학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2025-Autumn | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.30(Thu) 13:00 | 컨벤션홀 I | Evaluation of Corrosion Behavior of Gd2O3-MOx Burnable Absorber in a High-Temperature Steam | Sungwoo Ha, Yeonsoo Na, Gwangyeon Lim, Minjae Joo, Chaerin Kim, and Yoonho Kim(KEPCO NF) | PDF보기 | - |
| 2025-Autumn | 4D : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 10.30(Thu) 13:00 | 컨벤션홀 I | Comparative Study on Water Chemistry Properties Controlled with LiOH and KOH Additions for Corrosion Behavior Evaluation | Do-Yeon KIM, Seong-Jun Ha, Gi-Woong KIM, Hee-Sang Shim, Do-Haeng Hur, and Soon-Hyeok Jeon(KAERI), Seok Su Shon(Korea Univ.), Yong-Sang Cho(KHNP CRI) | PDF보기 | - |
| 2025-Autumn | 5A : 원자력 열수력 (Nuclear Thermal Hydraulics) | 10.30(Thu) 09:00 | 700A | Preliminary Single-code Analysis of Mass and Energy Release and Containment Vessel Response during Postulated LOCA and MSLB in i-SMR Using SPACE Code | Jisu Kim, Sung Yong Kim, Ye Eun An, Jeong Ju Kim, Min Shin Jung, Eun Ju Lee, and Ung Soo Kim(KEPCO E&C) | PDF보기 | - |
| 2025-Autumn | 5A : 원자력 열수력 (Nuclear Thermal Hydraulics) | 10.30(Thu) 09:20 | 700A | Preliminary Study of GPU Based FDM Acceleration Using Python CUDA | Gihyeon Kim and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2025-Autumn | 5A : 원자력 열수력 (Nuclear Thermal Hydraulics) | 10.30(Thu) 09:40 | 700A | Pressure Loss Prediction in Circular Pipe Using ChatGPT | Jong hui Lee, Seungyeob Ryu, Hun Sik Han, and Kwanghyun Ahn(KAERI), Gyeongseop Lee(SNU) | PDF보기 | - |
| 2025-Autumn | 5A : 원자력 열수력 (Nuclear Thermal Hydraulics) | 10.30(Thu) 10:00 | 700A | GPU-based Parallelization of the CUPID Code : Two Strategies and Preliminary Results | So-Hyun Park, Ik Kyu Park, and Il Jin Kim(KAERI) | PDF보기 | - |
| 2025-Autumn | 5A : 원자력 열수력 (Nuclear Thermal Hydraulics) | 10.30(Thu) 10:20 | 700A | Development of Frictional Pressure Drop Correlation for Single- and Two-phase Flow in Helically Coiled Tube | Zaidi Oktari, Byong Jo Yun, and Jae Jun Jeong(PNU) | PDF보기 | - |
| 2025-Autumn | 5A : 원자력 열수력 (Nuclear Thermal Hydraulics) | 10.30(Thu) 11:00 | 700A | CFD Analysis of a Spent Nuclear Fuel Dry Storage Cask Using an LTNE Porous Media Model | TaeGang Lee and Jae Jun Jung(PNU), Tae Hyung Na(KHNP) | PDF보기 | - |
| 2025-Autumn | 5A : 원자력 열수력 (Nuclear Thermal Hydraulics) | 10.30(Thu) 11:20 | 700A | CFD Review of Pure-Steam External Condensation on Horizontal Tubes | Taeyeon Min and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2025-Autumn | 5A : 원자력 열수력 (Nuclear Thermal Hydraulics) | 10.30(Thu) 11:40 | 700A | Deep Ensemble Algorithm for CHF Prediction under Uniform/Nonuniform Axial Profile Conditions | Chanyeong Yoon and Kyeungmo Kim(KENTECH) | PDF보기 | - |
| 2025-Autumn | 5B : 원자력 열수력 (Nuclear Thermal Hydraulics) | 10.30(Thu) 13:30 | 700A | Assessment of Filmwise Wall Condensation Heat Transfer Models in SPACE Code Using Experimental Data and MARS-KS | Hyo Jun An, Jae Hyung Park, JinHo Song, Joon Eon Yang, and Sung Joong Kim(HYU), Taeseok Kim(Jeju National Univ.) | PDF보기 | - |
| 2025-Autumn | 5B : 원자력 열수력 (Nuclear Thermal Hydraulics) | 10.30(Thu) 13:50 | 700A | Effect of CCFL at the Top of Core during ATLAS IBLOCA Tests | Hae Min Park and Seung Wook Lee(KAERI) | PDF보기 | - |
| 2025-Autumn | 5B : 원자력 열수력 (Nuclear Thermal Hydraulics) | 10.30(Thu) 14:10 | 700A | Analysis of CRUD Heat Transfer by Using CUPID-RV/GIFT Coupled Code. | Yong Suk Choi, Yeong Hun Lee, and Hyoung Kyo Cho(SNU) | PDF보기 | - |
| 2025-Autumn | 5B : 원자력 열수력 (Nuclear Thermal Hydraulics) | 10.30(Thu) 14:50 | 700A | Analysis of SMART RCP Shaft Break at a Full Power Accident Using a MARS-KS Based BEPU Approach | Nhan Hien Hoang, Seong-Su Jeon, and Jehee Lee(FNC Tech.), Ju-Yeop Park(KINS) | PDF보기 | - |
| 2025-Autumn | 5B : 원자력 열수력 (Nuclear Thermal Hydraulics) | 10.30(Thu) 15:10 | 700A | Major Regulatory Review Considerations on Safety Analysis of Small Modular Reactors | Ju Yeop Park(KINS) | PDF보기 | - |
Last Modified : 1998-Autumn
