Flowsheets are presented for the dissolution of Borax IV reactor fuel (6.35% UO/sub 2/)--ThO/sub 2/ pellets encased in 1% nickel--aluminum alloy and bonded with lead). In the preferred method the alurninum is dissolved first in boiling 2 M NaOH--1.78 M NaNO/sub 3/, with a urarium loss of approximately 0.07%. The lead and nickel are then dissolved in boiling 1.5 M HNO/sub 3/, with uranium losses of <0.2%. The oxide core is dissolved in two successive digestions with boiling 13 M HNO/sub 3/--0.04 M NaF--0.1 M Al(NO/sub 3/)) to produce a solution 0.6 M in thoriunn and 0.04 M in uranium. Dissolution of only the aluminum in sodium hydroxide or sodium hydroxide--sodium nitrate solution prior to core dissolution is unattractive since the rate of c...
In its 70-year history, Idaho National Laboratory has pioneered significant nuclear advancements and...
A series of characterization and dissolution studies has been performed to define flowsheet conditio...
The path of iodine from the Purex dissolver was determined during fuel dissolution using /sup 125/I ...
Laboratory dissolution studies of aluminum clad mixed oxide fuel rods have been conducted using two ...
"ORNL-2821 ; UC-10--Chemistry-Separation Processes for Plutonium and Uranum" -c.p.Includes bibliogra...
Flowsheets for the dissolution of aluminum-clad spent nuclear fuel have been proposed using 0.002 M ...
Methods for dissolving unirradiated uranium-molybdenum alloy reactcr fuels in nitric acid, nitric ac...
Aqueous zirconium fuel processing studies, directed at adapting the hydrofluoric acid process to con...
Aqueous methods for recovering uranium from BeO- and Al/sub 2/O/sub 3/- base gas-cooled-reactor fuel...
Modified Zirflex process flowsheets were developed for recovering uranium from the newer power react...
A series of dissolution and characterization studies has been performed to determine if FB-Line resi...
The H-Canyon facility will be used to dissolve Pu metal for subsequent purification and conversion t...
The dissolution of aluminum-clad uranium oxide-aluminum fuel was studied to provide basic data for d...
A modified Zirflex process was developed in the laboratory for dissolution of 1 to 10% uranium-zirco...
Consolidated Edison type fuel pellets were irradiated and analyzed, to determine the extent of fract...
In its 70-year history, Idaho National Laboratory has pioneered significant nuclear advancements and...
A series of characterization and dissolution studies has been performed to define flowsheet conditio...
The path of iodine from the Purex dissolver was determined during fuel dissolution using /sup 125/I ...
Laboratory dissolution studies of aluminum clad mixed oxide fuel rods have been conducted using two ...
"ORNL-2821 ; UC-10--Chemistry-Separation Processes for Plutonium and Uranum" -c.p.Includes bibliogra...
Flowsheets for the dissolution of aluminum-clad spent nuclear fuel have been proposed using 0.002 M ...
Methods for dissolving unirradiated uranium-molybdenum alloy reactcr fuels in nitric acid, nitric ac...
Aqueous zirconium fuel processing studies, directed at adapting the hydrofluoric acid process to con...
Aqueous methods for recovering uranium from BeO- and Al/sub 2/O/sub 3/- base gas-cooled-reactor fuel...
Modified Zirflex process flowsheets were developed for recovering uranium from the newer power react...
A series of dissolution and characterization studies has been performed to determine if FB-Line resi...
The H-Canyon facility will be used to dissolve Pu metal for subsequent purification and conversion t...
The dissolution of aluminum-clad uranium oxide-aluminum fuel was studied to provide basic data for d...
A modified Zirflex process was developed in the laboratory for dissolution of 1 to 10% uranium-zirco...
Consolidated Edison type fuel pellets were irradiated and analyzed, to determine the extent of fract...
In its 70-year history, Idaho National Laboratory has pioneered significant nuclear advancements and...
A series of characterization and dissolution studies has been performed to define flowsheet conditio...
The path of iodine from the Purex dissolver was determined during fuel dissolution using /sup 125/I ...