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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2007-Spring 제5분과 원자력안전 Calculation Method of Steam Generator Level for swelling and shrinking effects in YGN 1/2 Simulator Do Hyun Hwang, In Yong Seo(KEPRI), Weon Seo Park(KHNP), Jae Seung Suh(ENESYS) PDF보기 -
2007-Spring 제5분과 원자력안전 Critical Heat Flux during Flow Boiling Experiment with Surfactant Solutions Mohammad Sohail Sarwar, Yong Hoon Jeong and Soon Heung Chang(KAIST) PDF보기 -
2007-Spring 제5분과 원자력안전 Design Change Effect of Automatic PHT Pump Trip on Small Break LOCA for Wolsong Unit 1 Lee, Kwangho, Kim, Yongbae, Bae, Sungman(KEPRI) PDF보기 -
2007-Spring 제5분과 원자력안전 Experimental Investigation of the Local Temperature Distribution and Thermal Mixing Phenomena in a Cylindrical Tank C. K. Park, H. G. Jun, Y. J. Yoon, C. H. Song(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 PIV Measurements of Lateral Flow on Fuel Subchannel Seok Kyu Chang, Yeon Jun Choo, Sang-Ki Moon(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Heat Transfer Measurements in a 5x5 Rod Bundle with Vaned Spacer Grids Seok Kyu Chang, Yeon Jun Choo, Bok Deuk Kim, Sang-Ki Moon(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Preliminary Study for a Numerical Investigation on the Effect of an Upstream Elbow on an Orifice Flowmeter Performance Seong Hoon Kim, Young In Kim, Cheon Tae Park, Quun Sung Zee(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Effect of the Geometry on a Free Surface Fluctuation in a Vessel Ho-Yun Nam, Byoung-Hae Choi, Jong-Man Kim, and Byung-Ho Kim(KAERI) PDF보기 -
2007-Spring 제5분과 원자력안전 Simulant Melt Experiments on Boiling Heat Transfer at the Upper Surface of Molten Metal Kyoung-Ho Kang, Young-Rho Cho, Rae-Joon Park, Sang-Baik Kim, Seong-Wan Hong, Hee-Dong Kim(KAERI) PDF보기 -
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 -
Last Modified : 1998-Autumn