학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | Derivation of the Scaling Criteria for a Small Scale CANDU Moderator Test Facility | Bo Wook Rhee and Hyoung Tae Kim(KAERI) | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | Numerical Study of Thermal-hydraulics in CANDU-typed Moderator | Jae Ryong Lee, Han Young Yoon, and Hyoung Tae Kim(KAERI) Jae Jun Jeong(PNU) | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | Numerical Analysis of CANDU-6 Moderator System Using Open FOAM | Se-Myong Chang(KNU) Hyoung Tae Kim(KAERI) | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | A Simple Fully Passive Safety Option for SMART SBLOCA | Won Jae Lee(KAERI) | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | Design Assessment and Transient Simulation of an Integral Reactor, REX-10, Using TAPINS Code | Yeon-Gun Lee and Goon-Cherl Park(SNU) | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | A Scaling Study of the Natural Circulation Flow of the Ex-vessell Core Catcher Cooling System of a 1400 MWe PWR for Designing a Scale-down Test Facility | Bo.W. Rhee, K.S. Ha, R.J. Park, and J.H. Song(KAERI) | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | Analysis of Combined Ocean Thermal Energy Conversion Using Waste Heat from NPPs | Hyeonmin Kim, Jeong-tae Cho, and Gyunyoung Heo(KHU) Hoon Jung(KEPCO RI) | PDF보기 | - | ||
| 2012-Spring | 제1분과 : 원자로시스템기술(Reactor System Technology) | Shakedown Analysis for the Hydraulic Nut Device of Reactor Vessel | Kyu Wan Kim, Jong Min Kim, Sung Ho Park, and Taek Sang Choi(KEPCO E&C) | PDF보기 | - | ||
| 2012-Spring | 제 2 분과 : 핵자료, 원자로물리 및 계산과학(Nuclear Data, Reactor Physics and Computational Science) | Evaluation of Reactor Physics Characteristics for the Modified CANDU6 Fuel | Young Ae Kim and Dong Hwan Park(KHNP CRI) | PDF보기 | - | ||
| 2012-Spring | 제 2 분과 : 핵자료, 원자로물리 및 계산과학(Nuclear Data, Reactor Physics and Computational Science) | Time-average Calculation Using FEM in a CANDU Reactor | Eun Hyun Ryu, Joo Hwan Park, Yong Man Song, and Lee Chung Chan(KAERI) Hyung Jin Shim(SNU) | PDF보기 | - | ||
| 2012-Spring | 제 2 분과 : 핵자료, 원자로물리 및 계산과학(Nuclear Data, Reactor Physics and Computational Science) | Impacts of U-238 Thermal Movement on Safety Parameters of CANDU-6 | Yonghee Kim and Donny Hartanto(KAIST) | PDF보기 | - | ||
| 2012-Spring | 제 2 분과 : 핵자료, 원자로물리 및 계산과학(Nuclear Data, Reactor Physics and Computational Science) | Feasibility Study of Recriticality Monitoring by Noise Analysis Method | Chidong Kong and Deokjung Lee(UNIST) Eunki Lee(KHNP CRI) | PDF보기 | - | ||
| 2012-Spring | 제 2 분과 : 핵자료, 원자로물리 및 계산과학(Nuclear Data, Reactor Physics and Computational Science) | Sensitivity Analysis of Vanadium Self-powered Neutron Detector under Varied Geometries of Emitter and Insulator | Kyoon-Ho Cha, Seong-Man Bae, and Chan-Kook Moon(KHNP CRI) | PDF보기 | - | ||
| 2012-Spring | 제 2 분과 : 핵자료, 원자로물리 및 계산과학(Nuclear Data, Reactor Physics and Computational Science) | A Study on Criticality Safety Parameters of New Fuel Storage Rack Design | Joon Gi Ahn and Hyeong Heon Kim(KEPCO E&C) | PDF보기 | - | ||
| 2012-Spring | 제 2 분과 : 핵자료, 원자로물리 및 계산과학(Nuclear Data, Reactor Physics and Computational Science) | Comparison of Calculated Value by the Core Design ASTRA Code with Measured Data | Ji-Eun Jung and Sung-Tae Yang(KHNP CRI) | PDF보기 | - |
Last Modified : 1998-Autumn
