Zobrazeno 1 - 10
of 11
pro vyhledávání: '"Richard G. Ambrosek"'
Autor:
Robert P. Wadkins, Richard G. Ambrosek
Publikováno v:
Nuclear Technology. 97:344-351
This paper reports that aluminum-clad fuel plates generally used in nuclear research reactors have unique heat transfer characteristics that require three-dimensional heat conduction modeling without large conservatism. A model, ATR SINDA, was writte
This report provides documentation of the physics analysis performed to determine the linear heat generation rate (LHGR) and burnup calculations for the Advanced Fuel Cycle Initiative (AFCI) tests, AFC-1D, AFC-1H, and AFC-1G. The AFC-1D and AFC-1H te
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6c485fdda7e2fcd91e02f206c233f138
https://doi.org/10.2172/911238
https://doi.org/10.2172/911238
Publikováno v:
Volume 4.
The DOE Advanced Fuel Cycle Initiative and Generation IV reactor programs are developing new fuel types for use in the current Light Water Reactors and future advanced reactor concepts. The Advanced Gas Reactor program is planning to test fuel to be
Publikováno v:
Heat Transfer: Volume 2.
In 2000, British Nuclear Fuels Limited (BNFL) commissioned an irradiation program at the United States Department of Energy’s Idaho National Engineering and Environmental Laboratory (INEEL) to assess the effects of extended operating scenarios upon
Publikováno v:
10th International Conference on Nuclear Engineering, Volume 4.
Post-irradiation examination (PIE) has indicated an increase in the outer diameter of fuel pins being irradiated in the Advanced Test Reactor (ATR) for the MOX irradiation program. The diameter increase is the largest in the region between fuel pelle
Publikováno v:
Heat Transfer: Volume 4.
Safety requirements many times require specific evaluations for experiment operating conditions during periods of postulated off-normal operation. A unique experimental facility in the Advanced Test Reactor was designed for enhancement of the neutron
Autor:
Richard G. Ambrosek, Fred W. Ingram
Publikováno v:
Heat Transfer: Volume 4.
Test reactors are unique in that the core configuration may change with each operating interval. The process of safety analyses for test reactors at the Idaho National Engineering and Environmental Test Reactor Area has evolved as the computing capab
Publikováno v:
Nuclear Technology. 46:465-472
A study of critical heat flux (CHF) in a close-packed bundle of electrically heated rods which simulated the closely spaced nuclear fuel rods of the Power Burst Facility (PBF) was performed. The study examined the effects that close rod spacing and r
Autor:
T. Ginsberg, O. C. Jones, J. C. Chen, H. Deuber, J. G. Wilhelm, R. A. Lorenz, J. L. Collins, A. P. Malinauskas, J. J. Pyun, K. A. Williams, Charles E. Cartmill, Jorma Arros, J. H. Pitts, E. W. McCauley, R. E. Leadon, N. A. Lurie, V. K. Dhir, W. E. Kastenberg, D. W. Varela, A. Renard, G. Evrard, U. Wehmann, Robert P. Wadkins, Richard G. Ambrosek, Michael W. Young, Hsu-Chieh Yeh, Cleon E. Dodge, Lawrence E. Hochreiter, A. Segev, R. E. Henry, S. G. Bankoff, David J. Diamond, Hsiang-Shou Cheng, Cl. Vandenberg, H. Bonet, A. Charlier, F. Motte, J. C. Luxat, G. M. Frescura, S. K. Bhattacharyya, D. C. Wade, R. G. Bucher, D. M. Smith, R. D. McKnight, L. G. LeSage, W. P. Barthold, J. C. Beitel, P. S. K. Lam, Y. Orechwa, S. F. Su, R. B. Turski, G. Enderle, F. Katz, H. Mösinger, E. G. Schlechtendahl, K. Stölting, D. J. Kowalski, V. J. Esposito, J. Y. Boivin, H. Karwat, H. Albrecht, V. Matschoss, H. Wild, A. J. Buslik, R. E. Hall, Gérard Kurka, Alain Harrer, Pierre Chenebault, J. L. Quinet, L. Lannou, N. P. Wilburn, D. E. Smith, R. E. Baars, D B. Atcheson, B. W. Spencer, Peter K. Mast, James H. Scott, L. Mergan, J. Storrer, R Verbeke, J. P. Cordier
Publikováno v:
Nuclear Technology. 46:379-390
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