학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2020-Autumn | 5D : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.18(Fri) 11:20 | On-line | Experimental Study for Effect of SIP Flow Rate on Cold Leg 4 inch Upward Break Scenario in ATLAS Facility | Jongrok Kim, Byoung Uhn Bae, Yusun Park, Jae Bong Lee, Seok Cho, Nam Hyun Choi, and Kyoung Ho Kang (KAERI) | PDF보기 | - |
| 2020-Autumn | 5D : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.18(Fri) 11:40 | On-line | Extension of MARS-KS Motion Model to MULTID Component Modifying Volume Connection Information for Marine Reactor Simulation | Sang Wook Park, Hyung Joo Seo, and Hyoung Kyu Cho(SNU) | PDF보기 | PPT보기 |
| 2020-Autumn | 5E : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu)~12.18(Fri) | On-line | Prediction of Critical Heat Flux (CHF) Using Artificial Neural Network | Wazif Sallehhudin, Salama AlKetbi, Osama AlAtawneh, and Aya Diab(KINGS) | PDF보기 | PPT보기 |
| 2020-Autumn | 5E : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu)~12.18(Fri) | On-line | Evaluation of the Operator Actions to Maintain the Fuel Integrity During the Small Break LOCA with Safety Injection Failure for Westinghouse Type 2-loop Plant | Hyoung Kyoun Ahn, Dong Min Kim, Chan Eok Park, Gyu Cheon Lee, and Jae Young Huh(KEPCO E&C) | PDF보기 | PPT보기 |
| 2020-Autumn | 5E : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu)~12.18(Fri) | On-line | An Investigation of Accuracy Enhancement by Reconstructing MARS-KS Constitutive Relations with ANN using Data Augmentation | JaeHyung Sim, ChoHwan Oh, and Jeong Ik Lee(KAIST) | PDF보기 | PPT보기 |
| 2020-Autumn | 5E : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu)~12.18(Fri) | On-line | Assessment of Effective Thermal Conductivity Model of the SPACE for Fuel Axial Relocation in Ballooning Fuel Rods | Jong Hyuk Lee, Seung Wook Lee, Chiwoong Choi, Byung Hyun You, and Kwi Seok Ha(KAERI) | PDF보기 | PPT보기 |
| 2020-Autumn | 5E : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu)~12.18(Fri) | On-line | Study for Analyzing the Radiological Consequence of Small Line Break Outside of Containment in Design Basic Accident | Seung-Chan LEE, Duk-Joo Yoon, and Min-Jeong Kim(KHNP) | PDF보기 | - |
| 2020-Autumn | 5E : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu)~12.18(Fri) | On-line | Simulation of Crash Cooling during SBO Transient in CANDU-6 Plants | Seon Oh YU, Sung Chu SONG, Kyu Byung LEE, and Kyung Lok BAEK(KINS) | PDF보기 | PPT보기 |
| 2020-Autumn | 5E : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu)~12.18(Fri) | On-line | Numerical Study for the Effect of the Contraction Ratio on the Cavitating Venturi Internal Flow Pattern | Gong-hee Lee and June-ho Bae(KINS) | PDF보기 | - |
| 2020-Autumn | 5E : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu)~12.18(Fri) | On-line | Modification of Laminar and Transition Single Phase Heat Transfer Model in SPACE Code for Research Reactor Application | Dongwook Jang, Hyung Min Son, and Cheol Park(KAERI) | PDF보기 | PPT보기 |
| 2020-Autumn | 5E : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu)~12.18(Fri) | On-line | A Study on the Behavior of Humid Air in Sampling System for Leak Detection | Dae Kyung Choi and Choengryul Choi(Elsoltec), Tae-Soon Kwon and Dong-Jin Euh(KAERI) | PDF보기 | PPT보기 |
| 2020-Autumn | 5E : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu)~12.18(Fri) | On-line | Prediction of Natural Circulation Flow in ULPU-V Facility Loopu sing the Wall Boiling Model for Inclined Surface | Gi Su Lee and Byoung Jae Kim(CNU) | PDF보기 | PPT보기 |
| 2020-Autumn | 5F : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu)~12.18(Fri) | On-line | Simulation of OECD-ATLAS A5.1 Test with MARS-KS Code | Kyung Won Lee, Andong Shin, and Il Suk Lee(KINS) | PDF보기 | - |
| 2020-Autumn | 5F : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu)~12.18(Fri) | On-line | Clustering Study on Constitutive Equations for using Integral Effect Test Data to Improve Accuracy of a Reactor Safety Analysis Code | ChoHwan Oh, DohHyeon Kim, Jaehyeong Sim, Sung Gil Shin, and JeongIk Lee(KAIST) | PDF보기 | PPT보기 |
| 2020-Autumn | 5F : 원자력열수력 (Nuclear Thermal Hydraulics) | 12.17(Thu)~12.18(Fri) | On-line | Preliminary Investigation of Pressure Effect of the Emergency Cooldown Tank on Accident Grace Period of Small Modular Reactors | Jae Hyung Park, Doyoung Shin, Hoichul Jung, and Sung Joong Kim(HYU) | PDF보기 | PPT보기 |
Last Modified : 1998-Autumn
