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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) 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 -
2023-Spring 6A : 원자력 안전 (Nuclear Safety) 5.18(Thu) 10:00 Samda Hall A (3F) Comparison of Various Quantification Approaches for Seismic PSA Sang Hoon HAN(KAERI) PDF보기 PPT보기
2023-Spring 6A : 원자력 안전 (Nuclear Safety) 5.18(Thu) 10:40 Samda Hall A (3F) Offsite Power Recovery Time Analysis for Dynamic Probabilistic Safety Assessment Yunyeong Heo, Wooseok Jo, and Seung Jun Lee(UNIST) PDF보기 -
2023-Spring 6A : 원자력 안전 (Nuclear Safety) 5.18(Thu) 11:00 Samda Hall A (3F) Estimating the Effects of Offsite Power Recovery Time based on Cutset Analysis Jae Young Yoon and Dong-San Kim(KAERI) PDF보기 -
2023-Spring 6A : 원자력 안전 (Nuclear Safety) 5.18(Thu) 11:20 Samda Hall A (3F) An Uncertainty Analysis Methodology in Level 2 PSA and Its Application Juhyeok Choi, Dohyun Lim, Chanwoo Park, Minseop Song, and Moosung Jae(HYU) PDF보기 -
2023-Spring 6A : 원자력 안전 (Nuclear Safety) 5.18(Thu) 11:40 Samda Hall A (3F) A Sensitivity Analysis Methodology in Level 2 PSA and Its Application Chanwoo Park, Juhyeok Choi, Dohyun Lim, Minseop Song, and Moosung Jae(HYU) PDF보기 -
2023-Spring 6A : 원자력 안전 (Nuclear Safety) 5.18(Thu) 12:00 Samda Hall A (3F) Plume Segmentation by Time Phase and Its Application to All Source Term Categories of OPR1000 Seunghwan Kim and Sung-yeop Kim(KAERI) PDF보기 -
Last Modified : 1998-Autumn