Zobrazeno 1 - 6
of 6
pro vyhledávání: '"Frank E. Tippets"'
Publikováno v:
Nuclear Technology. 86:22-29
The Power Reactor Inherently Safe Module program is under U.S. Department of Energy sponsorship to develop a conceptual design for an advanced sodium-cooled liquid-metal reactor plant. This design is intended to provide significant reductions in plan
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2c832012b02b859229cb0fa98c6b229a
https://doi.org/10.13182/nt89-a34277
https://doi.org/10.13182/nt89-a34277
Autor:
Noriaki Takahashi, Hideaki Morishita, Naomichi Kanegae, Akihiro Niimi, John F. Carew, Robert C. Berglund, Frank E. Tippets, Leroy N. Salerno, Liq-Ji Yuan, Pao-Shan Weng, Cheng-Chang Chan, Tae Woon Kim, Sang Hoon Han, Kun Joong Yoo, Russell D. Mosteller, Peter J. Jensen, Michael J. Anderson, Laurance D. Eisenhart, Rana Abdollahian, Jason Chao, Walter J. Eich, Katsuyuki Kawashima, Ratib A. Karam, Werner Faubel, Sameh A. Ali, Elie Saad, Normand Laurent Laberge, Xiangdong Feng, C. H. King, M. S. Ouyang, B. S. Pei, S. C. Lee, Frank Schmittroth, Miriam A. Myjak, A. M. Shahub, M. M. R. Williams
Publikováno v:
Nuclear Technology. 86:1-6
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3eca8936294a050d553bbff3ad48137e
https://doi.org/10.13182/nt89-a34274
https://doi.org/10.13182/nt89-a34274
Publikováno v:
Nuclear Engineering and Design. 109:79-86
The Power Reactor Inherently Safe Module (PRISM) is a sodium cooled breeder reactor, conceived by the General Electric Company, which incorporates a number of innovative features with the objective of simultaneously achieving favorable power plant sa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8d68ce0c629e386f1ab05fc2ab2f57ec
https://doi.org/10.1016/0029-5493(88)90144-6
https://doi.org/10.1016/0029-5493(88)90144-6
Publikováno v:
22nd Intersociety Energy Conversion Engineering Conference.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a02cf84a7d4041ab6acd6bd7858f8dbc
https://doi.org/10.2514/6.1987-9209
https://doi.org/10.2514/6.1987-9209
Autor:
Frank E. Tippets
Publikováno v:
ASME 1959 Gas Turbine Power Conference and Exhibit.
Analytical comparison is made of the relative heat-transfer-area requirements of carbon dioxide and helium in nuclear-powered gas-turbine cycles and gas cooled reactor–steam turbine systems. Helium is shown to require considerably less heat-transfe
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c88ccc83264bd70fa8b1e2c1ad58a112
https://doi.org/10.1115/59-gtp-14
https://doi.org/10.1115/59-gtp-14
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