학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2006-Autumn | 제5분과 : 원자력안전 | Pressure/Temperature Analysis Using GOTHICComputer Code for Kori 3&4 Auxiliary BuildingEnvironmental Qualification | Won-sang Jeong and Hee-do Lee(KOPEC)Dong-soo Song(KEPRI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Structural Integrity Assessment of Reactor Pressure Vessel During Pressurized Thermal Shock | Y.S.Chang,H.S.Chang,S.M.Lee,J.B.Choi,and Y.J.Kim(SKKU)Y.H.Choi and M.J.Jhung(KINS) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Dynamic and Vibration Analysis of a Rotating Bladefor the HANARO Cooling Fan | Bong Soo Kim,Yong ChulPark,Young Sub Lee,andHoan Sung Jung(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Design Improvement of NSSS Integrity Monitoring System for SKN1&2 | Yang Gyun Oh,Gi ChanPark,Seung Min Baek,and Hang Bae Kim(KOPEC)Scott Galin(WEC) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Establishment of Regulations on Refurbishment Activities for CANDU Reactors | Sang Kyu Lee,ManwoogKim,and Hyun Koon Kim(KINS)Hee Yung Roh and TaeEun Jin(KOPEC) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Assessment of Welding Residual Stress for Pipelinesof Nuclear Power Plants Using a Fuzzy Model | In Joon Hwang,Man GyunNa,and Jin Weon Kim(CSU) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Wall-thinning Rate Evaluation of Pipes Under Accelerated Flow Condition | S.M.Lee,J.M.Kim,Y.S.Chang,J.B.Choi,and Y.J.Kim(SKKU)Y.H.Choi(KINS) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Real-scale Failure Tests on Local Wall-thinned Elbow Under Internal Pressure | Yeon-Soo Na and Jin-Weon Kim(CSU)Chi-Yong Park and Sung-Ho Lee(KEPRI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Comparison of FEA Responses Between Brick and Tetrahedron Elements of Mini Heat Exchanger forGeneration IV Reactors Subjected to Pressure and Thermal Loads | Bong Yoo,Man-Sik Myung,and Yun-Jae Kim(KU) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Inelastic Ratcheting Constitutive Models for a GEN-IV Reactor Structural Design Subjected to Elevated Temperature Operations | Gyeong-Hoi Koo and Jae-Han Lee(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Development of the Sludge Visualization Program | Seokun Lim,JangwoogChoi,Kyungjoo Kwon,Donghwa Suk,and Sujin Kim(KPS) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | The Evaluation of Safety Culture in Nuclear PowerPlant | Kwon,Maeng sub,ChungKi jun,KwonHoie Koo,Kang Jae yeul,and ParkHyun taek(KHNP) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Summary of the Safety Culture Activities in HANARO of KAERI | In-Cheol LIM,Jong-SupWU,and Kye-Hong LEE(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Suggestions on the Development of Safety Culture Assessment Method | Young Sung Choi,KwangSik Choi and Woong SikKim(KINS) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Quantitative Effects of Safety Culture on NuclearSafety | Moosung Jae(HYU) | PDF보기 | - |
Last Modified : 1998-Autumn
