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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
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 -
2012-Spring 제 2 분과 : 핵자료, 원자로물리 및 계산과학(Nuclear Data, Reactor Physics and Computational Science) Experience of Axial Offset Anomaly (AOA) Risk Assessment for Reload Core after Steam Generator Replacement Sun-Kwan Hong, Eui-Seung Ryu, and Chan-Kook Moon(KHNP CRI) PDF보기 -
2012-Spring 제 2 분과 : 핵자료, 원자로물리 및 계산과학(Nuclear Data, Reactor Physics and Computational Science) An Idea of 20% Test of the Inital Core Reactor Physics Yang Sung-Tae, Roh Kyung-Ho, and Jung Ji-Eun(KHNP CRI) PDF보기 -
2012-Spring 제 2 분과 : 핵자료, 원자로물리 및 계산과학(Nuclear Data, Reactor Physics and Computational Science) Performance Evaluation of Neutron Radiography Facility at Kyung Hee University Reactor, AGN-201K Jong-Min Choi and Myung-Hyun Kim(KHU) PDF보기 -
Last Modified : 1998-Autumn