Serial/Series Title
Oak Ridge National Laboratory Reports
19
HW (Series)
15
Hanford Works Reports
15
Atomic Energy Commission Reports
11
CNLM (Series) (Middletown, Connecticut)
4
Pratt & Whitney Aircraft Company Reports
4
AEC research and development report
3
Civil Effects Test Operations Reports
2
Health and Safety Laboratory Reports
2
Report (U.S. Atomic Energy Commission)
2
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Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959
Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design criteria, and the fabrication of reactor components" (p. 1).
Date:
May 25, 1959
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Brief Review of Heat Transfer Problems Encountered in the Production of Magnetic Fields
The design of internally cooled electrical coils for the production of high frequency intensity magnetic fields presents many new aspects and combinations of the familiar modes of heat transfer. However, the customary methodology appears to be sufficient for preliminary analysis and understanding of those problems. This methodology comprises the derivation of a qualitative, approximate equation expressing the relative performance of the various parts of a system, followed by an examination of this equation in order to locate the limiting features of the system. These features are then investigated by more powerful methods, which in turn provide guidance for development research in the laboratory.
Date:
May 25, 1959
Creator:
Alexander, L. G.
System:
The UNT Digital Library
Problems in Accountability Measurements Associated with the Interim Chemical Processing Program
Available knowledge of precision limits in S.S. accountability measurements and/or calculations by reactor and chemical processing groups is surveyed and summarizes. Experience in comparisons of reactor (production and research) calculations versus chemical plant accountability measurements is also reported. A general tentative conclusion is that available precisions (+/- 0.54 to +/- 0.78% ) in chemical plant measurements is also reported. A general tentative conclusion is that available precisions (+/- 1.0 to +/- 11.0%) possible by calculations (nuclear and/or engineering) of power reactor systems; however, with operation and empirical experience (e.g. less than +/-1.0%
Date:
May 28, 1959
Creator:
Arnold, E. D. & Gresky, A. T.
System:
The UNT Digital Library
Liquid Metal Fuel Reactor Experiment: Dynamic Utility Test Loop
This report provides an overview of the creation of the Liquid Metal Fuel Reactor Experiment program. It furthers the work by constructing a single loop to test all the components required for the 16 loop reactor. This utility loop was also constructed to provide a facility for testing various components such as valves and flow meters.
Date:
May 5, 1959
Creator:
Baker, O. H.
System:
The UNT Digital Library
An Experimental Evaluation of the Radiation Protection Afforded by a Large Modern Concrete Office Building
Abstract: "An experimental study was made to determine the effective shielding provided by a modern reinforced-concrete office building (AEC Headquarters building) from nuclear fallout. Pocket ionization chambers were used for measurement of the radiation-field strength. Fallout was simulated with distributed and point-source configurations of Co-60 and Ir-192 sources. Four typical sections were selected for study, and experiments were performed on each. These included an external wing with exposed basement walls and an external wing with a buried basement. Roof studies were made on an internal wing with a full basement and on the east end of wing A, which has a thin-roof construction. The thick-roof construction of 8 in. of concrete and 2 in. of rigid insulation covers all the building except the east end of wing A, which has 4 in. of concrete and 2 in. of insulation."
Date:
May 1, 1959
Creator:
Batter, J. F., Jr.; Kaplan, A. L. & Clarke, Eric Thacher
System:
The UNT Digital Library
Preliminary report on radioactive mineral deposits in the Gulf Coastal Plain of Texas and Louisiana, north and east of the Guadalupe River
"Approximately 30 radioactive mineral deposits are known to occur in the Gulf Coastal Plain of Texas and Louisianna, north and east of the Guadalupe River. A preliminary field examination and sampling of each deposit has been made"
Date:
May 1959
Creator:
Blair, Robert G.
System:
The UNT Digital Library
The Development of a Fluidized Bed Reactor for the Fluorox Process: Unit operations Monthly Status Reports for the Period November, 1958, Through May, 1959
Results of four experiemental runs in the Fluorox fluidized bed reactor system are reported. The engineering feasibility of UF6 production from UF4 by use of dry air of O2, 2UF4 + O2 = UF6 + UO2F2, in an Inconel fluidized bed reactor at 800-850°C was demonstrated in two experimental tests in which greater than 90% of the theoretical amount of UF6 was collected or measured. Two runs made with crude UF4 (produced from unpurified mill concentrate) as the feed material, showed that UF6 could be produced at 700-725°C but corrosion on Inconel was prohibitive.
Date:
May 26, 1959
Creator:
Bresee, J. C.; Scott, C. D. & Horton, R. W.
System:
The UNT Digital Library
Investigation Of Windows And Shields For Neutron Point Sources
An empirical approach for the evaluation of shielding materials for macrochemical manipulations of spontaneously fissioning heavy elements (curium and californium) has revealed interesting comparisons. High-density metal halide solutions were compared with lead glass and with rare earth glass for use as shielding windows. Laminated shields of lead-paraffin and uranium-paraffin were compared with water and with paraffin for shielding walls.
Date:
May 20, 1959
Creator:
Browne, Howard J.; Kaufmann, John A. & Garden, Nelson B.
System:
The UNT Digital Library
Nitrous Acid Behavior in Purex Systems
In HAPO solvent extraction processes there are two independent aspects of nitrous acid chemistry. One concern the decomposition of the solvent through nitration reactions and the attendant problems. These reactions are autocatalytic in the presence of nitric acid and have threshold values for both temperature and nitric acid concentration for a given solvent below which nitrous acid disappears and above which it is generated with continuous destruction of the solvent. These reactions are identical to those found in the prior study of the hexone system.
Date:
May 1, 1959
Creator:
Burger, L. L. & Money, M. D.
System:
The UNT Digital Library
Survey: Oxidation Characteristics of Columbium and Columbium Base Alloys
Unclassified experimental data concerned with the oxidation characteristics of Nb and Nb-base alloys are presented. The bulk of the results is presented in tabular form and cataloged under laboratory name sub-headings. The theory of alloy development for oxidation resistance is discussed. Methods of evaluating oxidation behavior are outlined.
Date:
May 20, 1959
Creator:
Clough, W. R. (William Raymond); Hirakis, E. C. & Krutenat, R. C.
System:
The UNT Digital Library
Toy Top Plasma Injector
Introduction: "It is the purpose of this note to describe the construction and operation of the plasma injectors used in the magnetic high compression experiments in progress at the Lawrence Radiation Laboratory at Livermore. As the investigations of these injections is still in progress, remarks concerning their operation or the characteristics of the injected plasma are of a tentative nature."
Date:
May 28, 1959
Creator:
Coensgen, F. H.; Cummins, W. & Sherman, A.
System:
The UNT Digital Library
A System for the Automatic Computation of Disintegration Rates From Radiochemical Data
From Abstract: "Automatic computation of these general formulas from raw data and procedures for their adaption to a number of specific analyses are described."
Date:
May 27, 1959
Creator:
Collins, William R., Jr.
System:
The UNT Digital Library
Hastelloy F Dissolver Installation in 321 Building
Hastelloy F is a prime contender as a material of construction for plant dissolvers in the power fuel reprocessing program. Consequently, the fabrication and installation of dissolver was undertaken to delineate any unknown problems associated with the use of Hastelloy F; and, at the same time, to provide a vessel for development studies on the Niflex or the Sulfex processes. The purpose of this report is to describe the actual basis for design as well as to present the problems encountered during the fabrication of the vessels.
Date:
May 25, 1959
Creator:
Cooley, C. R.
System:
The UNT Digital Library
Reprocessing of ARE Fuel, Volatility Pilot Plant Runs E-1 and E-2
After two batches (~ 340 kg) of fluoride salt from the ARE were reprocessed, pilot plant operations were terminated because of a leak through which an estimated 780 g of uranium (as UF6) escaped. Of the 21 kg of highly enriched uranium in the feed, 93.12% was collected as UF6 product, 0.13% represented measured losses, and 3.72% was unaccounted for (leak). An additional 3.03% was reclaimed from NaF beds and equipment washes. The product met both chemical purity and activity specifications for product level UF6. Decontamination from fission products was essentially complete. A gross gamma D.F. was apparently limited by the low activity of the feed salt.
Date:
May 11, 1959
Creator:
Culler, F. L.
System:
The UNT Digital Library
The Scattering of Thermal Radiation Into Open Underground Shelters
From Introduction: "The elimination of the burn hazard in shelters depends upon a separate, systematic investigation of each suspected agent. The purpose of the present investigation was to evaluate the contribution made by radiant energy and, if such contribution proved to be significant, to suggest means of eliminating this component."
Date:
May 1959
Creator:
Davis, T. P.; Miller, N. D.; Ely, T. S.; Basso, J. A. & Pearse, H. E.
System:
The UNT Digital Library
Design Criteria for a Pile Oscillator
In the use of a reactor as a device to measure neutron cross sections, the pile oscillator is often employed because of its much higher sensitivity compared to that available in static reactivity measurements. The factor limiting the available in static reactivity measurements. The factor limiting the available sensitivity is the generation of random noise, which originates in the statistical nature of the chain reaction. In other words, the nuclear reactions which maintain the chain reaction do not proceed uniformly, but rather at rates which fluctuate in time around some average values. These fluctuations limit the accuracy of measurements in the reactor.
Date:
May 25, 1959
Creator:
Dresner, Lawrence
System:
The UNT Digital Library
Niobium Phase Diagrams : Manuscript Report on Niobium-Carbon System
Abstract: "The niobium-carbon system has been determined by X-ray and metallographic examination of sintered and arc-cast alloys. Two carbides exist: hexagonal Nb2C with a limited range of homogeneity, and cubic NbC with a solubility range from 8.25 to 10.25 weight per cent carbon. Dilute alloys freeze by eutectic reaction at 2230 C. The solubility of carbon in niobium is 0.80 at the eutectic temperature, but this decreases rapidly with temperature. Metallographic evidence indicates a peritectic reaction between melt, Nb2C, and NbC; alloys richer in carbon than NbC freeze by eutectic reaction."
Date:
May 6, 1959
Creator:
Elliott, Rodney P.
System:
The UNT Digital Library
The Rhode Island and Providence Plantations Atomic Energy Commission Nuclear Science Center Volume II - Safeguard Report
This report presents the description and safeguard evaluation of an open pool research and test reactor rated at one megawatt. The reactor is being proposed by the General Electric Company to the Rhode Island and Providence Plantation Atomic Energy Commission.
Date:
May 20, 1959
Creator:
General Electric Company
System:
The UNT Digital Library
Parameters of Dissolver Equipment Design - Power Fuel Reprocessing
The Interim Power Fuels Reprocessing Program, as established by the Atomic Energy Commission, provides the service of recovering uranium, thorium, plutonium, etc., from irradiated fuels discharged from non-production reactors of both public and private ownership. To provide this service on an interim basis and at minimum capital investment, the Commission has assigned the processing responsibility for the various fuel types to several AEC sites. The sites are to be assigned fuel types most similar to their normal production. As a result, HAPO has been assigned the responsibility for processing the low enrichment uranium and uranium oxide type fuels with isotopic content up to 5% uranium-235. In addition, some plutonium base fuels will be processed at Hanford.
Date:
May 20, 1959
Creator:
Graf, W. A.
System:
The UNT Digital Library
Thermodynamic Properties of Dilute Aqueous Hydrochloric Acid Solutions at Elevated Temperatures from Electromotive Force Measurements
A study of the thermodynamic properties of dilute aqueous hydrochloric acid solutions at elevated temperatures by an electromotive force method was undertaken for several reasons. First, a great need for fundamental information at elevated temperatures was evident from the growing number of industries making use of aqueous solutions at elevated temperatures. Second, the use of the hydrogen electrode against the silver-silver chloride electrode in dilute hydrochloric acid solutions promised to give fundamental thermodynamic information on an important electrode system as well as on hydrochloric acid over a wide temperature range.
Date:
May 1959
Creator:
Greeley, Richard Stiles
System:
The UNT Digital Library
Design Criteria of a Consumable Electrode Welder for Water Mixing Fuel Elements
During the period when the writer mixing fuel element was being evaluated, a small Litton glass lathe and a General Electric Fillerarc welder were used to weld the mixing spool to the fuel element. Due to the condition of these units and to the numerous difficulties encountered with them, it was deemed necessary to design and procure a semi automatic welding unit which could weld in excess of three hundred fuel elements per day.
Date:
May 12, 1959
Creator:
Hanson. G. R.
System:
The UNT Digital Library
Strontium Program: Quarterly Summary Report, May 29, 1959
From Abstract: "This report is one of a sequence of quarterly reports, each designed to up-date its predecessor beginning with HASL-42, "Environmental Contamination from Weapon Tests". Herein are presented data which have accrued since HASL-55. Levels of strontinum-90 in fallout, milk, air, water, vegetation, foods, and bone are given, based on data available from February 1, 1959 to May 20, 1959."
Date:
May 29, 1959
Creator:
Hardy, Edward P., Jr. & Klein, Stanley
System:
The UNT Digital Library
Eurochemic Information Exchange- Answers to Specific Questions
A number of the questions which have been posed to us in the subject references are commented upon below. These have been reviewed by personanel of the Research and Engineering Operation and the Facilities Engineering Operation, Chemical Processing Department, and of the Chemical Research and Development Operation, Hanford Laboratories Operation. Particular acknowledment is given G. J Alkire, J. P. Duckworth, J. B. Fecht, R. G. Geier, E. R. Irish, H. M. Jones, G. C. Oberg, A. M. Platt, W. H. Reas, W. C. Schmidt, R. J. Sloat, W. H. Swift, M. T. Walling and L. L. Zahn of these organizations for assistance given assembling this information.
Date:
May 5, 1959
Creator:
Hill, O. F.
System:
The UNT Digital Library
Description of Purex Plant Process
Description of Purex plant process for irradiated uranium for the separation and decontamination of plutonium and uranium from each other and from fission products.
Date:
May 19, 1959
Creator:
Irish, E. R.
System:
The UNT Digital Library