Showing results 332 to 372 of 372
RANS Simulation of Turbulent Swept Flow over a Wire in a Channel for Core Thermal Hydraulic Design You, Byung-Hyun; Jeong, Yong Hoon, The 16th International Topical Meeting on Nuclear Reactor Thermalhydraulics(NURETH-16), American Nuclear Society, 2015-09-01 |
RANS simulation of turbulent swept flow over a wire in a channel for core thermal hydraulic design using advanced eddy-viscosity models You, Byung Hyun; Jeong, Yong Hoon; Addad, Y, 8th International Symposium on Turbulence, Heat and Mass Transfer, THMT 2015, pp.887 - 890, Begell House Inc., 2015-09 |
Reduction of Steam Partial Pressure by Silica Gel Considering Free Volume KAM, DONG HOON; Jeong, Yong Hoon, 2019 ANS Winter Meeting and Nuclear Technology EXPO, American Nuclear Society, 2019-11-20 |
Removal of Radioactive Nuclides and Minimization of the Wastes using Multi-functional Nanoparticle with External Magnetic Field in Decontamination Process or Severe Accident Mitigation Strategies KAM, Dong Hoon; 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 |
Role and Collaboration of Radiation Protection Experts: Summary of Discussions between the Japan Health Physics Society and the Korean Association of Radiation Protection Related to Tritiated Water Sasaki, Michiya; Yoshida, Hiroko; Kai, Michiaki; Jeong, Yong Hoon; Kim, Kyo-Youn; Lee, Hee-Seock, JOURNAL OF RADIATION PROTECTION AND RESEARCH, v.47, no.2, pp.107 - 109, 2022-06 |
Safety analyses of Kaist Micro modular reactor with modified Gamma+ code Oh, Bong-seong; Lee, Jeong-Ik; Kim, Seong Gu; Yu, Hwanyeal; Moon, Jangsik; Kim, Yonghee; Jeong, Yong Hoon, 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, Association for Computing Machinery, Inc, 2017-09 |
Safety Enhancements for PHWRs Based on Macroscopic Losses of the Fukushima Accident![]() Kim, Sang Ho; Futami, Tsuneo; Chang, Soon-Heung; Jeong, Yong Hoon, SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, v.520756, 2015-02 |
Safety evaluation of supercritical CO2 cooled micro modular reactor Oh, Bong Seong; Ahn, Yoon Han; Yu, Hwanyeal; Moon, Jangsik; Kim, Seong Gu; Cho, Seong Kuk; Kim, Yonghee; et al, ANNALS OF NUCLEAR ENERGY, v.110, pp.1202 - 1216, 2017-12 |
Scaling Criteria for Modeling Natural Circulation and High Pressure Condensation Phenomena Using Reduced Pressure System and Simulant Fluid Khasawneh, Khalid; 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 |
Sensitivity Study of Compact and Long-term-operable Passive Residual Heat Removal System Park, Wooseong; Jeong, Yong Hoon; Yoo, Yong Hwan; Kang, Kyung Jun, The 20th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-20), American Nuclear Society, 2023-08-21 |
Simulation of high temperature fuel rod bundle behavior during the QUENCH-06 experiment using CINEMA code Jeong, Woonho; Son, Donggun; Park, Jaehwan; Jeong, Yong Hoon, ANNALS OF NUCLEAR ENERGY, v.182, 2023-03 |
Simulation of the market penetration of hydrogen fuel cell vehicles in Korea Jun, Eunju; Jeong, Yong Hoon; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, v.32, no.4, pp.318 - 327, 2008-03 |
Size effect of nanometer vacuum gap thermionic power conversion device with CsI coated graphite electrodes Lee, JeongIk; Jeong, Yong Hoon; No, Hee Cheon; Hannebauer, Rob; Yoo, Sang-Keun, APPLIED PHYSICS LETTERS, v.95, no.22, 2009-11 |
Sodium-cooled fast reactor (SFR) fuel assembly design with graphite-moderating rods to reduce the sodium void reactivity coefficient Won, Jong Hyuck; Cho, Nam Zin; Park, Hae Min; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND DESIGN, v.280, pp.223 - 232, 2014-12 |
Studies of S-CO₂ power cycle application for a large PWR with a desalination capability Lee, Won Woong; Jung, Yong Hun; Jeong, Yong Hoon; Lee, Jeong-Ik, ICAPP 2015, American Nuclear Society, 2015-05-03 |
Study on Flow Instability and Critical Heat Flux for Downward Flow Boiling in a Narrow Rectangular Channel Lee, Juhyung; Jo, Daeseong; Chae, Heetaek; Chang, Soon Heung; Jeong, Yong Hoon, The Ninth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS9), Thermal Hydraulics Divisions of AESJ, KNS, 2014-11-17 |
Study on the Pressure Drop in the Helical Wire Inserted Tube Using FLUENT Code Park, Yusun; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2006-05-25 |
Study on the reactor vessel auxiliary cooling system failures in a hybrid micro modular reactor Lee, Seongmin; Choi, Jaejin; Choi, Young Jae; Jeong, Yong Hoon, The 19th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-19), American Nuclear Society, 2022-03-07 |
Study on the seawater cooled PRHRS of a nuclear propulsion ship with the upper heat exchanger for driving force and the seawater heat exchanger as an ultimate heat sink Yoo, Yong Hwan; Jeong, Han Koo; Park, Wooseong; Kim, Soo Hyoung; Jeong, Yong Hoon, INTERNATIONAL JOURNAL OF NAVAL ARCHITECTURE AND OCEAN ENGINEERING, v.16, 2024-03 |
Sub-channel Analysis of Ductless SFR Fuel Assemblies with Periodic Boundary Condition Moon, Jangsik; You, Byung Hyun; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2016-05-12 |
Subcooled flow boiling CHF enhancement with porous surface coatings Sarwar, Mohammad Sohail; Jeong, Yong Hoon; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.50, no.17-18, pp.3649 - 3657, 2007-08 |
Surfactant effects on critical heat flux during flow boiling experiment Sarwar, Mohammad Sohail; Jeong, Yong Hoon; Chang, Soon-Heung, 2007 Annual Meeting on American Nuclear Society, pp.491 - 492, 2007-06-24 |
System Design of a Supercritical CO2 cooled Micro Modular Reactor Kim, Seong Gu; Cho, Seong Kuk; HwanYeal, Yu; Kim, Yonghee; Jeong, Yong Hoon; Lee, Jeong-Ik, HTR 2014, Institute of Nuclear and New Energy Technology (INET), Tsinghua University, 2014-10 |
The characteristics of premature and stable critical heat flux for downward flow boiling at low pressure in a narrow rectangular channel Lee, Juhyung; Jo, Daeseong; Chae, Heetaek; Chang, Soon-Heung; Jeong, Yong Hoon; Jeong, Jae Jun, EXPERIMENTAL THERMAL AND FLUID SCIENCE, v.69, pp.86 - 98, 2015-12 |
The CHF Enhancement on Pool Boiling using Nano-fluids Chang, Won Joon; Jeong, Yong Hoon, The Fourth Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-4), WORTH, 2009-05-18 |
The effect of nanofluid stability on critical heat flux using magnetite-water nanofluids Lee, Jong Hyuk; Kam, Dong Hoon; Jeong, Yong Hoon, NUCLEAR ENGINEERING AND DESIGN, v.292, pp.187 - 192, 2015-10 |
The Effect of the Geometric Scale on the Critical Heat Flux for the Top of the Reactor Vessel Lower Head Park, Hae Min; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2012-05-17 |
The effect of the geometric scale on the critical heat flux for the top of the reactor vessel lower head Park, Hae Min; Jeong, Yong Hoon; Heo, Sun, NUCLEAR ENGINEERING AND DESIGN, v.258, pp.176 - 183, 2013-05 |
The Effect of the Inner Pressure Induced by Fission Gas on the SiC Layer Integrity Jeong, Hyedong; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Fall Meeting, Korean Nuclear Society, 2005-10-27 |
The importance of representative aerosol diameter and bubble size distribution in pool scrubbing Kim, Yo Han; Kam, Dong Hoon; Yoon, Jongwoong; Jeong, Yong Hoon, ANNALS OF NUCLEAR ENERGY, v.147, 2020-11 |
The Multi-Dimensional Analysis Method Development for KALIMER-600 using MARS-LMR CODE Woo, Seung Min; Park, Hae Min; Chang, Soon-Heung; Jeong, Yong Hoon, International Conference on Fast Reactors and Related Fuel Cycles (FR09), 2009-12 |
The Scaling Effect on the Critical Heat Flux of a Downward Curved Flow Channel Park, Hae Min; Jeong, Yong Hoon, The 18th Pacific Basin Nuclear Conference(PBNC 2012), KAIF,KNS, 2012-05 |
The Synergetic Effects of a Nuclear-Assisted Gas Turbine Power Cycle Jeong, Yong Hoon; Saha, Pradip; Kazimi, Mujid S., American Nuclear Society 2004 Winter Meeting, 2004-11-14 |
The synergetic effects of nuclear-assisted gas turbine power cycles Jeong, Yong Hoon; Kazimi, Mujid S., NUCLEAR TECHNOLOGY, v.160, no.2, pp.233 - 243, 2007-11 |
Theoretical Background and Case Study for the Exergo-economic Optimization of a Large-scale Electricity Storage System using supercritical Carbon Dioxide Py, Baptiste; Jeong, Yong Hoon, 2019 ANS Winter Meeting and Nuclear Technology EXPO, American Nuclear Society, 2019-11-18 |
Transition boiling heat trnasfer correlation with the consideration of hysteresis effect for the best-estimation of reflood henomena using space code Jeong, Woon Ho; Jeong, Yong Hoon, International Congress on Advances in Nuclear Power Plants (ICAPP’21), American Nuclear Society (ANS), the Atomic Energy Society of Japan (AESJ), the Korea Nuclear Society (KNS), the French Nuclear Society (SFEN), 2021-10-17 |
Validation of 1-D Code Developed to Analyze Passive Decay Heat Removal System Using Thermosyphon for Low Temperature and Low Pressure Pool-type LWR Moon, Jangsik; You, Byung-Hyun; Jung, Yong Hun; Jeong, Yong Hoon, 2014 International Congress on Advances in Nuclear Power Plants, American Nuclear Society, 2014-04-09 |
Waste Minimization and CHF Enhancement using Multi-functional Magnetic Nanoparticles during Severe Accident and Decontamination Process in Nuclear Power Plant KAM, DONG HOON; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2017-05-18 |
Wettability Effect on CHF in Subcooled Boiling Region using Cu-coated Surfaces under Flow and Atmospheric Pressure Conditions KAM, DONG HOON; Choi, Young Jae; Jeong, Yong Hoon, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2017-05-19 |
Wettability of heated surfaces under pool boiling using surfactant solutions and nano-fluids Jeong, Yong Hoon; Chang, Won Joon; Chang, Soon-Heung, INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, v.51, no.11-12, pp.3025 - 3031, 2008-06 |
Wettability of Heated Surfaces under Pool Boiling using Surfactant Solutions and Nanofluids Chang, Won Joon; Jeong, Yong Hoon; Chang, Soon-Heung, Korean Nuclear Society Spring Meeting, Korean Nuclear Society, 2007-05-11 |
Discover