학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2006-Autumn | 제5분과 : 원자력안전 | Investigation of the Condensation Effect at IRWST Pool Surface on Containment Back Pressure in APR1400 Containment | Eui Jong Lee(KHNP)Jin Yong Lee and Byung Chul Lee(FNC) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Effects of Multiple Pipes Break Accident in SMART-PUsing RELAP5/SMR Code | Su Hyun Hwang,Soon Joon Hong,and Byung Chul Lee(FNC)Young Seok Bang, Byung Gil Huh,and Kwang-WonSeul | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Assessment on the Reactor Containment Cooling Capability of Kori Unit 1 Under LOCA Conditions withLoss of Offsite Power | Jin Yong Lee(FNC)Jong Woon Park and Hyeong Taek Kim(KHNP) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Thermosyphon Phenomenon as an Alternate Heat Sink of Shutdown Cooling System for the CANDUReactor | Kim,Jonghyun(GNEST)Lee,Kwangho,Oh,Haechol,and Jun Hwangyong(KEPRI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Experimental Study on the Flow Characteristics in a Bare Rod Bundle Array | Seok Kyu Chang,Bok Deuk Kim,and Sang Ki Moon(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Characteristics of Core Thermal-hydraulic Design of SMART-P | Dae-Hyun Hwang,Kyong-Won Seo,Tae-Wan Kim,and Chung-Chan Lee(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Post-CHF Heat Transfer Characteristics in One Rod Bundle Geometry | Kwi Lim Lee and Soon Heung Chang(KAIST) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | 3-Pin Critical Heat Flux Test Results for CANDU Application of the Fuel Test Loop in HANARO | K.Y.Choi,S.K.Moon,S.Y.Chun,J.K.Park,W.P.Baek,S.K.Park,and J. Y.Lee(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Modeling of Protection System and Control Systemfor the APR1400 Using RELAP5 R/T | Jeong Kwan Suh,Jin Hyuk Hong,and Myeong SooLee(KEPRI)Doo Yong Lee(FNC) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Application of the Zirconium-steam Reaction Modelto the CFX Code | Hyoung Tae Kim,Bo Wook Rhee,and Joo Hwan Park(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Comparative Analyses on OPR1000 Steam Generator Tube Rupture Event Emergency OperationalGuideline | Sang Won Lee,Yeon Kyoung Bae,and HyeongTeak Kim(KHNP) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Analyses of Loss-of-Coolant Accidents for the HANARO Fuel Test Loop Based on the EvaluationMethod | S.K.Park,D.Y.Chi,B.S.Sim,C.Y.Lee,and B.D.Chung(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Rewetting Phenomena in a 6x6 Rod Bundle During a Reflood Phase | S.Cho,S.K.Moon,B.D.Kim,J.K.Park,and W.P.Baek(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | A Study on the Static Instability of a Once-through Steam Generator with Modular Feedwater Lines | Jae-Kwang Seo,Han-OkKang,Jun Lee,JuhyeonYoon,and Keung-Ku Kim(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | ARP1400 DVI Break Analysis Using the MARS 3.1 Multi-D Component | Moonkyu Hwang,Hong-Sik Lim,Seung-Wook Lee,Sung-Won Bae,and Bub-Dong Chung(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
