Practical procedures were demonstrated for partitioning plutonium from uranium in the Purex process with hydrazine-stabilized uranium(IV) nitrate as the reducing reagent for plutonium. Typical partitioning results were 0.04--0.2% loss of plutonium to the uranium product and less than 1 wt% uranium in the plutonium product. With uranium(IV) nitrate as a replacement for ferrous sulfamate, most solids in wastes from the Parex process can be eliminated. No undue hazard is expected from the use of hydrazine as the stabilizing agent. (auth
Purex process which utilizes solvent extraction to separate and purify uranium and plutonium from ea...
A study to define the effectiveness limits of sulfamic acid and to discover other better stabilizers...
"Chemical Separations Processes for Plutonium and Uranium (TID-4500, 16th Ed.).""Printed for the Uni...
Laboratory studies, followed by plant operation, established that a mixture of hydroxylamine nitrate...
Work performed at the E.I. du Pont de Nemours & Company, Explosives Department, Atomic Energy Diviso...
Labcratory data which indicate that the recovery of Pu and U and decontamination from fission produc...
Recovery and purification were satisfactory in miniatarepilot-plant tests of the Purex first cycle w...
It is anticipated that neptunium will be recovered in the Purex process by solvent extraction or ion...
Hydrazine nitrate-nitric acid solutions are used in the ion exchange process for separating Pu-238 a...
The Zirflex and Sulfex processes for chemical decladding Zircaloy or stainless-steel-clad UO/sub 2/ ...
A number of processes for the preparation of tetravalent uranium solutions, suitable for use as a re...
From abstract: "The Darex process developed for the recovery of uranium from stainless steel-contain...
The oxidation of uranium(IV) by oxygen and nitrous acid was studied in both 30% TBP-""Ultrasene"" an...
The technique for adjusting the valence of Pu in the Pu(IV-VI) system to the Pa(IV) state for effici...
The use of anion exchange for final Pu purification in the Redox facility requires the adjustment of...
Purex process which utilizes solvent extraction to separate and purify uranium and plutonium from ea...
A study to define the effectiveness limits of sulfamic acid and to discover other better stabilizers...
"Chemical Separations Processes for Plutonium and Uranium (TID-4500, 16th Ed.).""Printed for the Uni...
Laboratory studies, followed by plant operation, established that a mixture of hydroxylamine nitrate...
Work performed at the E.I. du Pont de Nemours & Company, Explosives Department, Atomic Energy Diviso...
Labcratory data which indicate that the recovery of Pu and U and decontamination from fission produc...
Recovery and purification were satisfactory in miniatarepilot-plant tests of the Purex first cycle w...
It is anticipated that neptunium will be recovered in the Purex process by solvent extraction or ion...
Hydrazine nitrate-nitric acid solutions are used in the ion exchange process for separating Pu-238 a...
The Zirflex and Sulfex processes for chemical decladding Zircaloy or stainless-steel-clad UO/sub 2/ ...
A number of processes for the preparation of tetravalent uranium solutions, suitable for use as a re...
From abstract: "The Darex process developed for the recovery of uranium from stainless steel-contain...
The oxidation of uranium(IV) by oxygen and nitrous acid was studied in both 30% TBP-""Ultrasene"" an...
The technique for adjusting the valence of Pu in the Pu(IV-VI) system to the Pa(IV) state for effici...
The use of anion exchange for final Pu purification in the Redox facility requires the adjustment of...
Purex process which utilizes solvent extraction to separate and purify uranium and plutonium from ea...
A study to define the effectiveness limits of sulfamic acid and to discover other better stabilizers...
"Chemical Separations Processes for Plutonium and Uranium (TID-4500, 16th Ed.).""Printed for the Uni...