Zobrazeno 1 - 5
of 5
pro vyhledávání: '"Shih-Kuei Cheng"'
Publikováno v:
Nuclear Technology. 113:21-28
The MELCOR code, developed by Sandia National Laboratories, is suitable for calculating source terms and simulating severe accident phenomena of nuclear power plants. Prior to simulating a severe accident transient with MELCOR, the initial steady-sta
Autor:
David P. Wagner, Larry A. Minton, John P. Gaertner, B. Thierry Meslin, Hymie Sol Shapiro, James Edward Smith, Yean-Chuan Yeh, Jyh-Tong Teng, David H. Worledge, Ian B. Wall, Hans J. Wingender, R. Leicht, Nathan Siu, Ali Mosleh, Michel Bloch, Daniel Dussarté, Jean-Louis Pierrey, Takeshi Matsuoka, Michiyuki Kobayashi, Kazuo Takemura, Henk W. Kalfsbeek, Shih-Kuei Cheng, Selim Sancaktar, David R. Sharp, B. John Garrick, Yukio Ishiguro, Keisuke Okumura, Corinne Bangil, Gerard Gambier, Michel Soldevila
Publikováno v:
Nuclear Technology. 84:225-230
Autor:
Shih-Kuei Cheng
Publikováno v:
Nuclear Technology. 84:305-314
A model for the potential reactor coolant pump seal loss-of-coolant accident in a Westinghouse Electric Corporation pressurized water reactor following a loss of component cooling water (CCW) is developed based on state-of-the-art knowledge. The pote
Autor:
Neil E. Todreas, Shih-Kuei Cheng
Publikováno v:
Nuclear Engineering and Design. 92:227-251
Consistent hydrodynamic models for subchannel friction factors and mixing parameters in wire-wrapped rod bundles have been developed for use in subchannel analysis codes. Both flow regime and geometry effects are taken into account in these models. T
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