Technical Report Archive & Image Library (TRAIL) - 45 Matching Results

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The Application of Data Processing Techniques to a Maintenance Work Control Program: Description of a data collection and reporting system which was devised and installed in the Union Carbide Nuclear Company's Y-12 Plant Maintenance Division.
Automatic Bubble Density Measurement with the Hough-Powell System: The Brookhaven Bubble Chamber Group is developing a Hough-Powell fast analysis system (HPD)1 for bubble chamber photographs. High precision measurements are made with a computer controlled flying spot digitizer. We are currently testing the track selection programs for the system. We have just completed a study of a method for automatic bubble density measurements.
Criteria for Evaluating Hazards Involved in Proposed Tests On and/or Modifications To the SM-1: 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.
Cross Sections of 14.5 Mev Neutron Reactions With Special Interest in Ca47 Formation: This report measures the cross sections of isotopes for 14.5 MeV neutrons and compares the author's results with calculated and existing literature values.
Development of Techniques for Power Production From Mixed Fission Products: "An investigation was made into the various processes for the fixation of mixed fission products as solids in order to determine the extent they could be utilized as heat sources for thermoelectric generators. Generators of up to ten watts can be designed and built with state-of-art'' thermoelectric materials and mixed fission products soon to be available from the ldaho Falls calcination pilot plant. Mixed fission products from other processes and plants to be on stream'' in this decade will be capable of fueling practical generators into the kilowatt range using thermoelectric materials available in the same time period. A survey was made on current research and development efforts on waste fixation processes. Studies showed that a wide range of power densities (from 0.002 to 0.2 watts per cubic centimeter) will be available from calcined fission product wasted. An experimental program for the consolidation of low density, Idaho Chemical Processing Plant alumina type wastes is reviewed. Preliminary results indicated that densification factors of three to four are readily obtainable for such wastes."
Eddy Transport in Liquid-Metal Heat Transfer: This report seeks to "develop a practical method of evaluating the eddy diffusivity of heat transfer for liquid metals, so that it can be incorporated into the more or less standard theoretical methods to give heat transfer coefficients which are in reasonable agreement with experimental facts"--from introduction.
The Effect of Temperature on the Yield Strength of the Polycrystalline Hexagonal Ag-Al Intermetallic Phase: The effect of temperature on the yield strength of the polycrystalline hexagonal Ag-Al intermetallic phase was investigated over the temperature range 77 to 775 K. It was found that the curve for yield stress vs temperature for both polycrystalline Ag-33 at .% Al specimens that were heavily cold worked prior to deformation and those that were recrystallized prior to deformation was parallel to that for prismatic slip in single crystals.
Engineering Report on the Design of the Pratt & Whitney Aircraft Forced Convection Alkali Metal Vaporization Condensation Heat Transfer Rig: Summary. A test rig has been designed to obtain basic two phase forced convection liquid metal heat transfer and pressure drop data for use in the design of liquid metal boilers. This engineering report includes background of the boiling problem, partial summary of work done by other investigators, the object, scope, engineering, and operations of this test rig, and a summary of reproducibility tests conducted in a water back-up rig.
Equations of State for Stream-Water Mixtures and Some Representative Applications Analysis: The majority of two-phase flow problems involving equations of state are solved by use of point-wise utilization steam table values. In this manner, problems involving the use of the various flow equations of continuity, momentum and energy are generally forced into iterative solutions. Considerable effort towards the development of an analytical expression for the state equation seems indicated so as to simplify the analysis of two-phase problems, particularly the transient cases. The question of instability of state and mixture condition is particularly apparent in the analysis of systems undergoing phase transformation as demonstrated by the significant difference between simple theory and experimental critical flow determinations. The assumption of homogeneous, equilibrium mixtures is indicated as a first attack upon the problem.
Experimental Investigations of the Removal of Sodium Oxide From Liquid Sodium: Experimental investigations were conducted to obtain additional information on the growth and characteristics of sodium oxide deposits in liquid sodium which could lead to system plugging. These investigations included the removal of sodium oxide from molten sodium by the cold trap method.
Extension of Programs for Calculations of Great Circle Paths and Sunrise-Sunset Times: Modification of an earlier program to remove restrictions in calculating the short or long great circle path.
Fabrication Development of UO2-Stainless Steel Composite Fuel Plates for core B of the Enrico Fermi Fast Breeder Reactor: Experimental work concerned with the development of an inexpensive composite fuel plate with a high burnup potential for application in a 500°C sodium environment as Core B of the Enrico Fermi Fast Breeder Reactor.
Facility Availability Brookhaven Graphite Research Reactor: January 1951 - March 1962: This technical report details and outlines the BGRR facility's operations and performance record over a period of twelve years. The author of this report finds that the reactor is "one of the most stable and dependable in the business." The report includes two figures.
Fast Neutron Interactions with Li⁶ and Li⁷: Abstract: "Measurements have been made of the cross sections for the reactions Id-6(n, dn)He-4 and Li-7(n, tn)He-4 over an incident neutron energy range of 5 - 14 MeV. The energy and angular distributions of all reaction products were determined."
Feed Materials Production Center Summary Technical Report: April 1, 1963-June 30, 1963: This report summarizes several reports pertaining to uranium processing.
Fuel Core Tester - UT-2: Report that "describes an instrument that nondestructively tests uranium fuel element cores by ultrasonic methods" (p. 2).
Ground-Water Test Well 2, Nevada Test Site, Nye County, Nevada: A Summary of Lithologic Data, Aquifer Tests, and Well Construction: Abstract: Ground-water test well 2 was drilled to a depth of 3,422 feet with rotary and cable tool drilling equipment.
Influence of Different Y Chromosomes on Secondary Nondisjunction in D. Melanogaster: Females heterozygous for a wildtype X chromosome from a Samarkand stock and an chromosome of the composition [formula] were tested for the frequency of X-chromosomal non-disjunction and segregation of the X's when Y chromosomes of different types were present in the females. The Y chromosomes used were 1) a normal unmarked Y, 2) [formula], 3) [formula] and 4) [formula] (a chromosome which arose in one of our experiments and has not yet been analyzed). Since this was only a preliminary test no attempt was made to isogenize the stocks. Larger scale experiments are planned in which these and other Y's will be used and the genetic background will be strictly controlled.
Influence of the Doppler Effect on the Meltdown Accident: The influence of the Doppler effect in the core disassembly process following a meltdown accident is examined with a Bethe-Tait type model in which the Doppler effect, as well as core disassembly, is considered in the reactor shutdown process. It is shown that a strong negative Doppler effect can radically reduce the explosive energy release in such an accident. (auth)
An Investigation of a "Dynamic" Theory for Mass Transfer: A new theory is proposed to evaluate individual mass-transfer coefficients without actual experiment.
Investigation of the Hydraulics of Horizontal Drains in Plumbing Systems: From introduction: "In this paper, data obtained by Hunter and by the author are reported from laboratory investigations of (1) surge flow introduced into empty simply drains, (2) attenuation of surges in simple drains, (3) continuous full-section flow in simple drains under substantially steady, uniform conditions, (4) steady flow in compound drains, and (5) surge flow introduced through a branch drain into the side or top of a main drain carrying steady flow."
Isotope Effects on Intermolecular Interactions and Isotopic Vapor Pressure Differences: This report discusses some of the problems in the calculation of isotope effects on the vibrational frequencies of the condensed phase.
Military Field Expedient Shielding Experiment: Convair-Fort Worth, under contract to the U.S. Army Engineer Research and Development Laboratories, performed experiments to obtain data for use in applying field materials to shield portable nuclear-reactor power plants.
Mode Identification in the Iris-Loaded Waveguide of a RF Particle Separator: The theoretical and practical aspects of the accelerating mode (TM01) in iris-loaded waveguides have been covered extensively in many reports and publications. The pulse shortening observed in linacs and the possible application of an iris-loaded waveguides as the deflecting structure for rf particle separators stimulated the interest in the nature of higher order modes. Some experimental results on higher order modes in iris-loaded waveguides are available in references. Results of studies done at CERN are not yet published; they were however communicated to the authors and represented the basis of work done at Brookhaven. A preliminary account of BNL results was given in reference. The purpose of this report is to describe the model measurements which were necessary to determine the geometry of a brazed or electroformed prototype for a deflecting waveguide. At the same time, a systematic investigation of other than the deflecting mode was done to ensure a nondegenerate field solution at the operating frequency. The measurements are compared with computational results obtained on the IBM 7090 at BNL.
Molecular Geometry and the Vapor Pressure of the Isotopic Ethylenes; Chemical and Structural Isomers: This report details a study of the vapor pressures of deuteroethylenes and C13 ethylene.
The "N" on "P" Silicon Solar Cell Gamma Ray Dose Rate Meter: The recently developed "n" on "p" type silicon solar cell has been evaluated for application as a high-level gamma radiation dose rate meter. The solar cell ionization current was found to be a linear function of dose rate in a range 10 2 to 10 7 rads per hour. A degradation rate of approximately one per cent per megarad was measured after stabilization with twenty megarads of cobalt-60 gamma radiation. The system has proven to be stable over long periods of time. Temperature dependence corrections have been found to be .0 per cent per degree centigrade between 0 and 60 degree centigrade.
Once Through Decontamination Studies- Interim Report No. 2: The decontamination of the present Hanford reactors involves a once-through cleaning operation. Considerable interest has been shown in determining the feasibility of this once-through technique for cleanup of certain portions of the NPR system. This is the second interim report of a series that covers tests performed in the 242-B Single Pass Flow Facility. The first was distributed in January, 1960.
Perturbation Techniques for the Deflecting Mode: The descriptive parameters of a waveguide with smooth or periodic structure are most easily measured in a waveguide section of suitable length which is transformed into a resonant cavity by placing short circuits at both ends. Measurements of dispersion diagram, phase velocity, group velocity, voltage attenuation coefficient, shunt impedance, field configuration, etc. all involve some form of perturbation technique. The introduction of a perturbing object in a resonant cavity changes the stored electric energy We and magnetic energy Wm by Δwe and ΔWm' resulting in a frequency shift Δf of the resonant frequency f, which is given by the perturbation formula of J. Muller.
Positron Scanner for Locating Brain Tumors: This report describes a system that uses positron emitting isotopes for locating brain tumors.
Possible Use of a Betatron Core on the Cosmotron: Most existing electron synchrotrons use betatron start for initial acceleration of the particles. The subsequent synchrotron acceleration is then performed with a nearly constant radio-frequency. Investigation of the effect of turn-on rate and initial energy spread is made mathematically. Several advantages are seen for such a technique. (D.C.W.)
Procedures for the Study of Bile Physiology in the Rat: This report describes procedures to "secure acceptable samples of bile from unanesthetized, nondepleted rats and sequential quantitative analysis with negligible experimental failure"--from abstract.
Proembryo Irradiation to Produce Blue-Fluorescent and Albino Seedlings: Technical report outlining an experiment to introduce radiation to maize plants after pollination to produce blue-florescent and albino seedlings.
A R.F. Vernier Time to Pulse Height Converter: This technical report describes a pulse height converter that employs the R.F. vernier method. This particular converter has been developed for use with the pulsed beam facility of the BNL Van de Graaff. This report then details a number of tests of the converter made using a RIDL model 34-12, 400-channel analyzer. The report includes 6 figures and 4 circuit diagrams to accompany the findings.
The Radiolysis and Pyrolysis of Several Polyaromatic Compounds: The radiolysis of several polyaromatic compounds which might be used as coolant material in a reactor was investigated using both gamma and reactor radiation. The compounds selected were naphthalene, anthracene, naphthacene, pyrene, phenanthrene, 1, 2 benzanthracene, chrysene, triphenylene, 9, 10 dihydrophenanthrene, phenazine, 7, 8, benzoquinoline and m-phenanthroline, in addition to the uncondensed ring compounds, biphenyl, ortho, meta and para terphenyl and bibenzyl. Gas yields, percentage decomposition, percentage "high boiler" and number average molecular weights were determined. A correlation was found between radiation stability and electron affinity and singlet triplet excitation energies. The most stable compounds were the condensed ring compounds, naphthalene, pyrene, chrysene, phenanthrene and triphenylene.
Reactor Containment Design Study: Introduction: Sargent & Lundy was authorized on November 1, 1960, to make an economic and technical feasibility study of various reactor containment designs which are being utilized for several power plants now under construction.
Separation and Spectrophotometric Determination of Rare Earths: Technical report. From Summary : "At the present time arsenazo appears to be widely used for the spectrophotometric determination of rare earths. Unfortunately, the method is not selective. The separation of rare earths and yttrium from interfering elements has been studied, and the following method has been proposed. Rare earths are precipitated as fluorides using fluorides using calcium fluoride as the carrier. Thorium and zirconium are removed by extraction with thenoyltrifluoroacetone (TTA) in xylene at pH 1.3. Small amounts of residual aluminum, iron, etc. are removed by extraction with 8-quinolinolchloroform at pH 4.5. Rare earths are separated from calcium by TTA extraction at the same pH, and they are then back-extracted into 1 M nitric acid. After evaporation of the solution, the rare earths are determined spectrophotometrically with arsenazo."
The Separation of Cerium from the Trivalent Rare Earths Using Hydrogen Peroxide and Sodium Acetate: At the present time, cerium-144 and premtheium-147 are the two fission product rare earths that appear most promising for use as the heat source in isotopic power units. Under proper conditions, cerium and the trivalent rare earths can be extracted from the Purex fission product waste stream as an insoluble sodium-rare earth double sulfate. A reprecipitation as the double sulfate, dissolution of the hydroxide, serves to give almost complete separation from the corrosion products, inert constituents of the waste, and from most of the fission products. The cerium and the trivalent rare earths must then be separated from each other. In the case of cerium recovery, it is necessary to remove the trivalent rare earths in order to maximize the specific activity of the cerium. If promethium is the desired product, a preliminary cerium separation is desirable to protect the ion-exchange resin (used for separating promethium from its adjacent rare earths) from the intense high-energy radiation from cerium.
The SNAP II Power Conversion System. Topical Report No. 4. Turbine Design and Testing: SNAP II is the designation for a 3 KW nuclear auxiliary power unit to be used in a satellite vehicle. The SNAP II system consists of a reactor heat source, a mercury Rankine engine and an alternator. A two stage, full admission, axial flow turbine was chose for the APU application. Design details and test results are presented in this report. This work was performed under a subcontract to to Atomics International as part of the Atomic Energy Commission Contract No. AT(11-1)-GEN-8.
A Spectrometer for Study of Neutron Activation of Beryllium-7 as a Function of Energy: Abstract. A neutron diffraction crystal spectrometer with a resolution of 13 microseconds per meter and monochromatic beam intensity up to 10(4)n/cm(2)=sec in the range 0.012-0.400 ev has been constructed for study of the activation cross section of Be7 as a function of energy in the thermal region. First preliminary results using ZnS(Ag) as a detector suggest the possibility of a resonance for the Be7(n,p)Li7 reaction in the region of 0.025-0.050 ev.
Stratospheric Monitoring Program: "The performance of the Model I electrostatic precipitator sampler in recent field and laboratory tests is described and discussed. Two of the four precipitator-bearing balloon flights during this interval reached the floating altitude of approximates 105,000 feet, and the precipitator operated efficiently on both. One sample was collected at the nominal design flowrate of approximates 100 cfm, and the second at approximates -200 cfm. Comparison of the deposition profiles of the stratospheric samples with those obtained under controlled conditions in the altitude chamber indicates that the field samples were collected with >90% efficiency. The laboratory tests also showed that the performance capability of the precipitator improves with increasing precipitator current, and with increasing altitude. One of the above balloon flights carried two Model A-I altimeters with recorder outputs. The two records were identical within plus or minus 250 feet. In addition, variations in altitude indications were consistent with the less sensitive aneroid barocoder measurements from the same flight. A revised Model A-I altimeter with a telemeterable output signal has been designed and constructed. The frequency of the signal is a function of the altitude. A preliminary design concept for a flowmeter with negligible flow resistance is described. It would utilize a velocity profile traverse, with the velocity at the various radial locations measured by ion tracers. Further design considerations for a high volume precipitator configuration are discussed."
Summary of Available Data on the Strontium 90 Content of Foods and of Total Diets in the United States: From Present Programs: "There has been a gradual expansion of the Sr^90 food analysis program to include vegetable foods and finally entire diets. In some cases the analyses have also been extended to other nuclides but these data are so limited that they will not be emphasized in this report. It is expected that considerable data on Ra^226 and other naturally occurring radionuclides will be generated in coming year."
The Thermal Decomposition of Irradiated [alpha] Lead Aside: This report studies the thermal decomposition of unirradiated and heavily reactor irradiated colloidal [alpha] - PbH6.
Thermodynamics of Solutions of Actinides and Fission Products in Bismuth: This report reviews the published work on the thermochemistry of the liquid alloys of bismuth with Th, Pa, U, and Pu and the high-yield fission products, and presents in a unified form the authors' own results in this field.
Transient Reactor Aerothermodynamics: The transient aerothermodynamic processes in a gas-cooled reactor are described in a simplified manner to illustrate some of the fundamental physical phenomena involved, to provide some approximate but useful methods of analysis, and to aid in the understanding and use of more complex computer solutions. The transient heat balance equation for an element of a single reactor channel is derived in terms of aerothermodynamic time constants, and typical analytic solutions for transients are presented. This equation is used in generating the time-dependent equation for the channel exhaust gas temperature. The single-channel analysis is extended to multiple channels. A method for determining the approximate transient temperature envelopes for various reactor components is presented. The effects of aerodynamic and thermal coupling between different reactor channels are illustrated. Some of the simplifying assumptions are investigated with respect to the conditions under which they are valid.
The Use of Ultrasonic in Electrodeposition and Electroplating : a Bibliography: This bibliography contains 20 references on the use of ultrasonic in electrodeposition and electroplating. The bibliography is limited to the period 1955 to 1959, with the references arranged alphabetically by title. Sources used in compiling this bibliography were: Applied Science and Technology Index, ASM Review of Metal Literature, Chemical Abstracts, Industrial Arts, Index, Nuclear Science Abstracts.

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