Zobrazeno 1 - 10
of 34
pro vyhledávání: '"Tracy S. Rudisill"'
Autor:
Jarrod M. Gogolski, Tracy S. Rudisill
Publikováno v:
Industrial & Engineering Chemistry Research. 62:4466-4469
Autor:
Jarrod M. Gogolski, Kathryn M. L. Taylor-Pashow, Tracy S. Rudisill, Michael L. Restivo, John M. Pareizs, Robert J. Lascola, Patrick E. O’Rourke, William. E. Daniel
The dissolution of used nuclear fuel generates a variety of off-gasses including flammable hydrogen and other species that are a concern for environmental release. The H-Canyon facility at the Savannah River Site is currently dissolving aluminum-clad
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::249206a9ce8837cae42466a22c03664d
Publikováno v:
Separation Science and Technology. 54:1893-1903
A dissolution flowsheet for the Low Enriched Uranium (LEU) ingots generated at the Idaho National Laboratory (INL) from the electrochemical processing of the EBR-II fuel was demonstrated at the laboratory scale. Dissolution experiments were performed
Publikováno v:
Separation Science and Technology. 54:1880-1892
H-Canyon at Savannah River Site has started dissolving High Flux Isotope Reactor (HFIR) fuel as part of the Spent Nuclear Fuel (SNF) processing campaign. Each HFIR fuel core contains inner and outer fuel elements fabricated from uranium oxide (U3O8)
Publikováno v:
Separation Science and Technology. 54:1904-1911
The complete recycle of used nuclear fuel (UNF) is desirable to recover the energy value from the remaining U and higher actinides; however, construction of a large-scale facility is extremely expe...
Publikováno v:
Separation Science and Technology. 53:1874-1884
The Savannah River National Laboratory was requested to develop a Pu metal dissolution flowsheet at two reduced temperature ranges for implementation in the Savannah River Site H-Canyon facility. The dissolution and H2 generation rates during Pu meta
Publikováno v:
Separation Science and Technology. 53:1906-1917
Samples of undissolved solids (UDS) from the dissolution of North Anna reactor fuel were characterized to investigate the effects of using air or oxygen as the oxidant during tritium removal. The UDS composition data also support the development of a