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) | 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 | - |
| 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 | - |
Last Modified : 1998-Autumn
