Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Type Conference
Showing results 2561 to 2580 of 5608
| First results of a compact advanced extreme ultraviolet spectrometer to measure spatio-temporally varying tungsten spectra in fusion plasmas Song, Inwoo; Choe, Wonho; Seon, Changrae; Hong, Joohwan; An, Younghwa; Barnsley, Robin; Lee, HG; et al, ECPD 2017: 2nd European Conference on Plasma Diagnostics, French Alternative Energies and Atomic Energy Commission (CEA), 2017-04-19 |
| First-order perturbation for uncertainty quantification in the deterministic truncation of Monte Carlo method Kim, HyeonTae; Kim, Inhyung; Kim, Yonghee, Tech 2018 Iron and Steel Technology Conference and Exposition, pp.430 - 432, American Nuclear Society, 2018-06 |
| First-principles Study for Discovery of High-entropy MXenes Seong, HyunWoo; Lee, Minseok; Ryu, Ho Jin, The Materials Science & Technology (MS&T23), The American Ceramic Soceity, 2023-10-04 |
| Fission Product Release from TRISO by Diffusion Chang, Won Joon; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Fall Meeting, Korean Nuclear Society, 2005-10-27 |
| Flash distillation of overazeotropic HIx phase based on optimal Bunsen reaction in I-S cycle Yoon, H.J.; No, Hee Cheon; Kim, Y.S.; Jin, H.G., 2009 ANS Annual Meeting and Embedded Topical Meeting: Nuclear and Emerging Technologies for Space, NETS 2009, v.100, pp.722 -, 2009-06-14 |
| Flat Panel Imager Test System for Digital Radiography 조규성; 김희준, 물리학회, 2000 |
| Floating absorber for safety at transient analysis code(FASTAC): verification and validation LEE, SEONGMIN; Jeong, Yong Hoon, The 12th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-12), Chinese Nuclear Society and American Nuclear Society, 2018-10-16 |
| Flow accelerated corrosion behavior of CANDU feeder piping characterized by high temperature rotating cylinder electrode Kim J.H.; Kim, In Sup; Chung H.S., Pressure Vessel and Piping Codes and Standards -2002- (2002 ASME Prssure Vessels and Piping Conference), v.439, pp.209 - 217, 2002-08-05 |
| Flow Accelerated Corrosion Behavior of Low Alloy Steel at Elevated Temperature 김인섭, Korean Nuclear Society, 2002 |
| Flow Analysis in the Helical Wire Inserted Tube using CFD code Park, YS; Chang, Soon-Heung, 한국원자력학회 춘계학술발표대회, 한국원자력학회, 2009-05 |
| Flow Boiling CHF Characteristics of Magnetic Nanofluid Under the Magnetic Field Condition Lee, Taeseung; Lee, Jong Hyuk; Jeong, Yong Hoon, 2013 International Congress on Advances in Nuclear Power Plants, Korean Nuclear Society, 2013-04-18 |
| Flow Boiling CHF Enhancement using Porous Surface Coatings Sawar, M. Sohail; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2006-05-26 |
| Flow Boiling CHF Experiment on Sudden Expansion Tube KIM, YONG JIN; Chang, Soon Heung; Jeong, Yong Hoon, The 11th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety(NTHAS11), Korean Nuclear Society, 2018-11-20 |
| 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 |
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