Technical report outlining the use of circular weirs in solvent extraction between liquid phases of nuclear fuel elements. From Abstract : "A correlation of the experimental coefficients was developed to allow calculation of general weir performance."

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."

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."

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."

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."

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."

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."

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."

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."

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."

Technical report. From Abstract : "Laboratory data are given and discussed that outline the potential application of N, N-distributed amides to the separation of uranium, neptunium, and plutonium from fission products."

Technical report. From Abstract : "The concentrations of Np(IV) and Np(V) ions in nitric acid solutions were determined quantitatively by a spectrophotometric method."

Technical report. From Abstract : "A semicontinuous process was developed for dissolving the solid residues that are produced in the calcium reduction process for converting plutonium fluoride to plutonium metal. The slag and crucible residues are charged to a column-type dissolver, and are there exposed to a flowing solution of hot nitric acid followed by a nitric acid - aluminum nitrate solution. The resultant solution is suitable as feed for an ion exchange process for recovering plutonium."

Technical report. From Abstract : "Several hundred long, thin-walled uranium tubes were extruded to close dimensional tolerance by a potentially low cost fabrication process in commercial facilities. The principal process steps were; forging uranium ingots, machining the forged ingots into billets, and extruding the billets into tubes. Some 750 tubes (maximum dimensions: 3.5 inches in diameter and 15 feet long) were fabricated by this process. Dimensional control was excellent in that 88% of the tubes were within +/- 0.010 inch of average dimensions over their entire length."

Technical report. From Abstract : "Optimum conditions were determined for the precipitation of neptunium (IV) peroxide from nitric acid solutions. The results indicate that the precipitation could be applied successfully on a plant scale. ... Two crystalline modifications of the peroxide were prepared; these two crystalline structures were similar to structures previously reported for plutonium peroxide."

Technical report. From Abstract : "Curium-242 was experimentally identified as a minor product of the irradiation of neptunium-237 in a nuclear reactor." From Introduction : "Determinations of the half-life, alpha energy, and daughter product of the purified curium nuclide were made in this study to confirm the identity as curium-242."

Technical report. From Abstract : "A number of similar eddy current instruments were developed to measure the thickness of Zircaloy over uranium metal in the range of 5 to 25 mils, Zircaloy over UO2 in the range of 20 to 40 mils, and the wall thickness of Zircaloy tubes in the range of 20 to 40 mils. The instruments were designed for use with hand-held probes or with feeder-mounted probes to measure the inside and outside cladding thickness of tubular elements and the wall thickness of Zircaloy sheaths. The instruments have a sensitivity of 3 microamps per mil change in Zircaloy thickness and an accuracy of +/- mil."

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."

Technical report. From Abstract : "The separation of neptunium and plutonium by anion exchange in nitrate solutions was studied under a wide variety of experimental conditions. A method of separation was developed that is adaptable to remote operation in the plant. In the method, Np(IV) and Pu(IV) are absorbed on an anion exchange resin from 8M nitrate solution. The column is washed with 8M HNO3 to remove contaminants; then the Pu is removed as Pu(III) by washing the column with HNO3 containing ferrous sulfamate and hydrazine. Finally, the Np is eluted with dilute HNO3."

Technical report. From Abstract : "A facility for separation of Pu238 and Np237 from irradiated neptunium dioxide target slugs was designed, constructed, and operated at the Savannah River Laboratory. This report describes the facility and includes design details of equipment." From Summary : "The main problems encountered during the design of the facility were: (1) to provide adequate containment and shielding of the radioactive materials, (2) to select chemical- and radiator-resistant materials, and (3) to provide for remote operation and maintenance of process equipment. ... This report contains a discussion of the major design problems and a detailed description of the facility and equipment."

Technical report. From Abstract : "A study was made of the kinetics and stoichiometry of the formation of hydrazoic acid in nitric acid solutions containing hydrazine and ferrous sulfamate. The data were used to establish safe limits for the use of hydrazine in process solutions."

Technical report. From Abstract : "Plutonium (principally Pu238) was separated from neptunium, and both the plutonium and neptunium were purified from fission products and cations by a three-cycle anion exchange process."

Technical report. From Abstract : "An existing ion exchange method was adapted for use in a shielded facility to separate Np237 from highly radioactive solutions. The subsequent determination of neptunium was made by alpha counting and alpha pulse height analysis. The coefficient of variation was $.8% (n=10) for a synthetic sample and 5.9% (n=23) for plant samples."

Technical report. From Abstract : "An analytical method was developed for the determination of Np237 in solutions that contain plutonium and fission products. Np (IV) was extracted into tri-n-octylamine. A quantitative recovery of a Np237 standard was obtained with a coefficient of variation of 1.0% (n=10). A coefficient of variation of 3% was obtained for seven analyses of a process sample."