학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2007-Spring | 제5분과 원자력안전 | Validation of the Severe Accident Management Guidance for Wolsong Plants | Youngho JIN, Yong-Mann SONG(KAERI) | PDF보기 | - | ||
| 2007-Spring | 제5분과 원자력안전 | Uncertainty Analysis of a Two-Color Pyrometry Applied to TROI Experiments | Kwang-Soon Ha, Byung-Tae Min, Jin-Ho Song, Seong-Wan Hong(KAERI) | PDF보기 | - | ||
| 2007-Spring | 제5분과 원자력안전 | The MIDAS Computer Code through an Integration of the Restructured MELCOR | S.H.Park, D.H.Kim, Y.M.Song(KAERI), S.W.Cho(KRTIC) | PDF보기 | - | ||
| 2007-Spring | 제5분과 원자력안전 | Mitigating Capability Analysis during LOCA for Korean Standard Nuclear Power Plants in Containment Integrity | Young Choi, Soo Yong Park, D. H. Kim, Y. M. Song(KAERI) | PDF보기 | - | ||
| 2007-Spring | 제5분과 원자력안전 | Applicability of 7λ DDT Criterion in the IRWST of APR1400 | Namduk Suh(KINS) | PDF보기 | - | ||
| 2007-Spring | 제5분과 원자력안전 | Re-evaluation of NUPEC M-7-1 Hydrogen Experiment using MELCOR 1.8.6 | Dong Ju Jang, Namduk Suh(KINS) | PDF보기 | - | ||
| 2007-Spring | 제5분과 원자력안전 | The Characteristics of Hydrogen Generation and Combustion during Severe Accidents in the CANDU-6 Plants | Soo Yong Park, Yong Mann Song(KAERI) | PDF보기 | - | ||
| 2007-Spring | 제5분과 원자력안전 | Preliminary Analysis of a Steam -Water Natural Circulation Flow under ERVC | Jae-Cheol Kim, Kwang-Soon Ha, Rae-Joon Park, Young-Rho Cho, Sang-Baik Kim(KAERI) | PDF보기 | - | ||
| 2007-Spring | 제5분과 원자력안전 | Comparative Analysis of MELCOR 1.8.5 and RELAP5 Codes for a SBO accident | Namduk Suh, Yongjin Cho(KINS) | PDF보기 | - | ||
| 2007-Spring | 제5분과 원자력안전 | An Evaluation of a Coolant Injection into an In-Vessel with a RCS Depressurization during a SBLOCA in OPR1000 | Rae-Joon Park, Seong-Wan Hong, Sang-Baik Kim, Hee-Dong Kim(KAERI) | PDF보기 | - | ||
| 2007-Spring | 제5분과 원자력안전 | Analysis of the TMI-2 Accident by using MARS/SCDAP | Rae-Joon Park, Young-Jin Lee, Bub-Dong Chung(KAERI) | PDF보기 | - | ||
| 2007-Spring | 제5분과 원자력안전 | Analysis of Ex-Vessel Corium Coolability using MELCOR 1.8.5 Code | Namduk Suh, Yongjin Cho(KINS) | PDF보기 | - | ||
| 2007-Spring | 제5분과 원자력안전 | Analysis of the Steam Generator Tube Rupture Source Term for a PHWR | See Darl Kim, Dong Ha Kim(KAERI) | PDF보기 | - | ||
| 2007-Spring | 제5분과 원자력안전 | Analyses of the Particle Size Distributions from TROI FCI Tests | I. K. Park, J. H. Kim, B. T. Min, S. H. Hong, S. W. Hong, H. D. Kim(KAERI) | PDF보기 | - | ||
| 2007-Spring | 제5분과 원자력안전 | Comparison of the Uniform Hazard Spectra for Korean NPP Sites | In-Kil Choi(KAERI), Masato Nakajima(ABIKO), Young-Sun Choun(KAERI), Yasuki Ohtori(ABIKO) | PDF보기 | - |
Last Modified : 1998-Autumn
