학술발표회 논문집 (ISSN: 3140-1864)
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Critical Heat Flux Experiments for In-Vessel Retention External Reactor Vessel Cooling Strategy Using 2-D Slice Test Section | Hae Min Park, Taeil Kim, and Yong Hoon Jeong(KAIST) Sun Heo(KHNP) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Corium Retention and Cooling by an Ex-vessel Core-catcher for Nuclear Power Plants | Jong Ho Lee and Ji Hwan Kim(KHNP) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Simulation of Energetic Isothermal Fuel-Coolant Interactions Using the Coupled Method of Rigid Body Dynamics and Moving Particle Semi-Implicit | Shane Park, Chong Kuk Chun, Jong Sun Lim, and Kee Yil Nahm(KEPCO) Gyoo-Dong Jeun(HYU) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Analysis of In-vessel Melt Progression Scenarios for an Advanced PWR Using MELCOR 1.8.6 | Tae-Woon Kim, Rae-Joon Park, Jin-Ho Song, and Sung-Won Cho(KAERI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Investigation of Bubble Mechanisms of Cocurent Downward Flows through Packing | DaeSeong Jo and Heetaek Chae(KAERI) Shripad T. Revankar(PU) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Experimental Study on Critical Heat Flux Characteristics of CuO/DIW Nanofluids according to Manufacturing Methods | Seung Won Lee, Sung Dae Park, Sarah Kang, and In Cheol Bang(UNIST) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Boiling Phenomena with Surfactant and Nanoparticles. | Sung Dae Park, Sarah Kang, Seung Won Lee, and In Cheol Bang(UNIST) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Void-fraction, Water Distance & Velocity Measurement of a Gas-liquid Two-phase Flow in a Complete Test Channel by Ultrasonic Methods | Kil Mo Koo, Jin-Ho Song, Chul-Hwa Song, and Won-Pil Baek(KAERI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | A Comparative Study of the Lattice Boltzmann and Volume of Fluid Method for the Rising Bubble Flows | Seungyeob Ryu, Cheon Tae Park, and Suhn Choi(KAERI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Development of Flow Regime Map inside a Vertical Pipe | Gyeong-Uk Kang and Bum-Jin Chung(JNU) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | The Thermal Hydraulic Test of SFR Irradiation Test Capsule | Chul-Yong Lee, Sung-Jae Park, and Kee-Nam Choo(KAERI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Experiments for the Scaling Analysis of AHX | Jeong-Hwan Heo and Bum-Jin Chung(JNU) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Verification of Flow Blockage Test in the MATRA-S Code | Tae Woo Kim, Seong Jin Kim, Jeong Hun Cha, Hyuk Kwon, and Dae Hyun Hwang(KAERI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Design Development of SCOP Facilities for Core Flow and Pressure Distribution of SMART Reactor | Dongjin Euh, Youngjung Youn, Hwang Bae, Incheol Chu, Yungjoo Ko, and Tae-Soon Kwon(KAERI) | PDF보기 | - | ||
| 2010-Autumn | 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Introduction of STELLA Program and Basic Design Features of the Test Facilities | Tae-Ho Lee, Tae-Joon Kim, Jae-Hyuk Eoh, Ji-Woong Han, Hyeong-Yeon Lee, In-Ku Hwang, Hee-Ryung Kim, a | PDF보기 | - |
Last Modified : 1998-Autumn
