Zobrazeno 1 - 10
of 27
pro vyhledávání: '"Guy L. Fredrickson"'
Autor:
Jerry Howard, Allison Harward, Tae-Sic Yoo, Levi Gardner, Guy L. Fredrickson, Michael F. Simpson, Krista Carlson
Publikováno v:
Nuclear Technology. 208:310-317
Molten eutectic LiCl-KCl salt is a widely used electrolyte for electrorefining uranium from spent nuclear fuel. Due to the hygroscopic nature of this salt, such operations must be performed under c...
Autor:
Michael N. Patterson, Toni Y. Karlsson, Vivek Utgikar, Tae-Sic Yoo, DeeEarl Vaden, Guy L. Fredrickson
Publikováno v:
Journal of Nuclear Materials. 520:87-95
This work examines the change in liquidus temperature of the salt used in the Mk-IV electrorefiner at the Idaho National Laboratory during processing campaigns of sodium-bonded driver fuels from Experimental Breeder Reactor II and the Fast Flux Test
Autor:
Tae-Sic Yoo, William C. Phillips, Guy L. Fredrickson, Michael R. Shaltry, Guoping Cao, Prabhat K. Tripathy, Ruchi Gakhar, Toni Y. Karlsson, Ammon N. Williams, David C. Horvath, Ken C. Marsden, Steven D. Herrmann, Robert O. Hoover
Publikováno v:
Journal of The Electrochemical Society. 166:D645-D659
Autor:
Ryan N. Searle, Gregory G. Galbreth, Tae-Sic Yoo, J.C. Price, Guy L. Fredrickson, DeeEarl Vaden, Eric J. Flynn, Michael N. Patterson
Publikováno v:
Progress in Nuclear Energy. 143:104037
Experimental Breeder Reactor II (EBR-II) operated from 1964 to 1994 as one of the first sodium-cooled fast reactors to use sodium-bonded metallic driver fuels and blankets. EBR-II was a testbed for fuel development and reactor design principles. Foll
Publikováno v:
Journal of Nuclear Materials. 510:551-555
The Mark-IV electrorefiner contains a molten-salt/molten-cadmium system for electrorefining uranium. The anode basket is loaded with chopped sodium-bonded metallic driver fuel. For the present investigation, the bulk of the fuel was U 10Zr binary all
Publikováno v:
Journal of Nuclear Materials. 508:521-529
A dissolution experiment is performed in order to examine the kinetics of uranium isotope equilibration in a molten salt and cadmium system. The salt contains a solute concentration of UCl3 in LiCl-KCl eutectic and the cadmium contained dissolved ura
Autor:
Guy L. Fredrickson, Tae-Sic Yoo
Publikováno v:
Journal of Nuclear Materials. 508:51-62
In the field of pyroprocessing of used nuclear fuels, liquid cadmium is applied in different ways to recover transuranics from molten salt, while effecting some degree of separations between transuranics and lanthanides. A model of the separation per
Autor:
Brandon Day, Nikunja Shrestha, Steven M. Frank, Guy L. Fredrickson, Vivek Utgikar, Krishnan S. Raja
Publikováno v:
ECS Transactions. 85:15-23