Browse "Dept. of Nuclear and Quantum Engineering(원자력및양자공학과)" by Type Conference
Showing results 2684 to 2703 of 5608
| Hardness and Modulus of 410 Martensitic Steel after High Temperature Proton Irradiation Waseem, Owais Ahmed; Ryu, Ho Jin; Jeong, Jong Ryul; Park, Byung Guk, 한국원자력학회 2016 추계학술대회, 한국원자력학회, 2016-10-27 |
| Harness Design for the Improvement of Transmitter Survivability in a Severe Accident Yoo, Min; Kang, Hyun Gook, American Nuclear Society 2013, American Nuclear Society, 2013-04-04 |
| HEA Phase Prediction and Principle Factor Analysis Using Machine Learning 이태규; 류호진, 33회 점단구조재료 심포지엄, 대한금속·재료학회, 2019-09-27 |
| Health and Environmental Risks of Energy Systems: Implications of Current Knowledge, Technology, and the Chernobyl Accident Yim Man-Sung; John S. Evans; Richard Wilson, The First Saharov Memorial Conference for Peace Progress and Human Rights, no.1991, Saharov Memorial Conference for Peace Progress and Human Rights, 1991-05 |
| Heat exchanger design study for micro molten salt reactor 손인우; 최성욱; 김상지; 이정익, 2022 한국원자력학회 춘계학술발표회, 한국원자력학회, 2022-05-19 |
| Heat Flux Enhancement using Particle-mixed Coolant in HTGR Jeong, Hyedong; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Autumn Meeting, Korean Nuclear Society, 2006-11-03 |
| Heat Load Reduction by Additional Injection Tank on Reactor Vessel Lower Head during Severe Accident Park, Hae Min; Jeong, Yong Hoon, The 5th China-Korea Workshop on Nuclear Reactor Thermal Hydraulics (WORTH-5), KNS,CNS, 2011-10-10 |
| Heat Removal Capability of the Passive Residual Heat Removal System, Proc. of Passive Safety Features in Nuclear Installations Chun, Moon Hyun, Post-SMIRT 14 International Seminar 18, 1997 |
| Heat Transfer Coefficient Measurement at Top Region of Reactor Vessel Lower Head under IVR-ERVC Condition Jung, Jun Yeong; 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 |
| 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 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 |
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