학술발표회 논문집
Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
---|---|---|---|---|---|---|---|
2020-Spring | 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 7.9(Thu)~7.10(Fri) | On-line | Evaluation of Mechanical Properties of Additive-Manufactured Stainless Steel for Nuclear Applications | Jung-Min Kim, Junhyun Kwon, and Hyung-Ha Jin(KAERI) | PDF보기 | - |
2020-Spring | 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) | 7.9(Thu)~7.10(Fri) | On-line | Additive Manufacturing of Co-base Alloy for Nuclear Application; Wear Property | Ji Hoon Kang, Jinsung Jang, Chang Hee Han, and Junhyun Kwon(KAERI), Min Ha Shin(KIST) | PDF보기 | - |
2020-Spring | 5C : 원자력열수력 (Nuclear Thermal Hydraulics) | 7.9(Thu)~7.10(Fri) | On-line | Application of MARS-FRAPTRAN Integrated Code to LBLOCA Analysis and Understanding of Fuel Rod Behavior | YOUNG SEOK BANG, JOOSUK LEE, and IL SUK LEE(KINS) | PDF보기 | - |
2020-Spring | 5H : 원자력열수력 (Nuclear Thermal Hydraulics) | 7.9(Thu)~7.10(Fri) | On-line | Application of Heat Transfer Enhancement Factors at Downstream of Quench Front Considering Collapsed Water Level | Seung Hyun Yoon, Jaeseok Heo, Kyung Doo Kim, Chiwoong Choi, and Kwiseok Ha(KAERI) | 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 | 5I : 원자력열수력 (Nuclear Thermal Hydraulics) | 7.9(Thu)~7.10(Fri) | On-line | A Study of Compressed CO2 Energy Storage System for Nuclear Power Plants Application | Soyoung Lee, Yongju Jeong, and Jeong Ik Lee(KAIST) | PDF보기 | - |
2020-Spring | 6B : 원자력 안전 (Nuclear Safety) | 7.9(Thu)~7.10(Fri) | On-line | Application of Various Protective Actions for Multi-unit Accidents | Sunghyun Park, Mina Cho, Seokwoo Sohn, and Moosung Jae(HYU) | PDF보기 | - |
2020-Spring | 6C : 원자력 안전 (Nuclear Safety) | 7.9(Thu)~7.10(Fri) | On-line | Application of DICE(Dynamic Integrated Consequence Evaluation) Case Study on Branching Rules Examples | Sejin Baek and Gyunyoung Heo(KHU), Taewan Kim(INU), Jonghyun Kim(CSU) | PDF보기 | - |
2020-Spring | 6H : 원자력 안전 (Nuclear Safety) | 7.9(Thu)~7.10(Fri) | On-line | Review and Application of the Recent Modeling Approach for Liquid Fuel Fire Scenarios in Nuclear Power Plants | Yong Hun JUNG and Dae Il KANG(KAERI) | PDF보기 | - |
2020-Spring | 10D : 원전건설 및 운영기술 (Nuclear Power Plant Construction and Operation Technology) | 7.9(Thu)~7.10(Fri) | On-line | Application of Advanced UT in Nuclear Power Plant Inspection | Tae-Geun LEE, Euisoon DOH, Hun-Hee PARK, and Hee-Sup BAE(Sae-An Eng.) | PDF보기 | - |
2020-Spring | 11B : 원자력정책, 인력 및 협력 (Nuclear Policy, Human Resources and Cooperation) | 7.9(Thu)~7.10(Fri) | On-line | Analysis on Legitimacy of Non-explosive Military Applications of Nuclear Material | Sung Yoon Park(KINAC) | PDF보기 | - |
2020-Spring | 12B : 원자력계측제어 및 자동원격 (Nuclear I&C and Automatic Remote System) | 7.9(Thu)~7.10(Fri) | On-line | Application of the Scoping Fire Human Reliability Analysis on the Nuclear Power Plant | Gayoung Park and Jonghyun Kim(CSU) | PDF보기 | - |
2020-Spring | 12E : 원자력계측제어 및 자동원격 (Nuclear I&C and Automatic Remote System) | 7.9(Thu)~7.10(Fri) | On-line | Application of STPA Methodology to Safety Analysis of Operation Automation System of Nuclear Power Plant Using Artificial Intelligence Technology | Kee-Choon Kwon, Jang-Yeol Kim and Seo Ryong Koo(KAERI) | PDF보기 | - |
2019-Autumn | 1B : 원자로시스템기술 (Reactor System Technology) | 10.25(Fri) 10:20 | 304호 (3F) | Application of New Rules for the Prediction of CANDU Pressure Tube Diameter | JONG YEOB JUNG(KAERI), RALPH MARIGOMEN(NESS) | PDF보기 | - |
2019-Autumn | 1C : 원자로시스템기술 (Reactor System Technology) | 10.25(Fri) 11:00 | 405A호 (4F) | Innovative Intermediate Compact Heat Exchanger Design for Possible Application on VHTR System | YongWan Kim, Injin Sah, and EungSeon Kim(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn