Zobrazeno 1 - 5
of 5
pro vyhledávání: '"Mukesh Tayal"'
Publikováno v:
Nuclear Technology. 76:209-220
The ELOCA-A code models the thermomechanical behavior of CANDU fuel elements during high-temperature transients such as loss-of-coolant accidents. Calculations include sheath and pellet temperatures, strains (including creep), sheath oxidation, and b
Autor:
Karen H. Koger, M. Jonathan Haire, Brett L. Humphrys, Jay F. Manneschmidt, Keiichi Setoguchi, Ryodai Nakai, Kazunori Sasaki, Naotaka Terashita, Takamichi Ogino, Makoto Osaki, Akira Kanagawa, Jan-Li Wang, Jay F. Kunze, L. C. Lewis, J. P. Henscheid, Mukesh Tayal, Lorne D. Macdonald, Erl Kohn, Walter P. Dovigo, T. Sampat Sridhar, Michael P. Manahan, Xiangdong Feng, Ian L. Pegg, Aaron Barkatt, Pedro B. Macedo, Samuel J. Cucinell, Shantao Lai, R. K. S. Rathore, P. Munshi, P. Arora, S. D. Malik, A. K. Vaish, K. S. Singh, U. Singh
Publikováno v:
Nuclear Technology. 85:245-249
Publikováno v:
Nuclear Technology. 85:300-313
The GASOUT computer code calculates fission gas release, activity release, and fission product swelling in a Canada deuterium uranium (CANDU) fuel element during transient (nonequilibrium) conditions such as load following, postulated accidents invol
Autor:
John C. Lee, Sin Tao Hsue, Mukesh Tayal, Ed Mischkot, Harve E. Sills, A. W. L. Segel, Masanori Takahashi, Masayuki Muroi, Atsuyuki Inoue, Masahiro Aoki, Makoto Takizawa, Kenkichi Ishigure, Norihiko Fujita, Kune Yull Suh, Neil E. Todreas, Pao-Shu Chang, Yau-Hui Ho, Chien Chung, Liq-Ji Yuan, Pao-Shan Weng, Tunc Aldemir, Steven A. Arndt, Don W. Miller, Alan B. Harker, John F. Flintoff, Peter J. Jensen, James F. Lang, Jason Chao, Kent D. Richert, Thomas J. Downar
Publikováno v:
Nuclear Technology. 76:197-201
Akademický článek
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