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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Kanigen, Electroless Nickel Plating for Steam Side of a Sodium Component Steam Generator

Description: Introduction: This is a final report on the evaluation of Kanigen electroless nickel plating for surfaces in contact with water and steam i a sodium heated AISI Type 316 stainless steel steam generator. The purpose of the coasting was to afford protection from stress corrosion cracking originating on the water-steam side of the unit. It has been concluded that the kanigen coating does not afford adequate protection for the services condition intended. This work was performed as part of the r… more
Date: February 15, 1961
Creator: Alco Products (Firm).
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chlorotriammineplatinum(II) Ion : Acid Hydrolysis and Isotopic Exchange of Chloride Ligand

Description: Abstract: The acid hydrolysis of [Pt(NH3)3Cl] has been shown to occur to a measurable extent. for this reaction: [APt(NH3)cCl]+ + H2O [chemical equilibrium symbol with rate constant k-1 above and k1 below] [Pt(NH3)c(H2O)]++ + Cl-, the equilibrium quotient was measured at 25 degree C and 35 degree C. At 25 degree C this quotient was 8.4 x 10-5 at [Mu] (ionic strength) = 0 and 25 x 10-5 at [mu] = .318 M. This variation is consistent with the expected changes in activity coefficients. [Delta]H … more
Date: May 15, 1961
Creator: Aprile, Ferruccio. & Martin, Don S., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development and Testing of Low Cost Fuel Elements for Power Reactor Service

Description: The development of swaging and vibratory compaction process for fabrication of clad UO2 fuel rods is described. The cost is less than 50% of that for an equivalent core fabricated from pellets. The irradiation testing of vibratory filled and swaged UO2 rods is reported for burn-ups from 2,000 to 12,000 Mwd/t UO2; the results indicate that the rods are capable of excellent performance power reactors.
Date: June 2, 1961
Creator: Babcock & Wilcox Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Equation of State of Solids at Low Temperature

Description: Technical report describing and evaluating the the three experimental methods for obtaining equation of state data at low temperatures; (1) approximate measurement of the PVT relationship by a piston-displacement technique, (2) the measurement of a heat capacity at constant volume as a function of molar volume and temperature, and (3) direct measurement of the pressure variation of the elastic constants using ultrasonic techniques. X-ray methods also might be applicable.
Date: October 13, 1961
Creator: Bernardes, N. (Newton), 1931- & Swenson, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Investigation of Local Boiling of SM-1

Description: Abstract; SM-1 Reactor Core I Rearranged and Spiked, and Core II with Special Components were analyzed under various off-design conditions to induce nucleate boiling. The steady state code, STDY-3, written for the thermal analysis of pressurized water cores, was employed for the analysis. The code performs a complete steady state parallel channel thermal analysis for both nominal and hot channels. Thermal characteristics of individual elements were investigated while changing the parameters of… more
Date: June 20, 1961
Creator: Bradley, P. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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gem-Bis(disubstitutedphosphinyl)alkanes. II. Extraction Properties of Bis(di-n-hexlphosphinyl)methane

Description: From abstract: "Bis(di-n-hexylphosphinyl)methane, HDPM, [(C6H13)2P(O)]2CH2, has been studied as an extractant for a variety of metals. HDPM was evaluated as an extractant for uranium(VI) and compared with tri-n-octylphosphine oxide, TOPO, (C8H13)3PO. In nonpolar solvents, HDPM forms a polymeric-like substance with compounds of uranium(VI). Viscosity measurements indicate that the molecular weight of this polymeric-like substance is about 100 times greater than the corresponding complex with TOP… more
Date: April 11, 1961
Creator: Burke, Keith E.; Sakurai, Hiroshi; O'Laughlin, Jerome W. & Banks, Charles V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Precipitation of Neptunium Peroxide

Description: 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."
Date: July 1961
Creator: Burney, Glenn A. & Dukes, Ernest K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pyrometallurgical Reprocessing of Thorium-Uranium Fuel

Description: From summary: "A proposed metallurgical procedure for reporocessing Th-U233 fuel has been outlined. Some basic experimental data pertinent to the proposed process which has been published elsewhere has been reviewed and some new data presented. In the dissolution of thorium-uranium alloy in magnesium the data show that protactinium precipitates with the uranium and cerium remains in the magnesium-rich solution. It is expected that yttrium, other light rare earth elements, the alkali and alkalin… more
Date: 1961
Creator: Chiotti, P.; Woerner, P. F. & Parry, S. J. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SM-2 Full Scale Flow Studies Termination Report

Description: Abstract: Hydrodynamic flow studies were conducted on a full scale model of the SM-2 reactor vessel and core. Test fluid was water at 200 psi and 200 degree F. Test facilities, model, and instrumentation design are discussed. Flow distribution in the stationary fuel elements, lattices, and control rods of the second pass was investigated. Pressure losses through the various core components were measured and are compared with calculated values. Observed over-all pressure drop was 71 feet of wate… more
Date: July 30, 1961
Creator: Christenson, J. A.; Richards, W. M. S. & Davidson, S. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hazards Summary Report for the SM-1 Core Temperature and Flow Instrumentation: Task XIV

Description: Abstract; This technical report describes the changes in the SM-1 incurred by the experiment, Core Temperature and Flow Instrumentation (Task XIV), and evaluates the possible hazard involved in these changes. Temperature and flow measurements will be taken on a Task XIV instrumented stationary fuel element, instrumented control rod fuel element and other selected points in the SM-1 core to provide data on the core steady state and transient performance. The hazards evaluation consists of a nu… more
Date: March 30, 1961
Creator: Coombe, J. R.; Brondel, J. O.; Lee, D. H. & Matthews, F. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hazards Evaluation of the SM-1 Penetrated Gasket

Description: Abstract: This technical report describes the as-constructed SM-1 penetrated gasket designed for SM-1 Core and Flow Instrumentation (Task XIV). This report supplements APAE No. 79, The Summary Hazards Report for Task XIV, and evaluates the effects of a postulated failure of this gasket. The effects of failure on the Maximum Credible Accident are determined and conclusions and recommendations for the use of this gasket are made.
Date: September 8, 1961
Creator: Coombe, J. R.; Gebhardt, F. G. & James, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hazards Report for SM-1 Core II Without the SM-1 Core I High Burnup Elements and With the PM-1-M-2 Element

Description: Abstract: The removal of both SM-1 Core I high burnup elements from SM-1 Core II and the insertion of the PM-1-M-2 element and the SM-1 Core I spare element in SM-1 Core II is discussed. Nuclear and thermal characteristics of Core II with these changes are presented and conclusions related to the changes in the hazard potential are made. If the core change indicated by this report is made, local peaking factors will be decreased and burnout ratios will be increased. This, of course, in itself… more
Date: October 7, 1961
Creator: Coombe, J. R.; Lee, D. H. & Mathews, F. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hazards Report for SM-1 Core II With the SM-1 Core II High Burnup Elements Replaced with SM-1 Core I Spare Elements

Description: Abstract: The removal of both SM-1 Core I high burnup elements from the SM-1 Core II and the insertion of two SM-1 Core I spare elements i their places are discussed. Nuclear and thermal characteristics of Core II with the change are presented and conclusion related to the change in hazard potential are made. If the core change indicated by this report is made, local peaking factors will be decreased and burnout ratios will be increased. This, of course, in itself leads to a more conservative… more
Date: October 9, 1961
Creator: Coombe, J. R.; Lee, D. H. & Matthews, F. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hazards Report for Insertion of the PM-1-M-2 Element in the SM-1 Core II

Description: Abstract: This technical report describes the Martin Co. PM-1-M-2 test element and analyzes the potential hazard incurred by its inclusion in the SM-1 Core II. A nuclear analysis develops power distributions and reactivity effects. Hydraulic and thermal analyses develop anticipated burnout heat flux ratios. An evaluation of the risk involved with the inclusion of this element is presented. In view of the narrow margin by which the PM-1-M-2 test element meets the minimum burnout ratios as def… more
Date: September 1, 1961
Creator: Coombe, J. R.; Scoles, J. F.; Brondel, J. O. & Lee, D. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hazards Report for the SM-1 Core II With Special Components

Description: Abstract: This technical report describes the changes incurred in the SM-1 by the insertion of the SM-1 Core II and special components. The special components consist of impact specimens, a boron gradient rod, SM-2 elements, a PM-1-M element, and high burnup SM-1 Core I elements. The change in hazards, due to operation of SM-1 with Core II and the special components is evaluated. The analysis indicates there is no change in hazards.
Date: March 30, 1961
Creator: Coombe, J.; Lee, D.; Segalman, I. & Robertson, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chapter 48: Analytical Chemistry of Cobalt

Description: This report provides a detailed discussion of the analytical chemistry of cobalt, including an introduction, the properties of cobalt, the sampling of cobalt-bearing materials, the separation and isolation of cobalt, the detection and identification of cobalt, the determination of cobalt, and the specific methods for determining cobalt.
Date: 1961
Creator: Dale, John M. & Banks, Charles V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recovery of Plutonium From Metallurgical Reduction Residues

Description: 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."
Date: June 1961
Creator: Dukes, E. Kenneth & Prout, William E., 1921-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor: Core Assembly Physics and Zero Power Tests Report

Description: Results of zero power tests to confirm the nuclear design of the Consolidated Edison Thorium Reactor Core are presented. The maximum core reactivity, control rod worths, and power distribution were measured.
Date: September 1961
Creator: Edlund, Milton C. (Milton Carl), 1924-; Ball, R. M.; Deddens, J. C. & Flickinger, R. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Study of the Potential Applications of Radioisotope Technology to Water Resource Investigations and Utilization

Description: The study which has been carried out under Contract AT(30-1)2477 has as its objective the review of all work which has been done on the application of radionuclear techniques to research in water resources and supply, the evaluation of this work, and the suggestions of specific experiments which must be performed if these applications are to be extended.
Date: January 31, 1961
Creator: Feely, Herbert W., 1928-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of Mixtures of Alcohols by Acylation

Description: From abstract: "Recently a general chemical method for the analysis of mixtures of alcohols appeared, using pyridine catalyzed acetylation and second order kinetics to determine the amount of the faster reacting component. The use of 0.25M isobutyric anhydride in pyridine containing 0.0025M perchloric acid as catalyst promotes the rate of the reaction and diminishes the time necessary to perform an analysis. A mathematical treatment of the data and kinetic plot reduces the number of kinetic poi… more
Date: November 1961
Creator: Fellows, William Dean & Fritz, James S. (James Sherwood), 1924-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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 th… more
Date: July 1961
Creator: Fisher, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hazards Report for the SM-1 Core II Without Special Components

Description: Abstract: This technical report describes the changes incurred in the SM-1 by the insertion of the SM-1 Core II without special components. The SM-1 Core II components were made to specifications very nearly identical to those of SM-1 Core I. The differences consist of europium absorber sections, internal europium flux suppressors in the control rod fuel elements, and low impurity cladding. Each of the SM-1 Core II components with the exception of the five absorber sections new in SM-1 Core … more
Date: April 19, 1961
Creator: Gallagher, J. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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