학술정보출판물

한국원자력학회에 오신 것을 환영합니다.

학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Preliminary CFD Analysis of Refrigerant Cooled, Scaled Down RPV of OPR1000 Do Yeong Lim and In Cheol Bang(UNIST) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Prediction of Flow Instability of Natural Convection in Sloped Channel Byeonghee Lee and Seok-Gyu Jeong(KAERI) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Analysis of CHF under Oscillatory Flow Condition using MARS-KS Moving Reactor Model Moonhee Choi and Hyoung Kyu Cho(SNU) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Validation of a CFX Code for Helical-Type MHD Power Generator Jong-Pil Park and Doo Hee Chang(KAERI) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) CCP Assessment under CANDU Normal Operating Condition with Various Reactor Power Jae Yong Oh, Euiseung Ryu, and Donghwan Park(KHNP) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Comparison of CCP using CHF Correlations under HSP-2 & 3 Conditions Jae Yong Oh, Euiseung Ryu, and Donghwan Park(KHNP) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) The Evaluation Process for Leak Detection Systems using CFD Analysis Dae Kyung Choi, Won Man Park, Sung Man Son, and Choengryul Choi(Elsoltec), Woo-Shik Kim, Tae-Soon Kwon, and Dong-Jin Euh(KAERI) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) A Numerical Study on Heat Transfer Characteristics of Various Shapes of Fuel Rods in Nuclear Reactors Hyerim Woo, Sungjin Yang, and Jongrak Choi(KETI) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Development of CFD Simulation Methodology for Cladding Oxidation Phenomenon Siwon Seo, Armanto Simanjuntak, Benrico Simamora, and Jaeyoung Lee(HGU) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Sensitivity Study for Active Single Failure in the Intermediate Break LOCA Yerim Park, Seyun Kim, and Junkyu Song(KHNP) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Numerical Modeling of Flow Boiling in a Rectangular channel using OpenFOAM Iljin Kim and Hyungdae Kim(KHU) PDF보기 PPT보기
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) A Preliminary Study on Reliability Evaluation Methodology for Passive Safety Systems Youngjae Park, Jeehee Lee, and Seong-Su Jeon(FNC Tech.), Ju-Yeop Park(KINS) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Modeling the CRUD Effects on Heat Transfer in Subchannels of Pressurized Water Reactor Hyeon Ji Kim, Ji Yong Kim, and In Cheol Bang(UNIST) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Preliminary Analysis of PIUS-type Experimental Apparatus with Hot/Cold Fluids Interface for Inherently Safety Ju Hun Jung and In Cheol Bang(UNIST) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Safety Analysis of MicroURANUS LFR for Unprotected Loss of Flow and Unprotected Loss of Heat Sink Joo Hyung Seo and In Cheol Bang(UNIST) PDF보기 -
Last Modified : 1998-Autumn