Resource Type
Collection
Serial/Series Title
Atomic Energy Commission Reports
164
Hanford Works Reports
68
University of California Radiation Laboratory Reports
62
HW (Series)
43
Oak Ridge National Laboratory Reports
34
UCRL (Series)
24
Los Alamos National Laboratory Reports
22
AECU (Series)
15
General Electric Company Atomic Power Reports
13
NYO (Series) (New York)
13
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392 Matching Results
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Transient Beam Loading In Linear Electron Accelerators
"The subject of beam loading in linear electron accelerators has been discussed. With suitable design it is possible to place the equilibrium electron phase angle well ahead of the crest of the traveling wave in the accelerator. With beam loading the equilibrium position will move toward the crest, but the electron energy will remain constant or nearly so over a considerable range of loading. Some loss in energy will result from moving the equilibrium phase angle off the wave crest but the spread in energies due to beam loading should be reduced.
Date:
May 1957
Creator:
Neal, R.B.
Object Type:
Report
System:
The UNT Digital Library
Theory Of The Constant Gradient Linear Electron Accelerator
"The effect of beam loading upon the design and performance of the accelerator is examined. Results are given in dimensionless form so that the various equations and grams can be used at any operating frequency. The constant gradient accelerator is somewhat less subject to beam loading than the uniform accelerator structure. For an accelerator of given filling time and 20% more."
Date:
May 1958
Creator:
Neal, R.B.
Object Type:
Report
System:
The UNT Digital Library
A Report on the Kinematics of High Energy Electron Scattering
"A convenient summary is given of useful formulas on the kinematics of high energy electron scattering together with a derivation of the relevant formulas for transforming from the center of mass to the laboratory system such parameters as scattering cross sections. The formulas derived hold for any two- body collision: the approximation (m = 0) employed for the electron scattering calculations is rigorously true for the elastic scattering of photons."
Date:
May 23, 1957
Creator:
Bernstein, Jeremy
Object Type:
Report
System:
The UNT Digital Library
Amplitude and Phase Functions for the Revised Parameters of the Cambridge Electron Accelerator
"The phase and amplitude functions describing the betatron oscillations in the synchrotron are calculated using the revised parameters of the Cambridge Electron Accelerator. The results are given numerically and plotted in a graph for one machine period."
Date:
May 27, 1957
Creator:
Lanza, G.
Object Type:
Report
System:
The UNT Digital Library
A Survey of Non-Fuel-Bearing Materials for the Marine Gas-Cooled Reactor
Results of an initial examination of non-fuel-bearing materials for the Marine Gas Cooled Reactor are presented. Areas given specific attention include structural and cladding materials and graphite moderator. Other areas not included because of classification include zirconium hydride moderator and control materials. In each report section, available pertinent information is summarized and a plan for future work is given.
Date:
May 1, 1958
Creator:
Bokros, J. C.; Dijkstra, L; & Merten, U.
Object Type:
Report
System:
The UNT Digital Library
Progress Report No. 54 for the Period through April 30, 1959
This is the fifty-fourth progress report of the Laboratory for Nuclear Science at the Massachusetts Institute of Technology. Progress reported covers the period for Physics and Chemistry through April 30,1959. Progress is reported on: (1) Chemistry of the fission elements group, (2) Nuclear chemistry (inorganic) group, (3) Nuclear chemistry (organic) group, (4) Cosmic ray group, (5) High energy accelerator physics group, (6) Bubble chamber group, (7) Liner acceleratory group, (8) Rockefeller generator group, (9) ONR generator group, (8) Radioactivity group, (9) Cyclotron group, (10) Theoretical group, (11) Personnel listing.
Date:
May 1, 1959
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
A Transistorized Binary Counter for Extreme Environments
A transistorized binary counter circuit is described that operates over a temperature range of -65 degree F to +165 degree F. the supply voltage is 28 + 4 volts and the maximum trigger repetition rate is 5 kilocycles. the binary circuit is pre-settable and resettable by means of a switching arrangement that can be mechanized. Texas Instrument type 904 silicon transistors whose large signal current gain is 2.8 or greater at a -65 degree F can be used in this circuit.
Date:
May 27, 1955
Creator:
Marceau, J. E.
Object Type:
Report
System:
The UNT Digital Library
Counting Room Equipment and Procedures and Sample Preparation
The following are some of the equipment currently used in the Health Physics counting rooms at the Laboratory: scintillation counters, end window beta-gamma counters, precipitcon beta-gamma counter, autoscaler beta-gamma counter, and continuous flow proportional counter. This technical report describes the equipment, supporting equipment, procedures, and sample preparation in use at the Laboratory.
Date:
May 1954
Creator:
Weiss, M. M. & Marshall, J. B.
Object Type:
Report
System:
The UNT Digital Library
A Study of Location Times for Positions Arranged on a Panel in a Random and an Ordered Manner
The results of an experimental pilot study on the location time, for a sequence of N specified positions on a panel, are given for 1 <_ N <_ 30. The positions to be located were randomly arranged on one set of panels and arranged according to an ordering scheme on a second set of panels. Th location time for N positions randomly arranged on a panel varies approximately as N(2). In the case of an order arrangement the location time is essentially proportional to N. Even for as few as 30 positions, the location time for an random arrangement was twelve times greater than for an order panel. For 60 positions the ratio would be 19, and for 90 positions the ratio would be 26.
Date:
May 25, 1955
Creator:
Beeler, J. R.
Object Type:
Report
System:
The UNT Digital Library
Frequency Components of a Step Function and a Sinusoid
Fourier analyses are made on two functions. The first is a step function forward from periodic samples of a sinusoid. If the frequency of the sinusoid is less than one-half of the sampling frequency, it is shown that the step function has no frequency components less than one-half of the sampling frequency other than that of phase, and duration with respect to the interval of the analysis. It is shown that the insertion of a blank space in the period of analysis reduces greatly the uncertainty of the amplitude of the initial sinusoid as estimated from the results of the Fourier analysis. The results of the analyses are useful in the design and evaluation of certain analog data-analyzing systems.
Date:
May 10, 1955
Creator:
McGehee, R. M.
Object Type:
Report
System:
The UNT Digital Library
Principles and Techniques of Ultrasonic Inspection
Ultrasonic inspection for subsurface flaws is widely used in American industry. This report reviews the general principles and specific techniques of ultrasonic testing. The information is based on a review of the technical literature plus the experience of the Quality Assurance Department at Sandia Corporation in applying this nondestructive testing technique to quality evaluation programs.
Date:
May 23, 1955
Creator:
Psillas, Harold C.
Object Type:
Report
System:
The UNT Digital Library
The Propagation of Spherical Shock Waves
This technical report is a summary of unclassified theoretical work on propagation of one-dimensional shock waves and on the propagation of spherical shock waves in gases.
Date:
May 4, 1953
Creator:
Ungar, Eric E.
Object Type:
Report
System:
The UNT Digital Library
Design Study of a Pebble-Bed Reactor Power Plant
Sanderson & Porter have carried out a series of studies over the last four years which indicate that the pebble-bed reactor way be an attractive way to obtain low-cost power. At the request of the Atomic Energy Commission, two design studies have been carried out on this concept at the Oak Ridge National Laboratory. The first of these a preliminary design of a 10-Mw(t) reactor experiment, the PRRE, was initiated September 10, and a report on the study was issued November 1960. The second phase of the work, a conceptual design study of a 330-Mw (e) central station, was initiated November 1, and is the subject of this report.
Date:
May 11, 1961
Creator:
Fraas, A. P.; Carlsmith, R. S.; Corum, J. M. & Foster, J.
Object Type:
Report
System:
The UNT Digital Library
Preliminary Design of a 10-Mw(t) Pebble-Bed Reactor Experiment
The objectives of this study have been to examine the problems of the pebble-bed reactor concept and to conceive a design of a facility for investigating the feasibility of this type of reactor. The design must provide for adequate leaktightness of the contaminated-gas system and adequate maintenance of contaminated components, the most vital feasibility questions of the concept.
Date:
May 8, 1961
Creator:
Fraas, A. P.; Carlsmith, R. S. & Corum, J. M.
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
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
Uranyl Sulfate-Dovex 21K Anion Exchange: A Literature Survey, Review of Preliminary Data and Outline of a Proposal Experimental Program
The system Dovex 21K and aqueous uranyl sulfate solutions were studied in the solution compositions range: 0-0.005 mol/liter uranyl sulfate, 0.15 mil/liter total sulfate, 0.02 mol/liter H2SO4 (pH 2).It is shown that UO3SO4 and/or UO2(SO4)2-/2 are sorbed on the resin to form R2UO2(SO4)2. It is surmized that these same species are also involved at high uranyl concentrations and pH 2 it is suggested that U2O5SO4, U2O5(SO4)2-/2, and R2U2O3SO4 species may be involved.
Date:
May 14, 1959
Creator:
Jury, S. H. & Adams, J. B.
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
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.
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
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
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
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
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