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Absorption Spectra of Lanthanide and Actinide Rare Earths
"In recent years a group of Dutch workers has measured the absorption spectra of all the rare earth elements (save promethium) in hydrochloric or nitric acid solutions, and their results have been summarized by Hoogschagen and Gorter."
The Absorption Spectrum of Hydrated Americium Chloride
The following document focuses on the study of the absorption spectra of americium chloride. Large samples and a spectrograph of great dispersion were used.
ABWR: PL-2 Design Report
From preface: This report satisfies the quarterly progress report requirements for PL-1 and PL-2 plant design work for the period ending September 30, 1960 At present time a SL-1 Core 2 is under construction. This is a replacement core for SL-1 (ALPR) and will be identical to a PL-2 core; a PL condenser is under test at the SL-1 facility; final construction plans for PL components and modules which are not site sensitive will be completed in March 1961.
ABWR Design and Development Quarterly Progress Report: July 1 - September 30, 1961
Quarterly design and development progress report on the activities of the Army Boiling Water Reactor (ABWR) Program.
ABWR Design and Development Quarterly Progress Report, January 1 Through March 31, 1962
Quarterly design and development progress report on the activities of the Army Boiling Water Reactor (ABWR) Program.
Accidental Radiation Excursion at the Y-12 Plant, June 16, 1958: Final Report
This report describes the circumstances leading to the accident, attempts to reconstruct the nuclear reactivity conditions, and reviews the dosimetric means and results which were used to help determine the exposure of affected employees.
Accumulating Effect of Carbon on the Velocity of Diffusion Between Alletropic Alloys and Ferronickel
The theory of metallic diffusion should be facilitated if the regularity of the lattice is disturbed mechanically, or by means of an alletropic transformation.
Accumulation and Distribution of Radioactive Strontium, Barium-Lanthanum, Fission Mixture and Sodium in Goldfish
This report details an experiment undergone to determine the amount of radioactive strontium, barium-lanthanum, fission mixture, and sodium accumulated by and distributed within non-feeding goldfish. The report includes tables detailing the findings.
Accurate Nuclear Fuel Burnup Analyses; Eighth Quarterly Progress Report, (September - November 1963)
The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Accurate Nuclear Fuel Burnup Analyses; First Quarterly Report, (December 1961 - February 1962)
The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Accurate Nuclear Fuel Burnup Analyses; Ninth Quarterly Progress Report, (December 1963 - February 1964)
The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Accurate Nuclear Fuel Burnup Analyses; Second Quarterly Progress Report, (March - May 1962)
The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Accurate Nuclear Fuel Burnup Analysis Quarterly Progress Report: Seventh Quarter, June 1963 - August 1963
Quarterly progress report on Accurate Nuclear Fuel Burnup Analysis project.
Accurate Nuclear Fuel Burnup Analysis Quarterly Progress Report: Sixth Quarter, March 1963 - May 1963
Quarterly progress report on Accurate Nuclear Fuel Burnup Analysis project.
The Acetate Complexes of Uranyl Ion and the Solubility of Sodium Uranyl Acetate
The following report provides data based off of the solubility of sodium uranyl acetate that was measured under a variety if conditions.
Acid-Base Equilibria in Tertiary Butyl Alcohol
From abstract: "The dissociation of acids in tertiary butyl alcohol has been studied by potentiometric, spectrophotometric, and conductimetric methods. Values for the over-all dissociation of perchloric and picric acids and several tetrabutylammonium salts were estimated by the Fuoss-Kraus treatment of conductance data. Potentiometric studies were carried out at constant ionic strength in order to minimize activity coefficient variations. An acidity scale was established from potentiometric measurements at a glass electrode, and conductance values of dissociation constants. A method was developed for the evaluation of the over-all dissociation constant of weak acids using potentiometric data for hydrogen ion activities and conductance data for the corresponding anion activities. Over-all dissociation constants are reported for perchloric acid, picric acid, 2,4-dinitrophenol, and benzoic acid. Apparent dissociation constants from potentiometric measurements at a constant ionic strength were determined for hydrobromic, nitric, hydrochloric, picric, and p-toluenesulfonic acids."
Acid-Base Reactions and Kinetics of the Halates in Fused Nitrates
From Abstract : "The mechanism of the reactions of the halates, bromate, chlorate, and iodate, with dichromate in fused alkali nitrates has been shown to involve a fast equilibrium followed by a slow rate determining strip to give oxygen and halogen gases as final products." Experiments outlined serve as insight into the structure of fused salts or fused electrolytes.
Acid-Base Reactions in Fused Salts. Dichromate-Bromate Reaction
Technical report. From Abstract : "The reaction of Lewis acid and base, Cr2O7= and BrO3_, in fused KNO3 - NaNO3 mixtures has been shown to involve an equilibrium followed by a slow decomposition to gaseous products."
The Action of Nitroeyl Chloride on Alkyl-Malemie Acids as a Method of Obtaining Oximes of e-Keta Acids and e-Amine Acids
Various Acids are mixed with Oximes to obtain e-Keta Acids and e-Amine Acids.
The Action of Oxygen on Activated Charcoal
The following report provides information conducted with the purpose of ascertaining the effect of oxygen on activated charcoal at approximately one atmosphere by measuring the amount of CO2 formed over a known length of time.
Activation Cross Sections by Boron Absorption
The following report studies the neutron activation cross-sections with the insertion of boron absorbers in the energy region 10 to 20,000 ev and the elements within the range.
Activation Energy for Fission
Abstract: The experimentally determined exponential dependence of spontaneous fission rate on Z^2/A has been used to derive an expression for the dependence of the fission activation energy on Z^2/A. This expression has been used to calculate the activation energy for slow neutron induced fission and photofission. The correlation with the experimental data on these types of fission seems to be quite good.
The Activation of the Rare Earths by Thermal Neutrons
Corresponding investigations were carried out for rare earths. Fractional estimates of intensities and rough values of the activation cross sections with thermal neutrons for all earther are listed.
The Activation of the Rare Earths by Thermal Neutrons
The present knowledge of artificial radio-activity is more spotty for the rare earths than for any other region of the periodic table. The chief reason for this is the difficulty of obtaining sufficiently pure samples or at any rate such of well-known composition. Rare earthers were investigated through the activation by thermal neutrons.
The Activity Coefficient of Plutonium(IV) Salts in Acidic Solutions
Summary: The activity coefficient of Pu(Cl04)4 was measured in perchloric acid solutions. The procedure used was to measure the extraction of the neutral plutonium(IV)-TTA chelate into benzene-TTA solutions at different perchloric acid concentrations. Equations are presented which show the relation of the extraction coefficients, obtained in the above manner, to the activity coefficient of plutonium(IV) per-chlorate. The activity coefficient of Pu(Cl0~)4 is similar to that of a strong acid, e.g., perchloric acid, in that its value increases rapidly when the perchloric acid concentration becomes greater than 2M. The distribution coefficient of TTA between benzene and aqueous perchloric acid solutions was found first to decrease slightly and then to increase two fold as the perchloric acid was varied from 0.01 to 6M. The activity coefficient of the uranous-TTA chelate in benzene was calculated from the results of solubility measurements. The values of the activity coefficient of UK4 are,within experimental error, identical with the values of the activity coefficient of TTA itself.
Acute Histopathological Effects of Single Doses of Slow Neutrons on Mice
The following report provides information conducted during histological observations made on the anatomy of female mice who have been exposed to 400 arbitrary units of slow neutrons.
Acute Intravenous and Intraperitoneal Toxicity Studies on Sodium Pentaborate Decahydrate and Sodium Tetraborate Decahydrate
This technical report describes the toxicity observations on mice of varying borate-glucose molar ratios and relative potencies (p) (4) for the pentaborate and tetraborate drug. This report outlines the methods and results of this experiment and provides a discussion of the results.
Acute Radiotoxicity of (BA-LA)140 in Rats and Mice : Part I. Preparation and Administration of the Emitters
Barium 140 and its daughter, lanthanum 140, were obtained from uranium fission. The composition of the solutions used in animal studies is given a procedure for delivering toxic doses to small animals and methods for preparing animal tissues for radioactivity measurements are described.
Acute Radiotoxicity of (Ha-La)140 for Rats and Mice. Part III. Effects of Height and Food Intake of Animals Treated with (Ha-La)140
In the (Ha-La)140 experiments mice and rats were injected intraperitonially with toxic doses of radiobarium. The weight curves indicate that there was definite retardation of growth in mice and 2.25 uc/g and in rats at 1.98 uc/g.
The Acute Radiotoxicity of Injected Na²⁴ for Mice and Rats
The following report describes the results from studies based on the toxicity and metabolism of radioactive substances derived from uranium fission. Rats and mice were administered radioactive sodium and reactions and changes were studied.
Acute Radiotoxicity of Injected Yttrium91
Report describing results of experiments that involved injecting radioactive yttrium into animals: "The excretion, retention, and distribution of the yttrium was measured, and its effect on survival and growth was observed. The average total excretion of Y91 to the time of death (from 76 hours to 24 days) was a little less than 30 per cent of the injected dose" (p. 2).
An Addendum to a Parametric Study of the Gas-Cooled Reactor Concept
From introduction: "This report provides background information regarding the study results presented in the first volume of this report and provides information resulting from the studies made on the gas cooled reactor concept."
Addendum to Report HW-30390: Estimated Power Generation in MTR Slug Test Facility
An addendum to report HW-30390 a additional power generation calculation for P, the rate of energy release, in kilowatts, was derived.
Addendum to the Spert IV Hazards Summary Report: Capsule Driver Core
From abstract: "explain all important features pertaining to a new pulsed irradiation reactor, the Capsule Driver, Core, and to analyze the potential problems and hazards of operating this reactor in the existing Spert IV facility."
Additional Extraction and Ion Exchange Studies of Temple Mountain District Ores
Uranium extraction of 95% has been obtained from samples of Temple Mountain ore by a cyclic test procedure in which the new feed was not roasted. This procedure involved acid leaching the ore, flotation and roasting of the carbonaceous material, and acid leaching the roaster calcine.
Additional Measurements on the Army Package Power Reactor Zero Power Experiments ZPE-1 and ZPE-2
During the course of the ZPE-2 experimental program additional measurements were performed such as the evaluation of various absorber section compositions and reactivity studies designed to facilitate analytical techniques
Adiabatic Injection
From introduction comments: The present analysis is intended to examine the relations for "adiabatic" injection in general from a different point of view.
The Adsorption and Surface Reactions of Hydrocarbons on Clean Iridium
From abstract: "The adsorption of ethane, ethylene and acetylene on clean iridium in a field emission microscope has been found to cause characteristic changes in the work function of the iridium surface. Further changes, which are time and temperature dependent, result when such surfaces are heated. Flash filament experiments have shown that the changes in work function upon heating are due to desorption reactions and that the desorbed product consists principally of hydrogen. By assuming a linear relationship between surface coverage and work function, it has been possible to determine the desorption kinetics from the observed rates of work function change at various temperatures. The results are consistent with a mechanism involving stepwise surface dehydrogenation in which a pair of hydrogen atoms is removed from the hydrocarbon molecule in each step, followed by desoption of the adsorbed hydrogen. At very high temperatures the remaining carbon atoms are removed, presumably by evaporation."
The Adsorption of He3 and He4 on Activated Charcoal
The adsorption on activated charcoal of pure He3 at 2.5 and 3°K, and of pure He4 at 4°K has been measured. The volume of gas necessary to form a monolayer is approximately the same for the two isotopes. It is shown that capillary condensation does not occur in this adsorbent at low saturations. The data have been analyzed by a number of methods with consistent results.
Adsorption of Radioactive Gases on Activated Carbon
The purpose of this experiment is to study the quantitative adsorption characteristics of a carbon adsorber bed receiving a radioactive inert gas in a helium stream. An objective of the experiment is to measure the equilibrium transmission of the radio-active gas through a carbon adsorber in order to determine if radio-active decay of the adsorbed gas permits additional adsorption.
Adsorption of Zirconium-Niobium on Silica Gel
From abstract: "Adsorption of radioactive zirconium-niobium from uranyl nitrate solutions by silica gel was increased by increasing the temperature and time the solution contacts silica gel, and decreased by "aging" the solutions before contacting the silica gel."
Adult Health Study : Review of Substudies, June 1962, Hiroshima and Nagasaki
Data are summarized from a series of studies to determine the late effects of radiation in adult populations of Nagasaki and Hiroshima. Results ae reported from studies on skin aging, hair greying, cardiovascular findings, neuromuscular response, antibody levels, ocular aging, auditory aging, and miscellaneous aging characteristics in persons exposed to radiation from the atomic bombs as adults; growth and development studies on exposed persons born between 1935 and 1945; the incidence of neoplasms in the exposed populations; possible genetic effects of radiation in selected groups; the incidence of tuberculosis and other infectious diseases in exposed populations; hematological studies; metabolic studies, and other related studies in exposed persons and their offspring. Possible future programs are discussed.
Advanced Designs and Special Applications for Fast Breeders
The purpose of this paper is to describe a few of the suggested advanced concepts for fast breeder reactors and to compare these with the standard approach as to their potential advantage. I have attempted to estimate the economic effect of full technical success with each of the proposed concepts. The proposed concepts include: (1) single sodium system, (2) steam-cooled core concept, (3) direct cycle reactor using potassium as reactor coolant and working fluid, (4) molten plutonium-fuel alloy circulated and cooled by a jet of sodium, (5) settled-bed core, (6) molten salt concept, and (7) paste-fuel system.
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development
First part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. I-ii).
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 2. Plant Conceptual Studies
Second part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. II-i).
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients
Third part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 4. Steam Driven Coolant Pumps
Fourth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept
Fifth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Advanced Pressurized Water Reactor Study [Part 1]: Phase 1 Report
From preface: This report covers Phase I of the authorized work, consisting of determination of the specific reactor concept and size for the most economic reactor, preparation of a reference design of the most promising concept and estimated capital and generating costs, evaluation of the variations in cost as a function of unit size, and evaluation of the reductions in ultimate costs for a power station having multiple units of the same type.
Advanced Pressurized Water Reactor Study [Part 1, Supplement]: Phase 2--A Report
From introduction: This report details the progress of the Advanced Pressurized Water Reactor Study.
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