Zobrazeno 1 - 10
of 36
pro vyhledávání: '"Joseph A. Naser"'
Publikováno v:
IEEE Sensors Journal. 17:311-322
In the current competitive energy market, the nuclear industry is committed to lowering operations and maintenance costs and increasing productivity and efficiency while maintaining a safe and reliable operation. The present nuclear power plant opera
Publikováno v:
Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors.
Plant configuration management is an essential element of nuclear power plant (NPP) design, construction, and operation. In the current operating model of NPPs, plant configuration management is highly dependent on large technical staffs. This depend
Publikováno v:
Nuclear Technology. 141:3-9
Deregulation of the electric utilities has made a major impact on nuclear power plants. To be competitive, more emphasis is being put on cost-effective production of electricity with a more critical look at whether a system should be modernized due t
The Light Water Reactor Sustainability (LWRS) Program is a research and development (R&D) program sponsored by the U.S. Department of Energy (DOE). The program is operated in close collaboration with industry R&D programs to provide the technical fou
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::249e7a79fb1450ecd0b5459451b4400d
https://doi.org/10.2172/974785
https://doi.org/10.2172/974785
Autor:
Steven A. Arndt, Richard Thomas Wood, Don W. Miller, Donald D. Dudenhoeffer, Leonard J. Bond, John O'Hara, David Eugene Holcomb, Edward L. Quinn, Bruce P. Hallbert, Joseph A. Naser
Publikováno v:
Volume 3: Thermal Hydraulics; Instrumentation and Controls.
Instrumentation, controls, and human-machine interfaces are essential enabling technologies that strongly influence nuclear power plant performance and operational costs. The nuclear power industry is currently engaged in a transition from traditiona
Autor:
Joseph A. Naser
Publikováno v:
Expert Systems and Computer Simulation in Energy Engineering: Selected Papers from the Second International Forum.
Autor:
Lance J. Agee, M. P. Paulsen, E. D. Hughes, K. R. Katsma, Clayton S. Miller, James Robert White, Richard D. Hentzen, Yoshinori Naruko, Toshihisa Ishida, Yoshimi Tanaka, Yoshiaki Futamura, A. A. Farooq Ansari, Kevin J. Burns, Douglas K. Beller, Quazi A. Haque, Stephen P. Schultz, Mario V. Bonaca, Albert Gharakhani, Richard W. Sterner, Jason Chao, V. K. (Bindi) Chexal, William H. Layman, David A. Rautmann, Craig E. Peterson, Larry W. Cress, Salvador Ranatza, T. Gary Broughton, N. G. Trikouros, Karel L. Papez, Daniel H. Risher, Michael E. Garrett, Samuel L. Forkner, T. A. Keys, George W. Perry, M. Wesley Waddell, Karl Hornyik, Joseph A. Naser, Neil M. Howard, Mitchell J. Krasnopoler, Lawrence A. Casper, Arvid M. Jensen, Kendall G. Magill, Penny M. Wikoff, William T. Li, Ching L. Wu, Osvaldo Fiorella, Manlio Mangia, Elio Oliveri
Publikováno v:
Nuclear Technology. 61:135-142
Autor:
H. Jüntgen, K. H. van Heek, Charles Yung Fen Chang, John Skears, J. N. Chung, P. S. Ayyaswamy, J. J. Koelling, G. E. Hansen, C. C. Byers, E. E. Gruber, Bal Raj Sehgal, Joseph A. Naser, Ching-lu Lin, Walter B. Loewenstein, R. M. Alire, J. K. Fink, J. J. Heiberger, R. Kumar, R. A. Blomquist, G. Schulze, H. Würz, H. J. Petroski
Publikováno v:
Nuclear Technology. 35:575-578
Autor:
Joseph A. Naser
Publikováno v:
Nuclear Technology. 61:313-328
The RETRAN-01 system thermal-hydraulics analysis code has been used to simulate the Peach Bottom Unit 2 boiling water reactor (BWR) turbine trip tests. Since these studies have been performed, a second version of the code, RETRAN-02, has been develop
Autor:
Joseph A. Naser
Publikováno v:
Nuclear Technology. 54:373-379
The RETRAN system thermal-hydraulics analysis code has been used to model a series of three turbine trip tests. These three tests were performed at the Peach Bottom Unit 2 (PB2) boiling water reactor (BWR) during April 1977. A detailed description of