Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Title
Showing results 5081 to 5100 of 10277
| Heat Transfer Coefficient Measurement for Downward Facing Flow Boiling Heat Transfer to Simulate IVR-ERVC Condition of LLOCA Case Jung, Jun Yeong; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2016-05-13 |
| Heat transfer coefficient measurement for downward-facing heat transfer on curved rectangular water channel Jung, Jun Yeong; Jeong, Yong Hoon, 24th International Conference on Nuclear Engineering, ASME, 2016-06-27 |
| Heat transfer coefficient measurement for outer wall of the reactor vessel lower head under IVR-ERVC condition = IVR-ERVC 조건에서 원자로 하부 외벽 열전달계수 측정link Jung, Jun Yeong; 정준영; et al, 한국과학기술원, 2016 |
| Heat Transfer Coefficient Measurement of Downward Facing Curved Surface Flow Boiling and Comparison with Prediction Correlation Jung, Jun Yeong; Jeong, Yong Hoon, International Workshop on Nuclear Safety and Severe Accident(NUSSA (Embedded to NUTHOS-11)), Korean Nuclear Society and American Nuclear Society, 2016-10-12 |
| Heat transfer correlation for the CO2 2-phase flow near the critical point 손인우; 배성준; 이정익, 2018 한국원자력학회 춘계학술발표회, 한국원자력학회, 2018-05-17 |
| Heat transfer distribution of randomly packed pebble-bed fuels for fluoride salt-cooled high temperature reactor (FHR) Kim, Seong Gu; Liu, Maolong; Lee, Youho; Lee, Jeong-Ik, International Topical Meeting on Advances in Thermal Hydraulics 2018, ATH 2018, pp.331 - 342, American Nuclear Society, 2018-11 |
| Heat Transfer Experiment with PureTemp58X for Passive Containment Cooling Application 조재완; 심재형; 이정익, 2019 KNS 춘계학술발표회, 한국원자력학회, 2019-05-23 |
| HEAT TRANSFER HELIUM_COOLED STORAGE BASKET FOR SPENT PWR FUEL RODS No, Hee Cheon, ICONE15 |
| HEAT TRANSFER IN HELIUM-COOLED STORAGE BASKET No, Hee Cheon, ICONE 2007 Spring |
| Heat transfer origin of thermal shock fracture and its application for LWR fuel during reflood Lee, Youho; No, Hee-Cheon, 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015, pp.7196 - 7207, American Nuclear Society, 2015-08 |
| Heat transfer performance evaluation of anodized Zirlo flat plates under pool boiling and atmospheric conditions Yu, Hyoung Suk; KAM, DONG HOON; Jeong, Yong Hoon, The Eighth China-Korea Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-8), Korea Atomic Energy Research Institute, Nuclear Power Institute of China, Xi’an Jiaotong University, 2017-10-23 |
| Heat Transfer Surface Morphology and Oxidation Effect on the CHF under Vertical Flow Boiling Considering the RPV Manufacturing and Operating Condition 정준영; 이민석; 정용훈, 2021 한국원자력학회 춘계학술발표회, 한국원자력학회, 2021-05-14 |
| Heats of formation of (U,Mo)Al-3 and U(Al,Si)(3) Ryu, Ho Jin; Kim, Yeon Soo; Hofman, Gerard L; Park, Jong Man; Kim, Chang Kyu, JOURNAL OF NUCLEAR MATERIALS, v.358, pp.52 - 56, 2006-11 |
| Helicon plasma generation at very high radio frequency Eom, GS; Bae, ID; Cho, Gyuseong; Hwang, YS; Choe, Wonho, PLASMA SOURCES SCIENCE TECHNOLOGY, v.10, no.3, pp.417 - 422, 2001-08 |
| Helium Hydraulic Tests in the Printed Circuit Heat Exchanger 노희천; Kim, In Hun; Lee, Cheol Shin, 한국원자력학회 춘계발표회, 한국원자력학회, 2008 |
| Helium Hydraulic Tests in the Printed Circuit Heat Exchanger No, Hee Cheon, KNS 2008 Spring |
| Helium ions irradiation analysis of W-0.5(TaTiVCr)(0.5) for application as a future fusion plasma-facing material Waseem, Owais Ahmed; Ryu, Ho Jin, MATERIALS CHEMISTRY AND PHYSICS, v.260, 2021-02 |
| Helium-water loop tests with PCHE for GAMMA validations No, Hee Cheon; Kim, In Hun, 한국원자력학회 추계발표회, 한국원자력학회, 2011 |
| Hetero-structured Oxide Dispersion Strengthened CoCrFeMnNi High-Entropy Alloy CHUNG, SEUNGHYEOK; Ryu, Ho Jin, 16th International Symposium on Novel and Nano Materials, ISNNM, 2020-11-04 |
| Heterodyne wave number measurement using a double B-dot probe Eom, GS; Kwon, GC; Bae, ID; Cho, Gyuseong; Choe, Wonho, REVIEW OF SCIENTIFIC INSTRUMENTS, v.72, no.1, pp.410 - 412, 2001-01 |
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