58 Matching Results

Search Results

Results: 1 - 24 next
open access

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.
Partner: UNT Libraries Government Documents Department
open access

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-
Partner: UNT Libraries Government Documents Department
open access

Application of Amides as Extractants

Description: Technical report. From Abstract : "Laboratory data are given and discussed that outline the potential application of N, N-distributed amides to the separation of uranium, neptunium, and plutonium from fission products."
Date: January 1961
Creator: Siddall, Thomas H., III
Partner: UNT Libraries Government Documents Department
open access

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.
Partner: UNT Libraries Government Documents Department
open access

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.
Partner: UNT Libraries Government Documents Department
open access

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.
Partner: UNT Libraries Government Documents Department
open access

Coolball, a Machine Code for Thermal Analysis of Pebble Bed Reactor Cores

Description: COOLBALL is an IBM 650 machine program designed to calculate local gas and ball temperatures, gas flow, and pressure loses as induced by non-uniform power generation and voidage within an axial flow Pebble Bed Reactor core. This code has been used extensively to study the thermal characteristics of Pebble Bed Reactor cores in support of a broad program for the development of the PBR concept.
Date: [1961]
Partner: UNT Libraries Government Documents Department
open access

Criteria for Evaluating Hazards Involved in Proposed Tests On and/or Modifications To the SM-1

Description: Abstract: This technical report elucidates principles of hazards evaluation. The concept of hazards potential is introduced and utilized to show how a reactor system perturbation will influence its nuclear safety. Literature relating to reactor safety is referenced to provide the sources of information required for hazards analysis and show how they influence a hazards evaluation. A checklist of items which should be considered in evaluating a change, test, or modification is presented.
Date: October 18, 1961
Creator: Scoles, J. F.
Partner: UNT Libraries Government Documents Department
open access

The Decontamination and Recovery of Precious Metals

Description: "This report is the third quarterly report under Contract AT(30-1)-2528 for the decontamination and recovery of precious metals from contaminated scrap. The results described in [2nd quarterly report] and expanded in this report confirm the statement that the method achieves not only the desired decontamination but also produces a product of high purity. In addition the relative simplicity of the method makes it particularly adaptable to large scale manipulation."
Date: 1961
Creator: Nuclear Materials and Equipment Corporation
Partner: UNT Libraries Government Documents Department
open access

Design Criteria for Irradiated Vessels Task 6.0 Summary Report

Description: Abstract: This technical report presents design criteria to prevent the brittle fracture of ferritic reactor vessels that cold occur as a result of the rise in NDT caused by fast neutron irradiation. The criteria require that maximum principal stress in the vessel does not exceed 18 percent of yield stress at temperatures below NDT + 60 degree F. Under certain conditions the allowable stress may be based on the irradiated yield stress. A discussion of brittle fracture and an explanation of the … more
Date: September 29, 1961
Creator: McLaughlin, D. W.
Partner: UNT Libraries Government Documents Department
open access

Detection and Identification of a Ruptured Fuel Element at the SM-1 (APPR-1) Nuclear Power Plant

Description: Summary. In October 1960, increases in the fission product activity of the primary coolant of the SM-1 power plant indicated that a fuel element failure had occurred. Low power tests were run first to determine the nature and magnitude of the defect. Flux tilting experiments were then performed to determine the general location of the failed element. Finally, the primary coolant flowing through each of the fuel elements was sampled at low reactor power for relative iodine activity to determi… more
Date: 1961
Creator: Misenheimer, Leo J.; Purple, Robert A. & Brown, Paul S.
Partner: UNT Libraries Government Documents Department
open access

Determination of Particle Size Distribution by X-Ray Absorption

Description: "As it is frequently necessary to know the distribution of particle sizes in various products used in industrial applications, a number of means have been devised for these determinations. Some of them include direct microscopic measurement, screening of product, extraction of samples from a settling slurry as with the Andreasen pipette, air and liquid elutriation, adsorption of gases and liquids, and light absorption."
Date: [1961]
Creator: Gaudin, Antoine Marc, 1900-1974 & Fuerstenau, Maurice C.
Partner: UNT Libraries Government Documents Department
open access

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
Partner: UNT Libraries Government Documents Department
open access

Diffusion of Krypton Through Uranium Carbide - Final Report

Description: This program was established to develop new information concerning the mechanism of diffusion of fission gases (krypton and xenon) through UO2 and UC. The work was to concentrated on measurements of diffusion rates in unirradiated materials in the temperature range of 1000°C to above 2000°C, these determinations being important to the projected use of refractory fuel materials in high-temperature, high-burnup reactors.
Date: January 10, 1961
Creator: Weinstock, J. J.; Pinkerton, A. P. & Ziegel, K. D.
Partner: UNT Libraries Government Documents Department
open access

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.
Partner: UNT Libraries Government Documents Department
open access

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).
Partner: UNT Libraries Government Documents Department
open access

Experiments and Analysis for SM-1 Core II With Special Components

Description: Abstract: This technical report contains a summary of analytical and experimental work performed on SM-1 Core II, with special components is presented. The effects of these special assemblies upon power distribution and core reactivity were calculated and compared to experimental measurements. A thermal analysis was conducted to determine steady state and transient performance of the special test components of the core as well as some of the hotter standard Core II components. Experimental work… more
Date: January 1, 1961
Creator: Lee, D. H.; Robinson, R. A. & Segalman, I.
Partner: UNT Libraries Government Documents Department
open access

Extended SM-2 Critical Experiments : CE-2

Description: Abstract: This technical report contains a description and results of a second series of critical experiments performed on the SM-2 core mock-up, as additional to the first series of experiments reported in APAE No. 54. The SM-2 core mock-up contains 36.4 kg U-235 and and estimated 67.9 gm B-10. The equivalent diameter and the active height are about 22 in.; the metal-to-water volume ration is 0.344. Data is presented on activation, reactivity, and stuck rod measurements. All measurements were … more
Date: June 30, 1961
Creator: McCool, W. J.; Robinson, R. A.; Weiss, S. H.; Raby, T. M.; Schrader, E. W. & Walthousen, L. D.
Partner: UNT Libraries Government Documents Department
open access

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.
Partner: UNT Libraries Government Documents Department
open access

Fission Product Activity in SM-1 Core I Primary System and Surface Contamination on SM-1 Type Fuel Elements. Task XVIII, Phases 2 and 3

Description: Abstract; The fission product data obtained during SM-1 Core I operation (June 1957 - May 1960) is reviewed briefly and interpreted. Evidence is presented to indicate that a fuel element defect was responsible for the high fission product activity level observed in the primary coolant. Relative escape coefficients are calculated and the defect size estimated. Anticipated fission product levels during SM-1 Core II and SM-1A Core I operation are estimated from alpha surface contamination data o… more
Date: February 28, 1961
Creator: Hasse, Robert A. & Zegger, John L.
Partner: UNT Libraries Government Documents Department
open access

Flow Characteristics of a Circular Weir in a Centrifugal Field

Description: Technical report outlining the use of circular weirs in solvent extraction between liquid phases of nuclear fuel elements. From Abstract : "A correlation of the experimental coefficients was developed to allow calculation of general weir performance."
Date: June 1961
Creator: Webster, Donald S.; Williamson, Clifton L. & Ward, James F.
Partner: UNT Libraries Government Documents Department
open access

Fuel Element Development Program for the Pebble Bed Reactor

Description: Previous results from the Pebble Bed Reactor Fuel Element Development Program had shown the excellent promise of vapor-deposited Al2O3 doq5intw on UO2 particles as a low permeability high temperature fission product barrier. However, since the matrix material for the PBR fuel element is a graphite sphere, carbonaceous coatings on the dispersed fuel particles might be of more interest because of improved particle coating-matrix compatibility and no displacement of neutron moderating materials. … more
Date: 1961
Creator: Sanderson & Porter, Inc.
Partner: UNT Libraries Government Documents Department
open access

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.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen