Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Title
Showing results 4841 to 4860 of 10267
| 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 at sudden expansion flow path under low pressure condition = 저압 조건 아래 급격히 팽창한 유로에서의 임계열유속에 대한 연구link Kim, Yong Jin; Jeong, Yong Hoon; et al, 한국과학기술원, 2020 |
| Flow boiling critical heat flux characteristics of magnetic nanofluid at atmospheric pressure and low mass flux conditions Lee, Tae-Seung; Lee, Jong-Hyuk; Jeong, Yong-Hoon, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.56, no.1-2, pp.101 - 106, 2013-01 |
| 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 boiling experiments for CHF evaluation under downward-facing heating including flow visualization: Effects of pressure, orientation, mass flux, and local quality Jung, Jun Yeong; Lee, Min Suk; Park, Hae Min; Jeong, Yong Hoon, ANNALS OF NUCLEAR ENERGY, v.171, 2022-06 |
| 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 instability during subcooled boiling for a downward flow at low pressure in a vertical narrow rectangular channel Lee, Juhyung; Chae, Heetaek; Chang, Soon Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.67, pp.1170 - 1180, 2013-12 |
| 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 characterization and void fraction measurement in a two-phase flow system by capacitance transducers = 이상류 계에서 캐패시턴스 변환기를 이용한 유동 영역의 결정과 기포율 측정link Choi, Jong-Bae; 최종배; et al, 한국과학기술원, 1985 |
| 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 regime transition and heat transfer model at low mass flux condition in a post-dryout region = 포스트-드라이아웃 영역에서의 유동형태 천이와 저유량 조건에서의 열전달 모델link Jeong, Hae-Yong; 정해용; et al, 한국과학기술원, 1996 |
| 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 |
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