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학술발표회 논문집 (ISSN: 3140-1864)

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) 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 -
2023-Spring 6A : 원자력 안전 (Nuclear Safety) 5.18(Thu) 09:00 Samda Hall A (3F) A New Calculation Method for Multi-unit Cascade Accidents Gee Man Lee, Hyun Seok Noh, and Woo Sik Jung(Sejong Univ.) PDF보기 PPT보기
2023-Spring 6A : 원자력 안전 (Nuclear Safety) 5.18(Thu) 09:20 Samda Hall A (3F) Review of the Importance Analysis Method in Seismic Probabilistic Safety Assessment Seunghyun Jang, Junhee Park, and Min Kyu Kim(KAERI) PDF보기 -
2023-Spring 6A : 원자력 안전 (Nuclear Safety) 5.18(Thu) 09:40 Samda Hall A (3F) COHRISK: A Multihazard Risk Quantification Software for Nuclear Power Plants Eujeong Choi, Jeong-Gon Ha, Minkyu Kim, and Daegi Hahm(KAERI), Shinyoung Kwag(HNU), Jung-Han Kim(PNU) PDF보기 -
Last Modified : 1998-Autumn