Showing results 2581 to 2600 of 5619
Flow Boiling CHF Experiments using Nanofluid under Different Heating Rate Kim, TI; Jee, YT; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2011-05-26 |
Flow Boiling CHF Experiments using Nanofluid under Different Heating Rate Kim, Tae Il; Lee, Joo Hyung; Chang, Soon-Heung, 2011 The 5th China-Korea Workshop on Nuclear Reactor Thermal Hydraulics (WORTH-5), WORTH-5, 2011-10-11 |
Flow Boiling CHF on Flow Path Simulating Cladding Deformation KIM, YONG JIN; Jeong, Yong Hoon, International Workshop on Nuclear Safety and Severe Accident(NUSSA), Chinese Nuclear Society, 2018-11-06 |
Flow Boiling Critical Heat Flux Enhancement by Using Magnetic Nanofluids and External Magnetic Fields Lee, Taeseung; Jeong, Yong Hoon, The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14), CNS,ANS,IAEA,AENNEA, 2011-09-25 |
Flow boiling critical heat flux enhancement on the 2-D slice for boric acid and TSP solution Park, Hae Min; Heo, Sun; Jeong, Yong Hoon, The 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14), CNS,ANS,IAEA,AENNEA, 2011-09-25 |
Flow Boiling Critical Heat Flux Enhancement with Tri-Sodium Phosphate and Boric Acid Solution in the Tube Park, Hae Min; Jeong, Yong Hoon, Korean Nuclear Society Autumn Meeting, KNS, 2012-10 |
Flow Boiling Experiment for the Heat Transfer Enhancement Using Nanoporous Coatings Sarwar, M.S.; Chang, Soon-Heung, 한국원자력학회 학술발표대회, 한국원자력학회, 2005-05 |
Flow Distribution Analysis in Micro Molten Salt Fast Reactor with Flow Distributor Park, Wooseong; Kim, Sang Ji; Jeong, Yong Hoon, International Congress on Advances in Nuclear Power Plants (ICAPP’23), American Nuclear Society (ANS), the Korea Nuclear Society (KNS), 2023-04-24 |
Flow Induced Vibration Characteristics in 2X3 Bundle Critical Heat Flux Experiment Kim, DH; Chang, Soon-Heung, 한국원자력학회 학술발표대회, 한국원자력학회, 2005-05 |
Flow Instability and Critical Heat Flux for Downward Flow in a Vertical Narrow Rectangular Channel Heated From Both-sides Lee, Juhyung; Daesung Jo; Soon Heung Chang, 2013 한국원자력학회 추계학술발표회, 한국원자력학회, 2013-10-25 |
Flow Measurement in a 2-D Slice for ERVC Conditions by PIV Yoon, Jongwoong; 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 |
Flow Regime Characterization and Void Fraction Measurement by Capacitance Transducers Chun, Moon Hyun; Sung Chang-Kyung, Winter Annual Meeting of the American Society of Mechanical Engineers., 1984 |
Flow regime comparison of MARS-KS to SPACE during LBLOCA 김민길; 이유호; 이정익, The Korean Nuclear Society Autumn Meeting(2014), pp.810 - 812, The Korean Nuclear Society, 2014-10 |
Flow sheet analysis of nuclear hydrogen production from water and sulfur Jung, Yong Hun; Jeong, Yong Hoon, 2nd International Topical Meeting on Safety and Technology of Nuclear Hydrogen Production, Control, and Management 2010, pp.83 - 89, 2010-06-13 |
Flow Structure and Near-Wall Bubble Behavior in Subcooled Flow Boiling at High Heat Flux Bang, IC; Baek, WP; Chang, Soon-Heung, 한국원자력학회 추계학술발표대회, 한국원자력학회, 2000 |
Flow-Accelerated Corrosion Behaviour of SA106 Gr.C Steel in Alkaline Solution using Rotating Cylinder Electrode Kim, In Sup, International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, pp.1 - 10, 2001 |
Flow-Accerlated Corrosion Behavior of SA106 Gr.C Steel in LiOH Solution using Rotating Cylinder Electrode. 김인섭, Korean Nuclear Society, 2000 |
Fluent의 삼차원 LES 난류 모델을 이용한 가압 경수로 연료봉 다발에서 멱 스펙트럼 밀도의 해석 노희천; 김현민, 한국원자력학회 춘계발표회, 한국원자력학회, 2003 |
Fluid-to-fluid scaling criteria validation for modeling condensation in horizontal tubes Khasawneh, Khalid; Jeong, Yong Hoon, The 12th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-12), Chinese Nuclear Society and American Nuclear Society, 2018-10-17 |
FLUKA Simulation for In-beam PET Development in Hadron Therapy 황지성; 장호종; 최경돈; 김준혁; 조규성, 방사선산업학회, 방사선산업학회, 2018-11-08 |
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