 |
Estimation of Fission Product Release from the TRISO Fuel Jeong, Hyedong; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2006-05-25 |
Estimation of fission product release from TRISO Jeong, Hyedong; Jeong, Yong Hoon; Chang, Soon-Heung, 2006 Winter Meeting of the American Nuclear Society, pp.858 - 859, American Nuclear Society, 2006-11-12 |
Estimation ofthe Thermal Efficiency of Hybrid Sulfur Cycle for Hydrogen Generation using Gas Cooled Reactor Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2005-05-27 |
Evaluation of Heat Removal Performance of Passive Decay Heat Removal system for S-CO2 Cooled Micro Modular Reactor Moon, Jangsik; Lee, Jeong-Ik; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2015-05-08 |
Experiment Study of the chracteristics of pool boiling CHF enhancement using water-based magnetic fluid Lee, Taeseung; Jeong, Yong Hoon, 한국원자력학회 2011년도 춘계학술대회 (Korean Nuclear Society Spring Meeting), 한국원자력학회, 2011-05-25 |
Experiment Study on the Magnetic Field Effect of Pool Boiling CHF Enhancement in Water-based Magnetic Fluid with Lower Concentration Lee, Jong Hyuk; Jeong, Yong Hoon, International Congress on Advances in Nuclear Power Plants(ICAPP '11), SFEN,AESJ,ANS,KNS, 2011-05-02 |
Experimental analysis of the flow in the vortex chamber of the safety injection tank for APR1400 Jeong, Woonho; Jeong, Yong Hoon, The Ninth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS10), Thermal Hydraulics Divisions of AESJ, KNS, 2016-11-28 |
Experimental and Analytical Study on the Simulation of Pool Boiling CHF Based on Macrolayer Dryout Model Jeong, Yong Hoon; Baek, Won-Pil; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2001-05-24 |
Experimental CHF Study on the Pressure Effect in the 2-D Slice Test Section Park, Hae Min; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2014-05-30 |
Experimental CHf study on the scaling effect of 2-D slice test section for in-vessel retention through external reactor vessel cooling strategy Park, Hae Min; Heo, Sun; Song, Chanyi; Jeong, Yong Hoon, International Congress on Advances in Nuclear Power Plants(ICAPP '11), SFEN,AESJ,ANS,KNS, 2011-05-02 |
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