UNT Libraries Government Documents Department - 39 Matching Results

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Aging of Al-Li Alloys - Part I

Description: Technical report outlining experiments on aluminum-lithium alloys. From Abstract: "Aluminum-lithium alloys are subject to precipitation from solid solution, and may be age hardened by the same techniques used for more common aluminum alloys. Spherical particles of precipitate were observed with the electron microscope in 1.5% and 2.8% Al-Li alloys after aging for times comparable to those required to produce maximum hardness. Rod-shaped particles that were oriented parallel to either the (110) or the (111) planes of the aluminum matrix were observed in overaged specimens."
Date: January 1959
Creator: Angerman, C. L.

Alpha Particle Radiolysis of Anion Exchange Resins

Description: Technical report. From Abstract : "Irradiation of 'Dowex' 1, 'Permutit' S-1, and 'Permutit' SK anion exchange resins with alpha particles results in losses in ion exchange capacity and in 'apparent per cent crosslinkage'. The order of decreasing radiolytic stability for these properties in 'Permutit" SX > 'Permutit' S-1 > 'Dowex' 1."
Date: November 1961
Creator: Ahrens, Rolland W.

Aluminium Corrosion in High Purity Water

Description: Summary: "A corrosion test of aluminum components in a 4-ft. section of a fuel tube has been tested under conditions simulating plant geometry and, as nearly as possible, the operating conditions of water purity, temperature, and flow rate. Results: 1. None of the aluminum components, 63S fuel tube, 2S solid fillers and 43S spacers showed any corrosion effects beyond normal oxide film formation. This was carried out in flowing water, maintained at a specific resistivity greater than 1 x 10(6) ohm-cm, for four weeks. 2. No corrosion pitting was observed on any of the aluminum surfaces; all became covered with a uniform film of Al2O3.H2O. On the boat tails, where type 304 stainless steel fins were in galvanic contact with 2S aluminum, no pitting or preferential attack occurred."
Date: May 1952
Creator: Nielsen, N. A.

Anion Exchange of Neptunium in Nitrate Solutions

Description: 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.

Anion Exchange Recovery of Plutonium From Reduction Residues

Description: 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.

Automatic Dose Computer for Radiation Film Badges

Description: 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.

Chemical Processing of Pu238

Description: 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."
Date: October 1962
Creator: Tetzlaff, Ralph N.

Coextrusion of Powder-Compact Slugs

Description: 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.

Concentration of Plutonium by Cation Exchange -- Stabilization of Pu(Ill) in Nitric Acid

Description: Technical report. From Abstract : "Ascorbic and isoascorbic acids, used in conjunction with sulfamic acid, reduced Pu(IV) rapidly and completely to Pu(III) in solutions of nitric acid. The solutions of Pu(III) were stable. Aminoguanidine sulfate also retarded the oxidation of Pu(III) but did not reduce Pu(IV)."
Date: February 1959
Creator: Tober, Frank W. & Russell, Edwin R.

Determination of Neptunium by Extraction With Tri-n-Octylamine

Description: 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."
Date: September 1962
Creator: Britt, Robert D., Jr.

Determination of Neptunium in High Activity Waste

Description: 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."
Date: September 1962
Creator: Holcomb, H. Perry

Eddy-Current Inspection Methods : Trip Report - The Dr. Förster Institute, Reutlingen, Germany

Description: Abstract; Test instruments developed at the Dr. Förster Institute, Reutlingen, Germany, were considered for possible application to Savannah River nondestructive inspection problems involving stainless steel and aluminum tubing. None of the equipment can solve these problems without modifications. Several instruments are recommended for further study in connection with their use with aluminum tubing. None will be considered for use with stainless steel at this time."
Date: November 1953
Creator: McMillen, R. C.

Extrusion of Uranium Tubes

Description: 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."
Date: July 1961
Creator: Fisher, R. E.

Fabrication of UO2 Fuel Elements by Vibrational Compaction

Description: 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.

A Facility for Chemical Separation of Pu238

Description: 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."
Date: August 1962
Creator: Coogler, Arthur L. & Fowler, Bill F.

Fuel Meltdown Experiments

Description: From Abstract: "Fuel tubes of enriched uranium-aluminum alloy were melted to various degrees of severity in the SPERT I reactor as a part of a program to evaluate reactor operating hazards. The heat flux encountered during the tests ranged from 200,000 to 650,000 pcu/(hr)(ft^2). The time required for the metal temperature to reach the melting point from the time when burnout began varied from 1.3 to 4.9 seconds. During these tests, pressure pulses were produced at a frequency of about one per second with peaks of about 150 psi."
Date: October 1958
Creator: Seaboch, James R. & Wade, James W.

Identification of Curium-242 in Irradiated Neptunium

Description: 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."
Date: August 1961
Creator: Carothers, Glenn A.

Manganese Dioxide Precipitation in Uranium - Aluminum Nitrate Solutions

Description: Technical report. From Abstract: "Precipitation of manganese dioxide in solutions of uranium-aluminum alloy effected maximum removal of fission products when the alloy solutions were acid deficient. Minimum adsorption of uranium and minimum volume of centrifuged MnO2 were obtained by precipitation in acidic solutions with vigorous agitation."
Date: February 1959
Creator: Henry, Hugh E.

Mounting Thermocouples on SPERT Test Assemblies

Description: Technical report. From Abstract: "A method of fastening thermocouples to 0.030-inch-thick aluminum cladding on test fuel elements was developed. The installation does not lead to hot spots by the addition of extra metal of the distortion of the cooling water channels. Fuel element temperatures were faithfully followed in SPERT tests up to the melting point. The method has been useful for fastening thermocouples to aluminum sections in general."
Date: December 1959
Creator: Sanders, Harold S.

Neutron Spark Counter

Description: 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.