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Density and Viscosity of Solutions in the Tributyl Phosphate Process for Uranium Recovery

Description: The following report discusses the presentation of preliminary density and viscosity data which may explain whether higher viscosities of the Deo Base-TBP systems, and a change in density differences between the two phases will lead to unsatisfactory column operation.
Date: November 29, 1949
Creator: Burger, L. L. & Slansky, C. M.
Partner: UNT Libraries Government Documents Department
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Determination of Organic Acids in Process Solutions

Description: Abstract: "A method has been established for the estimation of volatile organic acids in aqueous process solutions containing UNH, nitric acid, ANN, sodium dichromate and small amounts of hexone. The practice is to distill a 400 ul or 500 ul sample in the presence of an excess of phosphoric acid and ferrous sulfate under a high vacuum; a special apparatus utilizing a receiver cooled with a dry ice-isopropanol mixture is employed. The distillate is taken up in isopropanol and then titrated poten… more
Date: June 29, 1949
Creator: Brouns, R. J. & Pollock, C. W.
Partner: UNT Libraries Government Documents Department
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Heating in the Graphite Due to a Cadmium Control Rod

Description: From introduction: "This paper employs a multigroup method similar to that of J. S. Story, AERE-TR-177 to calculate, for cylindrical geometry, that heat energy source density in graphite due to absorption and Compton scattering of those gammas produced by neutron capture in a water filled cadmium control rod."
Date: September 29, 1951
Creator: Newkirk, W. H.
Partner: UNT Libraries Government Documents Department
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Recovery of Nitric Acid in the Tributyl Phosphate Process for Uranium Recovery. Part 2.

Description: Report discussing study on recovery of nitric acid in the uranium recovery process. The behavior of chloride ions and tributyl phophate is noted, and the quality of recycled nitric acid was tested. Stainless steel in the nitric acid recovery system was evaluated for corrosion.
Date: May 29, 1950
Creator: Wagner, R. M. & Groot, C.
Partner: UNT Libraries Government Documents Department
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Design considerations for a pulse column system

Description: From objectives: "The objectives of this investigation were to evaluate the hydraulic forces in the pulse column, and determine their effects on pulse column design."
Date: November 29, 1956
Creator: Cooper, V. R. & Groot, C.
Partner: UNT Libraries Government Documents Department
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Darex Pilot Plant Studies

Description: The Atomic Energy Commission has assigned the Hanford Atomic Products Operation the responsibility of providing the technology and facilities for the interim reprocessing of slightly enriched uranium fuels discharged from power and propulsion reactors. The fuel from the various reactors vary greatly in physical dimensions and in the composition of the core and cladding. For the purposes of chemical reprocessing, the fuels may be divided into the three main categories of aluminum, Zircaloy or st… more
Date: October 29, 1959
Creator: Shefcik, J. J.
Partner: UNT Libraries Government Documents Department
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Effect of the PRTR High Pressure Loop on Plutonium Recycle Program Objectives

Description: For purposes of an earlier consideration of the effects of in-reactor test loops on PRTR operation and program, the design of the high pressure, H20 cooled fuel test loop was assumed to be similar to that for the high pressure, gas cooled loop. Detailed design criteria for the H20 loop have recently been completed so that this assumption is no longer necessary. Therefore, to insure that the effects of all proposed in-reactor loops are fully evaluated with respect to Plutonium Recycle Program ob… more
Date: October 29, 1959
Creator: Peterson, R. E.
Partner: UNT Libraries Government Documents Department
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All In-Well Permeability Testing Packer

Description: Disposal of liquid radioactive wastes to ground requires knowledge of the area ground-water hydrology. Information is desired on direction and velocity of ground-water flow. Direction of flow can be determined from maps showing contours on the water table surface, such contours being derived from well water elevations. Ground-water velocity is more difficult to ascertain.
Date: September 29, 1959
Creator: Raymond, J. R.
Partner: UNT Libraries Government Documents Department
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Spectrographic Analysis of Plutonium by the Thenoyltrifloroacetone Extraction Method

Description: Impurities are separated from plutonium solutions by means of TTA (thenoyltrifluoracetone) extractions. Plutonium in hydrochloric acid solution is reduced to the trivalent state with hydroxylamine, and some impurities are extracted into hezone or a solution of TTA in hezone. The organic phase is removed, and the plutonium in the aqueous phase is oxidized to the tetravalent state with nitric acid. Investigations of several variables which affect the extraction are described..
Date: June 29, 1953
Creator: Van Tuyl, H. H.
Partner: UNT Libraries Government Documents Department
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Effect of the PRTR Fuel Elemental Rupture Test Facility on Plutonium Recycle Program Objectives.

Description: To insure a full evaluation of the effects of in-reactor loops with respect to all phases of the Plutonium Recycle Program, a separate study of each loop has been undertaken. An initial study was carried out which analyzed the effects of in-reactor loops using the design criteria for the gas loop as a basis. As soon as the design criteria for the H2O high pressure loop became available, a more detailed evaluation was completed for that loop. Recent completion of the scope description of the PRT… more
Date: January 29, 1960
Creator: Peterson, R. E.
Partner: UNT Libraries Government Documents Department
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Project CGC-830 Plant Modifications for Reprocessing Non-Production Reactor Fuels

Description: Facilities are to be designed for installation at Hanford for the reprocessing of irradiated, low enrichment fuels from non-production reactors, see Reference 1 and 2. The initial design of the processing facilities is to be based on processing the fuels discharged from the Dresden, Yankee, Piqua, Pathfinder and Shippingport (blanket elements only) reactors. Properties of the fuels and cladding make it impossible to completely process them in existing equipment, although the separation and deco… more
Date: July 29, 1960
Creator: Bierman, S. R.; Graf, W. A.; Kass, M.; Kligfield, G.; McKee, R.W.; Patridge, L. F. et al.
Partner: UNT Libraries Government Documents Department
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