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NACA Research Memorandums
322
NACA Technical Notes
157
Atomic Energy Commission Reports
138
United States Geological Survey Reports
100
Trace elements investigations report
75
Hanford Works Reports
56
University of California Radiation Laboratory Reports
37
Oak Ridge National Laboratory Reports
34
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31
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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
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Volatility: Fluorinator Design FV-100, Zr-U Fuel Element Processing Phase
Volstility Pilot Plant Mark III Fluorinator will be a double-chamber type vessel, each chamber 2-1/2ft. by 16in. o.d. separated by a 5 in. pipe 15 in. long. ASME flanged and dished heads will be used for the chamber tops and conical sections with a 60º apex angle for the chamber bottoms. A new furnace designed to maintain the complete lower chamber (molten salt + freeboard) above melt temperature will eliminate past experiences of salt solidification on the wall, heads, and in or on the internal process lines. External pipe runs will be sutoresistance heated to allow melting and drain back of salt plugs. The upper chamber serves as a gas de-entrainment and solids precipitation device to retain most of the entrained salt and condensable fluorides in the 100-400°C temperature range.
Date:
May 28, 1959
Creator:
Ruch, J. B.
Object Type:
Report
System:
The UNT Digital Library
Maritime Organic Moderated and Cooled Reactor
Introduction: This document describes the results of a six-week conceptual design study of an organic moderated and cooled reactor (OMCR) power plant adapted to a Class T-7 tanker.
Date:
May 27, 1959
Creator:
unknown
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Sizes of U. S. Steam- Electric Plants
At the present time, plants in the 100-500Mv size range are more numerous and carry the greatest portion (over 50%) of the total steam-electric plant load in the U.S. utilities industry. The contribution of plants of over 1,000-Mv capacity is increasing more rapidly than any other size clarification and at present represents about 10% of the total capacity. By 1962 the TVA will have six plants with capacities of over 1,000-Mv. The largest steam-electric plant in the U.S. is the TVA plant at Kingston, Tenn., with a nameplate capacity of 1,440-Mv. Turbine-generator units are also following a trend of ever-increasing size. In present construction, the 150-200 Mv size range for units is the most common and represents the greatest contribution to capacity. Two units of 500-Mv nameplate rating each, the largest in the U.S., are on order by the TVA, and an 800 Mv unit is contemplated.
Date:
May 26, 1959
Creator:
Robertson, R. C.
Object Type:
Report
System:
The UNT Digital Library
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
Object Type:
Report
System:
The UNT Digital Library
Artificial Cooling of the Columbia River By Dam Regulation Part 1
In early July, 1958, it appeared that Columbia River temperature at HAPO would be near 24.5ºC by the end of August. River temperature were averaging 4º to 5º above 1957 figures and were 3º to 4º above the ten year highs. It seemed desirable to examine the problem to determine if any corrective measure could be taken, since it was apparent that production losses were imminent.
Date:
May 25, 1959
Creator:
Kramer, H. A.
Object Type:
Report
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.
Object Type:
Report
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
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Measurement of the Nuclear Materials Content of Non-Production Fuels
In considering the problems associated with the measurement of SSNM content of Non-Production Fuels, two distinct problems are apparent. The first is the technical problem of obtaining highly accurate measurements in a complicated chemical and physical system. The second is the administrative problem of choosing a measurement system which provides a basic of financial settlement acceptable to both the seller (reactor operator) and the buyer (Commission).
Date:
May 25, 1959
Creator:
Schneider, R. A.
Object Type:
Report
System:
The UNT Digital Library
Radial Thermal Flux Traverses in Natural Uranium - Graphite Lattices
The spatial distribution of thermal neutrons in a reactor lattices cell is of fundamental importance for many reasons. First of all, this information allows the determination of the relative absorption rates in each component of the cell which in turn enables a determination of the thermal utilization, and the diffusion length of the lattice. In addition, the observed spatial distributions of thermal neutrons in the lattice cell is of major interest in testing various approximations to the solution of the transport equation such as the P1 and P3 solutions.
Date:
May 25, 1959
Creator:
Nilson, R. & Oakes, T. J.
Object Type:
Report
System:
The UNT Digital Library
The Effect of Solution and Vessel Thermal Expansion on Volume Measurements in the Chemical Processing Department
The major portion of transfers and inventory in the Chemical Processing Department are dependent on volume measurement. Good volume measurements are therefore essential to good SS material control. Considerable attention has been given to the volume problem especially on primary transfer points. Document HW-57888 discusses the biasing effect pf temperature on manometer oil. HW- 57866 given the procedure for vessel calibration. Other undocumented correspondence has discussed recent calibrations and certain aspects of temperature considerations in the volume determinations. However, there is a need to document for future reference the consideration given temperature and provide at the same time information which covers the temperature angle on all volume methods used in the Chemical Processing Department.
Date:
May 22, 1959
Creator:
Johnson, W. R.
Object Type:
Report
System:
The UNT Digital Library
Report of Fire in Laboratory Hood, Wing I, Building 4500
The fire involved approximately 30 liters of isopropyl alcohol as a result of the ignition of about 16-18 liters of isopropyl alcohol and a slurry of thoria and ammonium nitrate in a 20-liter glass carboy. This material was undergoing a volume reduction by boiling in a floor-type metal hood with Plexiglas sides and 3 sliding door on the front of ordinary glass. The alcohol vapor was vents directly into the hood (Fig1.)
Date:
May 22, 1959
Creator:
Lain, J. E. & Hungerford, T. W.
Object Type:
Report
System:
The UNT Digital Library
Braze Alloys v.s. Atmospheres : Final Report Project 1325
Summary. At the time this project was initiated, all brazing had been confined to small retorts of ten cubic feet capacity or less. Larger assemblies were scheduled which required retorts of over 100 cubic feet capacity. Hydrogen atmospheres had given the best results, however, there was considerable reluctance to use hydrogen in these large retorts from a safety standpoint. It was thought that thru the use of PMC 2252, an argon - 2 1/2% hydrogen gas atmosphere which in non-explosive, sufficient cleaning action might be attoined without the inherent hazards encountered with hydrogen. An investigation of the argon - 2 1/2% hydrogen gas as a brazing atomosphoer
Date:
May 21, 1959
Creator:
Rogers, S. L.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Nuclear and Radiation Hazards Evaluation of SRE Fuel Processing and Storage
Nuclear and radiation hazards have been investigated for all phases of operation to be carried out in the mechanical decladding of SRE fuel elements. The SRE fuel is 2.8% enriched with a maximum burnup of 1,000 Mvd/ton and minimum cooling of 120 days. Each element contains 9 kg of uranium metal (~2 kg U-235) and is made up from 84 slugs (3/4"D x 6'"), clad with (10 mil wall) stainless steel tubing. It is planned to ship the fuel from Santa Susana, California, to Oak Ridge in the modified PAR loop carriers, with a maximum of 10 elements being shipped in each carrier per trip.
Date:
May 20, 1959
Creator:
Suddath, J. C.
Object Type:
Report
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.
Object Type:
Report
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
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library