Anion Exchange Recovery of Plutonium From Reduction Residues (open access)

Anion Exchange Recovery of Plutonium From Reduction Residues

Technical report. From Abstract: "An anion exchange process was demonstrated for the recovery of plutonium from waste produced in the reduction of plutonium salts to the metal. Plutonium in a highly salted 6M nitric acid solution derived from the dissolution of slag and crucible waste was separated from impurities by absorbing the Pu (IV) nitrate complex on the anion exchange resin and subsequently eluting with nitric acid. A flowsheet for plant operation is presented."
Date: February 1960
Creator: Russell, Edwin R.
System: The UNT Digital Library
Recovery of Neptunium From Purex Waste by an Agitated Bed of Anion Exchange Resin (open access)

Recovery of Neptunium From Purex Waste by an Agitated Bed of Anion Exchange Resin

Technical report. From Abstract: "Data are presented for the absorption of thorium and neptunium from synthetic waste concentrate of the "Purex" process by a miniature agitated bed of anion exchange resin. The behavior of neptunium indicated that efficient recovery should be obtained from Purex high activity waste concentrate by this technique. A method was developed for calculating absorption losses from agitation beds of resin. The predicted losses were in excellent agreement with experimental results."
Date: February 1960
Creator: Prout, William E., 1921- & Fernandez, LeVerne P.
System: The UNT Digital Library
Physics Data From a Mockup of the HWCTR Lattice in the PDP (open access)

Physics Data From a Mockup of the HWCTR Lattice in the PDP

Technical report. From Abstract: "Experiments were performed in the Process Development Pile (PDP) with a critical mockup of the Heavy Water Components Test Reactor (HWCTR) lattice. Reactivity measurements served to determine control rod worths, the temperature coefficient of the reactor at low temperatures, the dependence of keff on concentrations of U235 and poisons in the "driver" region of the reactor, and the changes in keff that occur in certain conceivable accidents in the HWCTR. Flux distribution measurements were made to determine over-all flux shapes, local flux variations around individual components, azimuthal flux variations due to asymmetrical combinations of control rods, and vertical flux variations obtainable through the use of control rods of partial length. Sufficiently detailed flux measurements were made to permit the calculation of neutron economy tables and to determine the neutron leakage from the reactor. Suitable adjustments in the input parameters made it possible to fit the experimental results with a two-group calculation."
Date: February 1960
Creator: Graves, William E.
System: The UNT Digital Library
Fabrication of UO2 Fuel Elements by Vibrational Compaction (open access)

Fabrication of UO2 Fuel Elements by Vibrational Compaction

Technical report. From Abstract : "Arc-fused UO2 was vibrationally compacted to as high as 93.4% of theoretical density inside a stainless steel sheath tube. Selected particle sizes were used, and the assembly was vibrated axially in the frequency range of 300 to 1500 cycles per second. The same blend of UO2 particle sizes was vibrationally compacted to 87.5% of theoretical density within the annulus between two concentric stainless steel sheath tubes. The effects of particle size distribution, vibrational compaction procedure, sheath thickness, and fuel element shape on the maximum obtainable density were investigated."
Date: February 1962
Creator: Marah, Harold G.
System: The UNT Digital Library