학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Technical Considerations for the Systems Analysis in SMART PSA | NamChul Cho and Chang-Ju Lee(KINS) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | A Proposed Approach for Enhancing Design Safety Assurance of Future Plants | Kju-Myeong Oh, Sang-Kyu Ahn, and Chang-Ju Lee(KINS) Inn Seock Kim(ISSA Tech.) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Study on LOCA Frequency and Contribution to Risk of Nuclear Power Plant | Seong Soo Choi, Dong Sik Jin, and Poong Oh Kim(ACT Co.,Ltd.) Inn Seock Kim(ISSA Tech.) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | A Study on the Regulatory Requirement of Event Frequency Change by Facility Improvement and Modification in Wolsong Unit 1 | Kilyoo Kim and Jinhee Park(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Comparison between Heinrich's Law and the Number of Events in Domestic Nuclear Power Plants | Sun Yeong Choi and Joon-Eon Yang(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Assessment of In-Core Damage for Feeder Stagnation Break in CANDU | Jong Yeob Jung and Joo Hwan Park(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Analysis of Worldwide Regulatory Framework for On-Line Maintenance | Sang-Kyu AHN, Kyu-Myung OH, and Chang-Ju Lee(KINS) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Design of Nanoparticle Engineered Safety Injection Tank | Myoung-suk Kang, Changhyun Jee, Sangjun Park, and Gyunyoung Heo(KHU) In Choel Bang(UNIST) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Application of a New Approach for Estimating LOCA and SGTR Frequencies | Ho-Jun Jeon, Ji-Yong Oh, and Moon-Goo Chi(KHNP) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | An Evaluation of the Unexpected Trip Limits Using the Quality Control Approach | Hyun-woo Lee and Moosung Jae(HYU) Kilyoo Kim(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Thermal Field of Moderator Circulation in CANDU-6 Reactor | Tae Kwang Eom, Sung Je Hong, and Jae Young Lee(HGU) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Evaluation of MARS Code on CHF with Fluid-to-Fluid Method Under Inlet Flow Fluctuation | Jin S. Hwang, Jong W. Kim, and Goon C. Park(SNU) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Simulation of UPTF Test 20 by Using MARS Multi-Dimensional Component | Sung Won Bae and Bub Dong Chung(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Transport Characteristics of Representative Debris in a Open Channel | Kyung Sik Choi and Ji Hwan Joeng(PNU) Joo Yeop Park(KINS) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | MARS Transient Analyzer for Dual Reactor Unit Producing 2000 MWe | Kyoung M. Kang and Kune Y. Suh(SNU) | PDF보기 | - |
Last Modified : 1998-Autumn
