Zobrazeno 1 - 10
of 21
pro vyhledávání: '"William H. Layman"'
Publikováno v:
Nuclear Engineering and Design. 157:469-480
Design requirements for the advanced light water reactor (ALWR) have been developed so as to provide high assurance of containment integrity even in the event of a severe accident. The containment integrity requirements are in the form of two design
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::75280e967eff52587dad0b72dea0ed58
https://doi.org/10.1016/0029-5493(95)01004-2
https://doi.org/10.1016/0029-5493(95)01004-2
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d8b83ac9572102af0ca3601f19276f7a
https://doi.org/10.13182/nt83-a33185
https://doi.org/10.13182/nt83-a33185
Publikováno v:
Nuclear Technology. 83:252-273
The Nuclear Safety Analysis Center (NSAC) at the Electric Power Research Institute has a Generic Safety Analysis Program to help resolve high-priority safety issues. Several high-priority safety is...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a6de9336cd355bd60ac27b53de88582d
https://doi.org/10.13182/nt88-a34140
https://doi.org/10.13182/nt88-a34140
Autor:
Lance J. Agee, Jorge Arpa, Alan S. Fatemi, S. K. Mathavan, Bruce E. Schmitt, E. D. Hughes, K. R. Katsma, M. P. Paulsen, G. D. Miller, J. G. Refling, A. J. Roscioli, S. A. Somma, C. A. Kukielka, L. M. Olson, Ernest V. Moore, S. F. Deng, K. K. Chitkara, B. B. Chu, Adel Alapour, Robert A. Hommerson, Craig E. Peterson, V. K. (Bindi) Chexal, William H. Layman, Richard D. Hentzen, Garry C. Gose, Richard F. Farman, Charles E. Hendrix, Jason Chao, Yine-Ping Ting, Talmage B. Clements, M. A. Alammar, Norman T. Simms, Vincent P. Manno, Michael W. Golay, Terry F. Rees, Jess M. Cleveland, Kenneth L. Nash
Publikováno v:
Nuclear Technology. 70:1-6
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::49ffed49a345d0764b710ec980fa1ecd
https://doi.org/10.13182/nt85-a33657
https://doi.org/10.13182/nt85-a33657
Publikováno v:
Nuclear Technology. 76:172-184
The reactor protection system (both analog- and digital-based) setpoints of Combustion Engineering nuclear steam supply systems were examined to determine the feasibility of scram reduction by relaxing these setpoints. Representative safety analyses,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::689d0188733762060dd3426c5e29adf9
https://doi.org/10.13182/nt87-a33908
https://doi.org/10.13182/nt87-a33908
Autor:
U. S. Rohatgi, Pradip Saha, V. K. Chexal, Jong Ho Lee, Soon Heung Chang, Christine Yuelys-Miksis, Harald Moers, Hanns Klewe-Nebenius, Hans J. Ache, Pao-Shan Weng, Hseuh-Hsing Cheng, Chuan-Chung Hsu, Kuan-Han Sun, Jeffery David Lewins, Tsunetaka Banba, Takashi Murakami, Hideo Kimura, Lance J. Agee, Thomas L. Temple, Terry J. Garrett, Steven W. Sorrell, Jason Chao, William H. Layman, Gary Vine, Robert O. Montgomery, Kenneth L. Peddicord, Roger L. Boyer, Charles R. Albury, Lance G. Riniker, Kevin B. Ramsden, Laurence M. Olson, Trevor L. Cook, Steven M. Mirsky, Bruce Ching, Chong Chiu, Charles W. Forsberg
Publikováno v:
Nuclear Technology. 76:1-8
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c029d8d3d8c4f2057960dac55ffde49b
https://doi.org/10.13182/nt87-a33891
https://doi.org/10.13182/nt87-a33891
Autor:
Craig E. Peterson, Jason Chao, Larry W. Cress, William H. Layman, David A. Rautmann, V. K. (Bindi) Chexal
Publikováno v:
Nuclear Technology. 61:224-237
The RETRAN-02 and DYNODE-P thermal-hydraulic codes were compared against actual Prairie Island plant data from a steam generator tube break incident that occurred on October 2, 1979. The predictions from the code calculations compare well with actual
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::709ff004cbf1f4f279bdf926b56e7923
https://doi.org/10.13182/nt83-a33193
https://doi.org/10.13182/nt83-a33193
Autor:
Lance J. Agee, Peter J. Jensen, V. K. (Bindi) Chexal, Jason Chao, William H. Layman, M. P. Paulsen, B. E. Griebenow, L. R. Feinauer, J. H. McFadden, V. K.(Bindu) Chexal, Gary Vine, Adi R. Dastur, Steven J. Ganthner, A. Frank Wenger, James F. Harrison, J. J. Martínez Caballero, Pablo García Sedano, Jorge Arpa, Jose Ramos, Juan R. Villar, Steven P. Nesbit, Richard J. Gerling, Gregg B. Swindlehurst, Mansur A. Alammar, Ronald V. Furia, Jimmy H. Chin, Chandrakant B. Mehta, Joseph O. Erb, James G. Miller, Shie-Jeng Peng, John Sorensen
Publikováno v:
Nuclear Technology. 83:235-240
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::121d953e4821228a7200be77fb5ac30e
https://doi.org/10.13182/nt88-a34138
https://doi.org/10.13182/nt88-a34138
Publikováno v:
Nuclear Technology. 76:113-125
Several scram setpoints were analyzed for the purpose of reducing scram frequency in a Westinghouse four-loop plant. The results showed that the low-low steam generator (SG) level setpoint can be eliminated when reactor power is 50% or less during a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1416d3cd9355a20354e79dd720a93ba6
https://doi.org/10.13182/nt87-a33903
https://doi.org/10.13182/nt87-a33903
Autor:
William H. Layman, Craig E. Peterson, Richard D. Hentzen, V. K. (Bindi) Chexal, Garry C. Gose
Publikováno v:
Nuclear Technology. 70:74-83
Under certain anticipated transient without scram (ATWS) sequences for a boiling water reactor, it would be desirable to reduce system power, particularly where the primary system has been isolated by closure of all main steam isolation valves and is
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9699eab324ccf44060a9a455539ead04
https://doi.org/10.13182/nt85-a33665
https://doi.org/10.13182/nt85-a33665