Coextrusion of Powder-Compact Slugs (open access)

Coextrusion of Powder-Compact Slugs

Technical report. From Abstract: "A process was developed for manufacturing aluminum-clad slugs containing UO2 or ThO2 dispersed in an aluminum matrix. In this process a mixture of the oxide and aluminum powder is cold compacted to form the billet core, which is then coextruded with an aluminum sheath to produce the clad slug."
Date: April 1960
Creator: Marsh, Harold G.
System: The UNT Digital Library
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
Thermal Conductivity of Aluminum-Lithium Alloys Containing Up to 8% Lithium (open access)

Thermal Conductivity of Aluminum-Lithium Alloys Containing Up to 8% Lithium

Technical report. From Abstract: "The thermal conductivities of aluminum-lithium alloys containing up to * wt % lithium were determined at temperatures between 125 and 260ºC. The addition of lithium to aluminum sharply reduces the conductivity from 0.60 cal/(sec)(ºC)(cm) for pure aluminum to 0.22 cal/(sec)(ºC)(cm) for 2 wt % alloys; further addition linearly and more gradually decreases the conductivity to 0.16 cal/(sec)(ºC)(cm) for a 7.9 wt % alloy."
Date: April 1960
Creator: Costas, Louis P.
System: The UNT Digital Library
Automatic Dose Computer for Radiation Film Badges (open access)

Automatic Dose Computer for Radiation Film Badges

Technical report. From Abstract: "A combination densitometer and analog computer is described which determines radiation exposure of photographic film used in personnel badges. The range of the instrument is 0 to 300 mr gamma and 0 to 300 mrad beta plus gamma. A novel phototube circuit is used to obtain logarithms directly."
Date: April 1960
Creator: Davis, John E.
System: The UNT Digital Library
Swaging of Uranium Dioxide Tubes - [Part] I (open access)

Swaging of Uranium Dioxide Tubes - [Part] I

Technical report. From Abstract: "A method was developed for fabricating tubular fuel elements of uranium dioxide by swage compaction of crushed, fused UO2. The elements were 5 to 10 feet long and were clad with stainless steel. UO2 densities up to 91% of theoretical were obtained in tubes about 2.1 inches in outside diameter and 0.3 inch in wall thickness."
Date: August 1960
Creator: Ferrara, Anthony S.
System: The UNT Digital Library
Neutron Spark Counter (open access)

Neutron Spark Counter

Technical report. From Abstract : "Spark counters of the wire plate type are rugged and simple, and their sensitivity is directly proportional to the specific ionization of incident particles. Spark counters are insensitive to beta and gamma radiation but readily respond to alpha particles. With a suitable converter, the spark counter can also be employed as a neutron counter. Spark counters thus appear to be very good candidates for the measurement of neutron flux at reactor startup, where the high background of gamma radiation can be troublesome to other types of counters. A spark counter of cylindrical geometry was built and shown to have adequate sensitivity and stability for such duty."
Date: October 1960
Creator: Caiati, Frank P.
System: The UNT Digital Library
Anion Exchange of Neptunium in Nitrate Solutions (open access)

Anion Exchange of Neptunium in Nitrate Solutions

Technical report. From Abstract : "The absorption and elution of the anionic nitrate complex of neptunium (IV) were studied with several anion exchange resins and under a wide variety of conditions." From Introduction : "The objective of this study was to provide a technical basis for selecting process conditions for the recovery of Np."
Date: December 1960
Creator: Burney, Glenn A.
System: The UNT Digital Library
Spectrophotometric Determination of Mixtures of Neptunium(Iv) and Neptunium(v) in Nitric Acid Solutions (open access)

Spectrophotometric Determination of Mixtures of Neptunium(Iv) and Neptunium(v) in Nitric Acid Solutions

Technical report. From Abstract : "The concentrations of Np(IV) and Np(V) ions in nitric acid solutions were determined quantitatively by a spectrophotometric method."
Date: December 1960
Creator: Dukes, E. K. & Shuler, W. E.
System: The UNT Digital Library