Zobrazeno 1 - 10
of 16
pro vyhledávání: '"Samir M. Sami"'
Autor:
M. Kraitem, Samir M. Sami
Publikováno v:
Nuclear Technology. 83:81-92
An improved digital computer model DYNAM/US has been developed for predicting thermally induced instability in a once-through boiling flow with superheat. The present model includes newly developed dynamic schemes to calculate subcooled boiling, tran
A Transient Two-Phase Velocity Difference Model for Drift Calculation in CANDU Thermohydraulic Codes
Autor:
Samir M. Sami
Publikováno v:
Nuclear Technology. 75:283-297
A realistic velocity difference scheme has been developed for calculating the drift parameters in both horizontally and vertically oriented sections of the primary heat transport systems of CANDU reactors. This model predicts the unequal velocity eff
Autor:
William M. Davidson, Alan K. Morimoto, Mary M. Moya, J. Lee Schoeneman, Siegfried Thunborg, Gregory P. Starr, Samir M. Sami, C. Tran, Mo-chen Hsu, Norio Naito, Akira Sakuma, Kei Shigeno, Nobuyuki Mori, Jae-Joo Ha, Tunc Aldemir, Fahmy M. Hussein, Mohamed A. Obeid, Khalid S. El-Malahy, Stephen E. Binney, Richard D. Harris, Tatsuhiko Uda, Yoshihiro Ozawa, Hajime Iba, Hans Wanner, Othar K. Tallent, Earl W. McDaniel, Karen E. Dodson, Terry T. Godsey, Alexander P. Murray, Carol Braester, Roger Thunvik, Hyong Chol Kim, Ming-Yuan Hsiao, Samuel H. Levine
Publikováno v:
Nuclear Technology. 79:243-247
Autor:
William J. Garland, Simon H. Pang, Dov Ingman, Leib Reznik, Samir M. Sami, Mario Dalle Donne, Giacinto P. Tartaglia, Shlomo Ron, Zeev B. Alfassi, Michael Baer, Erich Zimmer, Joachim Borchardt, Budhi Sagar, Paul W. Eslinger, Robert G. Baca, Dhanpat Rai, Janet A. Schramke, Dean A. Moore, Gary L. McVay, Azar P. Majidi, Michael A. Streicher, R. S. Piascik, K. E. Moore
Publikováno v:
Nuclear Technology. 75:235-238
Autor:
Samir M. Sami, C. H. Le, Jack L. Collins, Morris F. Osborne, R. A. Lorenz, Seihiro Itoya, Masami Kato, Nobuaki Abe, Hideo Nagasaka, Haim Tobias, Efraim Taragan, Yoram Oren, Abraham Soffer, Timothy S. Roth, A. Biancheria, Hideo Hirayama, Dick Duffey, Peter F. Wiggins, Philippe J. Vernier, Philippe Solignac, Y. L. Yuan, R. P. Gardner, K. Verghese, Cheng-Hsin Mao, Pao-Shan Weng, Gerard L. Hofman
Publikováno v:
Nuclear Technology. 77:1-5
Autor:
M. Kraitem, Samir M. Sami
Publikováno v:
Nuclear Technology. 77:237-246
A dynamic reliable model has been developed to predict the steam volume fraction and the dynamics of flow regime boundaries in flow boiling. The model was established from the void propagation equation and the advanced dynamic drift-flux scheme. Nume
Autor:
Samir M. Sami
Publikováno v:
Nuclear Technology. 72:7-23
A digital computer approach for predicting the dynamic response of surge tanks is presented. The applications of different models are presented for analyzing the primary pressure transients of CANDU reactors. Conservation equations for deformable con
Autor:
Samir M. Sami, Yoshiro Asahi, Hiroaki Wakabayashi, Stanley K. Widener, H. Deuber, Yassin A. Hassan, Chaitanyamoy Ganguly, Parameshwar Venkappa Hegde, Gyan Chand Jain, Uddharan Basak, Radhey Shyam Mehrotra, Sukomal Majumdar, Pradip Ranjan Roy, David A. Wesley, M. Michael Yovanovich, John A. Andersen, Hiroshi Kamizono, Shizuo Kikkawa, Shingo Tashiro, Haruto Nakamura, Emilio Tassoni, Ferruccio Gera, Dov Ingman, Amos Notea, Naozo Hattori, Kenji Hayashi
Publikováno v:
Nuclear Technology. 72:1-5
Autor:
Samir M. Sami, C. H. Le
Publikováno v:
Nuclear Technology. 77:7-17
A dynamic void quality perturbation model has been developed to improve the capabilities of the NUFREQ code with respect to local void perturbation calculations. The present model calculates the local void perturbation in terms of the local quality p
Autor:
Samir M. Sami, C. Tran
Publikováno v:
Nuclear Technology. 79:260-273
The development of an improved model to determine the dynamic response of the primary heat transport pump during severe transients in a Canada deuterium uranium reactor is presented. A lumped parameter model is proposed. A control volume formulation