학술정보출판물

한국원자력학회에 오신 것을 환영합니다.

학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Effects of Truly Optimized PWR Lattice Core Design on Reactor Power and Critical Heat Flux in a Natural Circulation Small Modular Reactor Jae Hyung Park, Jihun Im, Hyo Jun An, and Sung Joong Kim(HYU) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Performance Comparison of Compact Heat Exchangers Suitable for Chloride Molten Salt Fast Reactor Intermediate Heat Transport System Sunghyun Yoo, In Woo Son, Sungwook Choi, and Jeoing Ik Lee(KAIST) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Predictability Evaluation of SPACE for DVI Line Break Test with ATLAS Hae Min Park, Sung Won Bae, and Seung Wook Lee(KAERI) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Performance Evaluation of an AHX for Thermal Energy Storage System Test Loop In Sub Jun, Jung Yoon, and Hyeonil Kim(KAERI) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Preliminary Multi-Physcis Aanalysis of a 2x2 Rod Array Using CUPID/GIFT Coupled Code Yeong Hun Lee, Kyuseok Sim, Youho Lee, and Hyoung Kyu Cho(SNU) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) SB LOCA Analysis of a Floating Nuclear Reactor Under Combined Motion Condition Yujeong Ko, and Hyoung Kyu Cho(SNU), Han Rim Choi(KEPCO E&C) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Evaluation the Effect of Surface Roughness of Cr-coated Cladding with Multi-layer Model on Large Break-Loss of Coolant Accident Dong-Young Lee, Tae-Sun Ro, Bub-Dong Chung, and Soon-Joon Hong(FNC Tech.) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Preliminary Sensitivity Analysis of APR1400 IBLOCA Scenario using SPACE Code Seung Wook LEE, ByungHyun YOU, and Jonghyuk LEE(KAERI) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Simulation of Recirculation between Reactor Coolant System and Containment with MARS-KS using Simple SMR Input Jin-Hwa Yang, Byong Guk Jeon, and Hwang Bae(KAERI) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Analysis of Loss of Condenser Vacuum Loss with One POSRV Open Failure Accident using SPACE Code for APR1400 Chang-Keun Yang(KHNP) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Numerical Study on Conjugate Heat Transfer of IVR-ERVC using Ansys Fluent Seungsu Han and Hyungdae Kim(KHU) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Preliminary CFD Analysis to Evaluate the Therml-Hydraulic Characteristics of Printed Circuit Steam Generator using the CUPID Code Taewoo Kim(UST), Hyun-Sik Park, Ik Kyu Park, and Sang Ji Kim(KAERI) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Sensitivity Analysis of the Core Flow in the APR-Type Reactor: A Comparative Study of Grid System and Turbulence Model Sungman Son, Won Man Park, and Choengyul Choi(Elsoltec), Sang Gyu Lim and Uiju Jeong(KHNP) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Dynamic Characteristics of Steam Generator Tube Finite Element Models: A Comparative Study of Element Types Won Man Park, Dae Kyung Choi, and Choengryul Choi(Elsoltec), Young Jin Oh(KECP E&C) PDF보기 -
2023-Spring 5I : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Modification of TASS/SMR Code for Thermal-hydraulic Behavior under Moving Condition Jeongeun Kim, Youngyu Jung, Hyungjun Kim, Youngjong Chung, and Soohyoung Kim(KAERI) PDF보기 -
Last Modified : 1998-Autumn