Zobrazeno 1 - 10
of 157
pro vyhledávání: '"E. E. Feldman"'
Autor:
E. E. Feldman, B. Dionne, L. P. Foyto, M. Kallimullah, K. Kutikkad, J. C. McKibben, A. P. Olson, N. J. Peters, J. G. Stevens, J. A. Stillman, null (University of Missouri-Columbia)
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c89be2bc2d1f0b0360112e206404223d
https://doi.org/10.2172/1129374
https://doi.org/10.2172/1129374
Autor:
R .B. Vilim, E. E. Feldman
Passive safety in the Very High Temperature Reactor (VHTR) is strongly dependent on the thermal performance of the Reactor Cavity Cooling System (RCCS). Scaled experiments performed in the Natural Shutdown Test Facility (NSTF) are to provide data for
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cf78d153959af631a5147d6ae654b0ef
https://doi.org/10.2172/915029
https://doi.org/10.2172/915029
Nuclear systems codes are being prepared for use as computational tools for conducting performance/safety analyses of the Very High Temperature Reactor. The thermal-hydraulic codes are RELAP5/ATHENA for one-dimensional systems modeling and FLUENT and
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::30a257e10ecfab17614afd6b8576d587
https://doi.org/10.2172/925358
https://doi.org/10.2172/925358
Autor:
T. Allen, J. Gan, E. A. Hoffman, E. E. Feldman, H. Ludewig, I. U. Therios, R. F. Kulak, C. P. Tzanos, T. Y. C. Wei, L. Y. Cheng, P. Sabharwall, T. C. Totemeier, J. Jo, R. Nanstad, K. D. Weaver, William F. Gale, W. Corwin, Venu G. Krishnardula, T. Marshall, Jeffrey W. Fergus
The gas-cooled fast reactor (GFR) was chosen as one of the Generation IV nuclear reactor systems to be developed based on its excellent potential for sustainability through reduction of the volume and radio toxicity of both its own fuel and other spe
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e70e453e7e29fd77d147ee87e9818d06
https://doi.org/10.2172/911777
https://doi.org/10.2172/911777
Autor:
William F. Gale, M. J. Driscoll, K. D. Weaver, R. B. Vilim, M. Golay, E. A. Hoffman, T. C. Totemeier, M. K. Meyer, K. Czerwinski, G. Apostolakis, J. Gan, E. E. Feldman, D. E. Clark, T. Y. C. Wei
The gas-cooled fast reactor (GFR) was chosen as one of the Generation IV nuclear reactor systems to be developed based on its excellent potential for sustainability through reduction of the volume and radio toxicity of both its own fuel and other spe
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::259e51b321384b569d601b5f827c3224
https://doi.org/10.2172/911236
https://doi.org/10.2172/911236
Autor:
A. Gandini, T. Y. C. Wei, W. S. Yang, E. A. Hoffman, Michael Todosow, M. Fatone, E. E. Feldman, T. A. Taiwo, M. Salvatores, Robert Hill, J. W. Holland, I. G. Prokofiev, G. Palmiotti
The objective of this project is to develop a conceptual design of a particle-bed, gas-cooled fast reactor (PB-GCFR) core that meets the advanced reactor concept and enhanced proliferation-resistant goals of the US Department of Energy's NERI program
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::44cf3ea7847385b6ab83c41c41acf482
https://doi.org/10.2172/816765
https://doi.org/10.2172/816765
The gas-cooled fast reactor (GFR) was chosen as one of the Generation IV nuclear reactor systems to be developed based on its excellent potential for sustainability through reduction of the volume and radiotoxicity of both its own fuel and other spen
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::329ac8eeae5f8a6b48edec5b0b934275
https://doi.org/10.2172/910729
https://doi.org/10.2172/910729
Autor:
L. K. Chang, E. E. Feldman
Publikováno v:
Numerical Heat Transfer. 2:373-385
The TCLUSTI computer code has been developed to study the transient thermal performance of a liquid metal fast breeder reactor (LMFBR) subassembly that is thermally coupled to its six immediate neighbors. Each of the seven subassemblies may be either