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Quarterly Report October, November and December, 1956

Description: Methods of producing extremely clean surfaces on rolled Zircaloy-2 strip have been investigated. It has been found that the finer abrasives, 400 mesh or finer, are more effective than coarse types because of their ability to penetrate pits and crevices more readily. Two such cleanings, with an intermediate 35 v/o HNO3-5 v/o HF pickle, resulted in a microscopically clean surface. Ultrasonic inspection of the EBWR fuel plates has been completed during this quarter. Approximately 95% of the plates… more
Date: December 31, 1956
Creator: Foote, Frank G.; Schumar, James F. & Chiswik, Haim H.
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Efficiency of a Three Inch Higgins Column

Description: The following report describes the usage of a semi-continuous ion exchange contactor--named the Higgins contactor--fit to operate the Purex process, a process that recovers plutonium and uranium from irradiated natural uranium fuel elements. It is intended to use the contactor in the final purification and concentration stage of the process plutonium streams.
Date: December 20, 1956
Creator: Vaughan, Victor C.; Jansen, George & Bagley, Raymond O.
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Chemical Properties of Sodium Triethylhydroborate and Sodium Triisopropoxyhydroborate

Description: Technical report abstract: Sodium hydride and triethylborane react to form sodium triethylhydroborate, NaBH(C2H5)3. This compound, a liquid at rooom temperature, was found to be soluble in hexane and mineral oil. A study was made of the thermal decomposition of sodium triethylhydroborate and its behavior toward boron trifluoride, boron trichloride, methyl borate, carbon dioxide, silane, and ethylene. Sodium triisopropoxyhydroborate, NaBH(OC3H7)3, was prepared and also found to be soluble in h… more
Date: December 13, 1956
Creator: Pearson, Richard King, 1926-; Edwards, L. J. & Maginnity, P. M.
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Chemical Engineering Division Summary Report July, August, and September, 1956

Description: Additional runs have been made in the six-inch, continuous-flow mixing chamber to study the rate of mass transfer between isobutanol and water. These runs were inconclusive because the effluents were mutually saturated. A new four-inch cell has been designed and is being fabricated; this will permit a reduction in the time available for mass transfer. Consideration has been given to other liquid pairs which may transfer more slowly than isobutanol-water. The system nitrobenzene-ethylene glycol … more
Date: December 1956
Creator: Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
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Concentration of Plutonium by Cation Exchange Part I - New Elutriants

Description: From summary: "The concentration of plutonium by cation exchange was significantly improved by using a solution of ammonium lactate and sulfamate as the elutriant instead of nitric and sulfamic acids. The new elutriant permitted essentially complete elution of the plutonium and also avoided formation of gases in the resin bed during elution. At 45ºC, 2.8M ammonium lactate plus 0.15M ammonium sulfamate eluted 99.3 per cent of the total plutonium at an average concentration of 43.8 grams per lite… more
Date: December 1956
Creator: Bonner, Oscar D.; Burney, Glenn A. & Tober, Frank W., 1919-1995
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Centrifugal Casting for Plutonium and Plutonium-Uranium Plates

Description: The objective of this investigation was to determine the feasibility of centrifugal casting to produce fuel element plates suitable for use in a power reactor. Preliminary investigations involving the centrifugal casting of metal plates suitable for use in a power reactor proved to be successful. Lead plates cast at medium speeds contained very few voids and exhibited a surface which conformed very closely to that of the mold.
Date: November 28, 1956
Creator: Quinlan, F. B. & Tverberg, J. C.
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Corrosion of Stainless Steel, Titanium, and Tantalum in Plutonium - Nitric Acid Solutions

Description: The letter E. R. Irish/W. H. Swift to R.E. Burns and H. H. Hopkins, dated August 15, 1956, subject Plutonium Concentration Problems, requested information on corrosion of stainless steel, titanium, and tantalum in plutonium nitrate-nitric acid solution, with and without sulfate ion. Experimental conditions and results of tests designed to yield the requested information are given below.
Date: November 27, 1956
Creator: Brunstad, A.
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An Ultrasonic Method for Bond Testing Reactor Fuel Elements

Description: Ultrasonic testing has been investigated as a possible non-destructive method for checking the bond integrity of certain type fuel elements. Equipment has been developed to inspect experimental fuel elements for various research programs. Circuits have been devised to discriminate the size of defects and to map the areas which are unbonded.
Date: November 27, 1956
Creator: Worlton, D. C.
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Magnetic Field Distributions in a Pinched Discharge

Description: By use of small magnetic probes inserted into the discharge, the magnetic field distributions in the interior of a high-power pinched discharge have been measured as a function of time. From these data the current distributions can be deduced. By applying a static pressure calculation, in the cases when the radical pinch accelerations are small, the plasma pressure nkT in the pinch has been determined, with superimposed axial magnetic fields, and for stable and unstable configurations.
Date: November 20, 1956
Creator: Burkhardt, L. C.; Lovberg, Ralph H. (Ralph Harvey) & Phillips, J. A.
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Evaluation of Peerless Magnetic Drive Process Pump

Description: The desirability of employing leakproof process pumps for handling the corrosive and radioactive process solutions in the H.A.P.O. separations plants has led to the establishment of a program for the development and testing of packless pumps with particular emphasis on evaluation of commercially available units. One such pump, its operating characteristics and behavior, are described in this report.
Date: November 19, 1956
Creator: Dunn, J.
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Post-Irradiation Examination of Cluster-Type Fuel Elements

Description: Cluster fuel elements meet many of the requirements of high temperature recirculating water reactors and have several advantages over solid fuel elements. Operation at higher specific power levels for a given temperature limit are attainable because of the larger heat transfer surface. Failure of a single rod in cluster does not restrict coolant flow as severely as failure of a solid fuel element, hence the number and severity of stuck charges can be reduced.
Date: November 19, 1956
Creator: Boyd, C. L.
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Analysis of Thorex Pilot Plant Radiation Exposures During 1955

Description: The Thorex Pilot Plant at Oak Ridge National Laboratory was operated during 1955, processing reactor-irradiated thorium slugs to recover U233 and thorium and 12 MTR fuel elements to recover U235 and Np237. The radiation exposure received by operating personnel during this period averaged 60 mrcp/man-week. Most radiation exposure was received in areas that were intended to be only slightly or nonradioactive. However, because insufficient decontamination of process solutions was achieved and equi… more
Date: November 16, 1956
Creator: McCarley W. T.
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Note on Power Recovery From Warm Water

Description: Several studies of power recovery from Hanford pile effluents have been made, from which the conclusion can be drawn that, while recovery of power is feasible, it is costly because of the large volume of vapor which must be handled per kilowatt-hour of energy provided. This note is to call attention to the possibility of developing cheaper machinery than the conventional low-pressure turbine stages considered in previous studies through use of a water expansion cycle.
Date: November 15, 1956
Creator: Wood, E. C.
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PRPR Control Requirements. Part I.

Description: The following remarks are intended primarily to assist in the orientation of the PRP reactor control development program in a direction consistent with the basic objectives of the program as a whole, and to discuss certain aspects of particular control systems which have a bearing on the capabilities of the reactor with respect to these objectives.
Date: November 14, 1956
Creator: Triplett, J. R.
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An Evaluation of the Corrosion and Oxidation Resistance of High-Temperature Brazing Alloys

Description: The fabrication of heat exchangers and radiators to be used in conjunction with high-temperature nuclear reactors may present exceedingly complex problems. Rigid heat transfer requirements may necessitate the use of compact assemblies of thin-walled small-diameter tubes as integral parts of the heat transfer units. Intricate designs may also be required in which cooling fins must be securely joined to the tubes at closely spaced intervals. In addition to the difficulties in fabrication imposed … more
Date: November 7, 1956
Creator: Hoffman, E. E.; Leitten, C. F., Jr.; Patriarca, P.; Slaughter, G. M.; Pope, J. E.; Shubert, C. E. et al.
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Radiobiological Studies of the Columbia River Through December, 1955

Description: Radiobiological studies were made to determine effects of radioactive effluents from the Hanford reactors upon the aquatic biota of the Columbia River and to evaluate related hazards. Data from studies completed between September, 1945, and December, 1955 are presented and interpreted. All forms of life were many times more radioactive than the water they inhabited. Some radioisotopes were much more readily accumulated than others in living organisms. Differences in the concentration of certain… more
Date: November 7, 1956
Creator: Davis, J. J.; Watson, D. G. & Palmiter, C.C.
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