학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2006-Autumn | 제5분과 : 원자력안전 | SBLOCA Mass and Energy Release Analysis for Kori3&4 EQ | T.M.Kim,C.W.Kim,K.S.Han,J.H.Song,and J.T.Seo(KOPEC)D.S.Song(KEPRI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Containment Response Analysis for Equipment Qualification of Kori Nuclear Power Plant Unit 3 and 4 | Choong Sup Byun,DongSoo Song,and HwangYong Jun(KEPRI)Kwi Hyun Seo and WanJung Song(ENERGEO) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Preliminary Analyses on the ATWS Events for OPR1000 Using RETRAN-3D Code | Sang Won Lee and YeonKyoung Bae(KHNP) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Assessment of MEDUSA Code with Turbine Trip & Natural Circulation Test of YGN Unit 6 | Jong Cheol Park,ChanEok Park,and Jong TaeSeo(KOPEC) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Analysis of LOFT Experiments L6-1 and L6-5 Using MEDUSA Code | Myung Taek Oh,Chan EokPark,Sang Yong Lee,and Jong Tae Seo(KOPEC) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Safety Evaluation of Low-temperature Overpressurization Events for Yonggwang Units 1&2 | Jongbeom Lee(KHNP) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | An Approach for Quantifying Safety Margins in Nuclear Power Plants | Huichang Yang and JeongIck Yun(ENESYS)Jeong Seuk Park and JuYeop Park(KINS) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Head Loss Coefficient Evaluation Based on CFD Analysis for PWR Downcomer and Lower Plenum | Ji Hwan Jeong and JongPil Park(PNU)Byoung Sub Han(ENESYS) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Cooling Analysis of Spent Fuel Pool with a CFDMethod | H.C.Jang,B.R.Jung,and J.K.Hwang(KOPEC) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Analysis of SBLOCA in SMART-P Using RELAP5/SMRCode | Su Hyun Hwang,SoonJoon Hong,and ByungChul Lee (FNC)Young Seok Bang,ByungGil Huh,and Kwang-WonSeul(KI | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Components Effects for the Performance of thePassive Residual Heat Removal System of an Advanced Integral Type Reactor | Hyun-Sik Park,Ki-YongChoi,Sung-Jae Yi,and Moon-Ki Chung(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Development of Coupled Interface System Betweenthe FADAS Code and a Source-term Evaluation Code XSOR for CANDU Reactors | Han Seong Son and DeokYong Song(ENESYS)Manwoong Kim,ShinHyeong Ki,Sang-Kyu Lee,and Hyun-Koon Kim(KIN | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Application of Subcooled Boiling Model to Thermal-hydraulic Analysis Inside a CANDU-6 Fuel Channel | Manwoong Kim,Sang KyuLee,and Hyun Koon Kim(KINS)Jin Bok Yu(ATES) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Application of an Iterative Solution Scheme to MARS | K.D.Kim,H.S.Lim,and B.D.Chung(KAERI) | PDF보기 | - | ||
| 2006-Autumn | 제5분과 : 원자력안전 | Development and Verification of a Semi-implicit Three-field Pilot Code | Moonkyu Hwang,Sung-Won Bae,Young-Jin Lee,Hyung-Kyu Cho,Jae-JunChung,and Bub-DongChung(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
