Adsorption of Zirconium-Niobium on Silica Gel (open access)

Adsorption of Zirconium-Niobium on Silica Gel

From abstract: "Adsorption of radioactive zirconium-niobium from uranyl nitrate solutions by silica gel was increased by increasing the temperature and time the solution contacts silica gel, and decreased by "aging" the solutions before contacting the silica gel."
Date: July 1957
Creator: Karraker, David G. & Parker, Sidney G.
System: The UNT Digital Library
Aging of Al-Li Alloys - Part I (open access)

Aging of Al-Li Alloys - Part I

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.
System: The UNT Digital Library
Aluminium Corrosion in High Purity Water (open access)

Aluminium Corrosion in High Purity Water

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.
System: The UNT Digital Library
An Automatic Flaw Detector for Aluminum Cans (open access)

An Automatic Flaw Detector for Aluminum Cans

From abstract: "A tester, utilizing eddy currents, was developed to detect inclusions and voids in aluminum cans. The sensing element is a small probe that does not touch the can under inspection. An experimental feeder, developed along with the tester, permits the automatic inspection of one can per minute."
Date: October 1956
Creator: Ross, John D.
System: The UNT Digital Library
Behavior of Technetium in the Purex Process (open access)

Behavior of Technetium in the Purex Process

Technical report. From Abstract : "Predictions of the behavior of technetium in the Purex process and details of the chemistry of technetium for Purex process conditions are given."
Date: April 1959
Creator: Siddall, Thomas H., III
System: The UNT Digital Library
Concentration of Plutonium by Cation Exchange Part I - New Elutriants (open access)

Concentration of Plutonium by Cation Exchange Part I - New Elutriants

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 liter. It was found necessary to elute hydrogen and hydroxylammonium ions from the resin beds before elution of plutonium. The hydroxylammonium ions decompose to form gases in the resin bed at the desired temperature for plutonium elution. The hydrogen ions exchange with ammonium ions of the elutriant and decrease the concentration of plutonium in the eluate."
Date: December 1956
Creator: Bonner, Oscar D.; Burney, Glenn A. & Tober, Frank W., 1919-1995
System: The UNT Digital Library
Concentration of Plutonium by Cation Exchange -- Stabilization of Pu(Ill) in Nitric Acid (open access)

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

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., 1919-1995 & Russell, Edwin R.
System: The UNT Digital Library
Corrosion in Hydrogen Sulfide - Water Systems (open access)

Corrosion in Hydrogen Sulfide - Water Systems

From abstract: "This report gives a detailed account of the corrosion test work carried out by the Engineering Research Laboratory on the behavior of materials of construction in the hydrogen sulfide-water system. Results developed during the period from October 1950 through November 1954 are included."
Date: October 1955
Creator: Snyder, J. A. & Warren, D.
System: The UNT Digital Library
A Detector for Sub-Surface Cracks (open access)

A Detector for Sub-Surface Cracks

From abstract: "An instrument was developed to detect cracks within 1/8 inch of the surface of cylindrical uranium fuel slugs. The instrument measures changes in eddy currents that are induced at a frequency of 2 KC."
Date: August 1954
Creator: Goodwin, L. E.
System: The UNT Digital Library
Distribution of Uranyl Nitrate Between Al(NO3)3 and Tributyl Phosphate (open access)

Distribution of Uranyl Nitrate Between Al(NO3)3 and Tributyl Phosphate

From abstract: "The distribution of uranyl nitrate was measured from aluminum nitrate and nitric acid solutions into diluted tri-n-butyl phosphate. This information is useful for designing solvent extraction processes for recovery of uranium from aluminum nitrate or nitric acid solutions."
Date: March 1958
Creator: Ames, Donald P. & Karraker, David G.
System: The UNT Digital Library
Eddy Current Detection of Al-Si Penetrations in Canned Slugs (open access)

Eddy Current Detection of Al-Si Penetrations in Canned Slugs

From abstract: "An instrument for detecting aluminum-silicon alloy penetrations in the aluminum jacket of fuel slugs is described. The instrument is of the eddy current type and the sensing element is a small probe that does not touch the specimen under inspection. Al-Si inclusions 0.020 inch in diameter that penetrate to within 0.005 inch of the can surface can be detected. The response of the circuits is such that a slug 8 inches long can be scanned in 45 seconds."
Date: December 1957
Creator: Robinson, Richard C. & Ross, John D.
System: The UNT Digital Library
Eddy-Current Inspection Methods : Trip Report - The Dr. Förster Institute, Reutlingen, Germany (open access)

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

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.
System: The UNT Digital Library
Effect of Solvent Degradation on the Purex Process (open access)

Effect of Solvent Degradation on the Purex Process

From abstract: "The combined attack of HNO3 and HNO2 on tributyl phosphate - kerosene solvent used in the Purex process produces degradation products that cause abnormal quantities of zirconium to be extracted along with the plutonium and uranium and thus limits the decontamination."
Date: May 1958
Creator: Siddall, Thomas H., III; Wallace, Richard M. & Prout, W. E.
System: The UNT Digital Library
Electrolytic Reduction of Thorium Oxide (open access)

Electrolytic Reduction of Thorium Oxide

From abstract: "Thorium metal has been produced by electrolytic reduction of thorium oxide. Reduction was accomplished in both a KF-ThF4 melt and a NaCl-KCl-ThCl4 melt. A flowsheet for the complete process using the fused fluoride system is proposed."
Date: February 1957
Creator: Meyer, Leon Herbert, 1926-
System: The UNT Digital Library
Extraction of Uranium and Other Actinides From Nitric Acid by Di-N-Butyl N-Butylphosphonate (open access)

Extraction of Uranium and Other Actinides From Nitric Acid by Di-N-Butyl N-Butylphosphonate

From abstract: "Equilibrium data are presented for the distribution of uranium, other actinides, zirconium, and nitric acid between aqueous solutions and di-n-butyl n-butylphosphonate diluted with n-dodecane. Data for the physical properties and chemical stability of the phosphonate are also given."
Date: June 1957
Creator: Siddall, Thomas H., III & Loehlin, J. H.
System: The UNT Digital Library
Fuel Meltdown Experiments (open access)

Fuel Meltdown Experiments

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.
System: The UNT Digital Library
Initial Operation of the Standard Pile (open access)

Initial Operation of the Standard Pile

From abstract: "The Standard Pile was first brought to criticality on July 25, 1953. The first two months of operation permitted calibration of the reactor and preparation of it for use as a neutron source in exponential experiments."
Date: December 1953
Creator: Axtmann, Robert C.; Heinrich, L. A.; Robinson, R. C.; Towler, O. A. & Wade, J. W.
System: The UNT Digital Library
Ion-Chamber Water Monitor (open access)

Ion-Chamber Water Monitor

From abstract: "An instrument capable of detecting fission-product contamination in the moderator has been developed. It consists of a thin-walled ion chamber and associated electronic equipment for automatically detecting deviations from normal moderator decay rate. Indication of fission-product activity is independent of power level, flowrate, and other ambient conditions. Tests show the sensitivity and long-term stability to be good."
Date: February 1955
Creator: McCarthy, R. L.
System: The UNT Digital Library
Irradiation of Powder Metallurgy Plates (open access)

Irradiation of Powder Metallurgy Plates

From abstract: "Four plates of uranium that were fabricated by powder metallurgy techniques and clad with 1100 aluminum by hot pressing were irradiated in the Materials Testing Reactor. Increases of about one-half per cent in length and one per cent in thickness were observed after exposure of 1600 megawatt days per ton. The surfaces of the plates remained smooth."
Date: April 1957
Creator: Angerman, C. L.; Douglass, D. L. (David Leslie), 1931-; Marshall, R. P. & Caskey, George R., Jr.
System: The UNT Digital Library
Irradiation of Thorium Slugs (open access)

Irradiation of Thorium Slugs

From abstract: "Ninety-two thorium slugs were irradiated in the Hanford piles to study the dimensional stability of the metal. The burnups that were incurred covered the range from 300 to 2800 ppm of the Th232. Slugs with burnups as high as 800 ppm were examined for visual and dimensional changes. The dimensional stability of these slugs was excellent, and no significant corrosion occurred on the aluminum cans. A cursory examination of slugs with burnups of greater than 800 ppm showed no gross dimensional instability."
Date: May 1956
Creator: Marshall, Robert P.
System: The UNT Digital Library
Irradiation of Wrought Uranium Plate (open access)

Irradiation of Wrought Uranium Plate

From abstract: "Wrought uranium plate, clad in 1100 aluminum with a nickel bonding layer, was irradiated to a maximum exposure of 1600 MWD/T in the MTR and was demonstrated to be suitable as a fuel element material. Beta-transformed plate, or beta-transformed plate that was cold stretched 2-1/4 per cent, did not change appreciably in dimensions but roughened on the surface. As-rolled plate increased in length, but did not roughen. Irradiation reduced the strength and virtually eliminated the ductility of the plate. Abrasion of the cladding caused corrosion pitting. The strength of the nickel diffusion bond between core and cladding was unimpaired by the irradiation."
Date: July 1957
Creator: McDonell, William R. & Marshall, Robert P.
System: The UNT Digital Library
Isotopic Purification of Tritium by Electrolysis (open access)

Isotopic Purification of Tritium by Electrolysis

From abstract: "An electrolytic refining process was developed to produce tritium of high isotopic purity with negligible loss. The operation is semicontinuous, with multiple stages in cascade. All tritium oxide is handled within the confines of a hermetically sealed enclosure. The mechanical operability of the process was demonstrated in a five-stage prototype line designed to process 15 gram-mols of feed per day. An average separation factor per stage of 5.3 was obtained with a feed of tracer-level tritium. The equipment is described in detail."
Date: May 1958
Creator: Johnson, B. S., Jr.; Grace, J. T.; Meyer, L. H.; Karraker, D. G. & Nicholson, C. K.
System: The UNT Digital Library
Kinetics of the Beta Transformation of Uranium (open access)

Kinetics of the Beta Transformation of Uranium

From abstract: "When uranium is heat treated at low beta-phase temperatures and air cooled, the rate of loss of preferred orientation is markedly less than the rate of coarsening of the grain structure. A coarse-grained structure cannot therefore be taken as an infallible indication of satisfactory heat treatment. The final grain size of incompletely transformed metal is essentially equal to or larger than the starting grain size. Large-grained specimens can not be refined by interruption of the transformation at an intermediate stage."
Date: September 1957
Creator: McDonell, William R.
System: The UNT Digital Library
Manganese Dioxide Precipitation in Uranium - Aluminum Nitrate Solutions (open access)

Manganese Dioxide Precipitation in Uranium - Aluminum Nitrate Solutions

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.
System: The UNT Digital Library