Zobrazeno 1 - 5
of 5
pro vyhledávání: '"T. G. Broughton"'
Autor:
M. Levenson, F. Rahn, D. O. Campbell, A. P. Malinauskas, W. R. Stratton, H. A. Morewitz, G. W. Parker, G. E. Creek, H. Bunz, W. Schikarski, W. Schöck, R. R. Smith, Z. T. Mendoza, C. A. Stevens, R. L. Ritzman, R. K. Hilliard, A. K. Postma, M. A. Feraday, Emile Vanden Bemd, R. L. Nelson, N. Parkinson, W. C. L Kent, Dennis L. Berr, T. G. Broughton, P. S. Wal, Yurii Mikhailovich Karatsu, G. S. Lellouche, Walter E. Clark, W. B. Howerton, J. C. Mailen, R. Kolowith, D. V. Archer, F. E. Holt, W. C. Miller, J. J. McCown, E. B. J. Kleis, H. van Dam
Publikováno v:
Nuclear Technology. 53:89-95
Autor:
T. G. Broughton, N. G. Trikouros
Publikováno v:
Nuclear Technology. 54:342-357
This paper provides examples of RETRAN code applications to illustrate the use of the code in situations requiring control system/thermal-hydraulic interaction, inference of system behavior, and benchmarked models. All of these analyses were performe
Autor:
T. G. Broughton, L. C. Pwu
Publikováno v:
Nuclear Technology. 54:358-363
This paper discusses the use of the RETRAN system analysis code to simulate a Three Mile Island Unit 2 overfeeding transient that occurred during a plant startup The simulation of the startup overfeeding shows that the RETRAN two-loop model is capabl
Autor:
C. C. Lin, C. R. Pao, J. S. Wiley, W. R. DeHollander, J. Hadermann, J. Patry, Katsuro Takahashi, Yoshiaki Himeno, Nobutomo Takahashi, June Takahashi, Tatsuro Iguchi, J. H. McFadden, M. P. Paulsen, G. C. Gose, C. E. Peterson, N. L. Ellis, J. A. McClure, Joseph A. Naser, Bal Raj Sehgal, Lance J. Agee, James R. White, Charles E. Hendrix, V. K. Chexal, W. H. Layman, W. W. Brown, G. B. Caldwell, T. G. Broughton, N. G. Trikouros, L. C. Pwu, Gregg B. Swindlehurst, E. Lin, Y. H. Cheng, J. K. Hsiue, H. J. Diamond, W. G. Lee, James T. Cronin, Bruce C. Slifer, D. P. Griggs, T. J. Honan, E. D. Hughes, L. J. Agee, Gian Piero Celata, Franco Vittorio Frazzoli
Publikováno v:
Nuclear Technology. 54:245-252
Autor:
P. S. Walsh, T. G. Broughton
Publikováno v:
Nuclear Technology. 53:217-225
This paper presents a method which has been developed to aid pressurized water reactor (PWR) power plant operators in monitoring the transition of the plant from normal full-power conditions to expected post-reactor-trip conditions. Using a pressure-