학술정보출판물

한국원자력학회에 오신 것을 환영합니다.

학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Validation of Wall Film Condensation Model in the Presence of the Non-Condensable Gas for CAP Jehee Lee, Yeon-Jun Choo, Seong-Su Jeon, and Soon-Joon Hong(FNC Tech.) PDF보기 -
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Development of Constitutive Equations in Reactor Safety Analyssi Code with Data-based Modeling Using Artificial Neural Network ChoHwan Oh, Doh Heyon Kim, Jaehyung Sim, Sung Gil Shin, and Jeong Ik Lee(KAIST) PDF보기 -
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Simulation of SBO in CANDU-6 Using MARS-KS Code Seon Oh YU, Min Ki CHO, Kyung Lok BAEK, and Sung Chu SONG(KINS) PDF보기 -
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line TASS/SMR-S Analysis on a Single-Phase Natural Circulation Phenomenon in SMART-ITL during 3-Different Operating Conditions Hwang Bae, Ji Han Chun, Young-Jong Chung, and Hyun-Sik Park(KAERI) PDF보기 -
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Verification of DICE Physical Module Integrity by SBLOCA Calculation Hyunjoon Jeong and Taewan Kim(INU), Jonghyun Kim(CSU), Gyunyoung Heo(KHU) PDF보기 -
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Analysis of IFA650.9 Using MARS-KS Coupled with SCDAP Yunseok Lee and Taewan Kim(INU) PDF보기 -
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Preliminary Simulation on Jet Breakup Experiment Using High Accuracy Kernel Correction Scheme for Smoothed Particle Hydrodynamics Hae Yoon Choi and Eung Soo Kim(SNU) PDF보기 -
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Validation of Integrated Code of MARS-KS and FRAPTRAN Using Halden IFA-650.5 LOCA Test Chang-Yong Jin, Joosuk Lee, and Deog Yeon Oh(KINS) PDF보기 -
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Effect of Core Asymmetry for the Analysis of DNBR Using Multi-scale Codes Il Suk Lee, Dong Hyeog Yoon, Young Seok Bang, and Kwang Won Seul(KINS), Yong Chan Kim(Korea Univ.) PDF보기 -
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line CANDU 6 Small Break LOCA with High Power Channel of 5% or More Pressure Tube Creep Dongwook Kho and Sungmin Kim(KHNP CRI) PDF보기 -
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Heat Loss Determination of ATLAS Facility and System Code Application Seong-Su Jeon, Bicer Erol, Jae-Ho Bae, and Soon-Joon Hong(FNC Tech.), Byoung-Uhn Bae and Kyoung-Ho Kang(KAERI) PDF보기 -
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Computational Study of wall Condensation Phenomena in the Presence of Non-condensable Gases Containing a Light Gas by Using CUPID-MARS Coupled Code Chang Won Lee, Jin-Seong Yoo, and Hyoung Kyu Cho(SNU) PDF보기 -
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Implementation of the Crud Layer Model into the SPACE Code Jin Yoo(NESS), Seung Wook Lee(KAERI), Young Jae Park and Hyungdae Kim(KHU), Byoung Jae Kim(CNU) PDF보기 -
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line CAP Code Validation of Two-Phase Flow Pressure Drop Kum Ho Han, SeongSu Jeon, and SoonJoon Hong(FNC Tech.) PDF보기 -
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Enhancing CHF Prediction of AECL Look-Up Table Along with Machine Learning TaeHyun Chun and YongGyun Yu(KAERI) PDF보기 -
Last Modified : 1998-Autumn