Zobrazeno 1 - 10
of 21
pro vyhledávání: '"B. R. Westphal"'
Autor:
B. R. Westphal, S. X. Li
Publikováno v:
Metallurgical and Materials Transactions B. 50:799-807
Upon the re-examination of two experimental studies, additional thermophysical data pertaining to the uranium-rich portion of the uranium-plutonium binary phase diagram have been elucidated. The first study involved the analysis of solidification coo
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:
Annals of Nuclear Energy. 135:106970
The method of input accountancy for a used oxide fuel reprocessing plant has been based on the sampling of a homogenized liquid stream of dissolved used oxide fuel. This article presents an alternative sampling strategy where samples are taken direct
Publikováno v:
Journal of Nuclear Materials. 457:241-245
An alternative method to sampling and chemical analyses has been developed to monitor the concentration of zirconium in real-time during the casting of uranium products from the pyroprocessing of used nuclear fuel. The method utilizes the solidificat
Autor:
Tae-Sic Yoo, B. R. Westphal, Steven M. Frank, T. P. O’Holleran, J. J. Giglio, Daniel G. Cummings, K. C. Marsden, M. N. Patterson, Kenneth J. Bateman, Paula A. Hahn, William M. McCartin
Publikováno v:
Metallurgical and Materials Transactions A. 46:83-92
As part of the pyrometallurgical treatment of used Experimental Breeder Reactor-II fuel, a metal waste stream is generated consisting primarily of cladding hulls laden with fission products noble to the electrorefining process. Consolidation by melti
Publikováno v:
Advances in Molten Slags, Fluxes, and Salts: Proceedings of the 10th International Conference on Molten Slags, Fluxes and Salts 2016 ISBN: 9783319486253
Advances in Molten Slags, Fluxes, and Salts: Proceedings of the 10th International Conference on Molten Slags, Fluxes and Salts
Advances in Molten Slags, Fluxes, and Salts: Proceedings of the 10th International Conference on Molten Slags, Fluxes and Salts
Given the renewed interest in uranium from the pyroprocessing of used nuclear fuel in a molten salt system, the two biggest hurdles for marketing the uranium are radiation levels and transuranic content. A radiation level as low as possible is desire
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::53e03217a119d32f9e32ada88d3b512b
https://doi.org/10.1002/9781119333197.ch82
https://doi.org/10.1002/9781119333197.ch82
Publikováno v:
Metallurgical and Materials Transactions A. 40:2861-2866
As part of the spent fuel treatment program at the Idaho National Laboratory, alternate crucible materials are being developed for the processing of uranium and salt. The separation of salt (LiCl/KCl based) from uranium is performed in an inductively
Autor:
Shelly X. Li, R. W. Benedict, B. R. Westphal, G. L. Frederickson, T. A. Johnson, DeeEarl Vaden
Publikováno v:
Scopus-Elsevier
ResearcherID
ResearcherID
An engineering-scale pyroprocessing integrated efficiency test was conducted with sodium-bonded, spent Experimental Breeder Reactor II drive fuel elements. The major pieces of equipment used to con...
Publikováno v:
Separation Science and Technology. 43:2695-2708
A head-end processing step, termed DEOX for its emphasis on decladding via oxidation, is being developed for the treatment of spent oxide fuel by pyroprocessing techniques. The head-end step employs high temperatures to oxidize UO2 to U3O8 resulting