학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 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 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Nuclear Safety and the Role of Quality Assurance | Hyuk-il Kwon,Chan-GookPark,Ji-Hee Nam,Kwon-Hyun Kim,Young-GunLee,and Nam-Jin Lim(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Safety Culture Improvement Activities of YGN 3 & 4 | Ill-hoon Cho(KHNP) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Analysis of the Survey Results for the Safety Culture Attitude of HANARO Center | Jong-Sup Wu,In-CheolLim,and Kee-Hong Lee(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | New Paradigm in Nuclear Safety from Quality Assurance to Safety Management System | Nam-Jin Lim,Chan-GookPark,Ji-Hee Nam,Kwan-Hyun Kim,Hyun-il Kwon,and Young-Gun Lee(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Computational Two-phase Flow Analysis forSubcooled Boiling in Annulus Channel | B.U.Bae and G.C.Park(SNU)H.Y.Yoon,D.J.Euh,and C.H.Song(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Prediction of a Drainage from an Open Water Tank | Jonghark Park,HeetaekChae,Cheol Park,HeonilKim,Sooyoul Oh,and Jeongsoo Ryu(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Investigation of Thermal-hydraulic Characteristicson Aging Effect for CANDU Reactors | Jun Soo Yoo,Yong WonChoi,Chang Hwan Park,and Un Chul Lee(SNU)Manwoong Kim,Sang-KyuLee,and Hyun-Koon | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | A Study on the Cycle Analysis of a Cryogenic Refrigerator for the CNS in the HANARO | Bong Soo Kim,Young KiKim,and Jungwoon Choi(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Development of a CANDU Moderator Analysis Model;Based on Coupled Solver | Churl Yoon and Joo Hwan Park(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | CFD Prediction of AFW Pump Room Temperature in Ulchin Units 3&4 | Churl Yoon,MeejeongHwang,Joon-Eon Yang,and Joo Hwan Park(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Thermal Analysis for Environmental Qualification of Kori Nuclear Power Plant Unit 3 and 4 | Kwi Hyun Seo(ENERGEO)Choong Sup Byun and Dong Soo Song(KEPRI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | CHF Performance of Hybrid Mixing Vane Grid (II) | C.H.Shin,Y.J.Choo,Y.J.Youn,S.K.Moon,and T.H.Chun(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Development of Steady-state Thermal-hydraulic Model for Wolsong-3 | Hoon Choi and Yong-BaeKim(KEPRI) | PDF보기 | - |
Last Modified : 1998-Autumn
