Technical Report Archive & Image Library (TRAIL) - 32,741 Matching Results

Search Results

An Exploration Systems Approach to the Copper Mountain Area Uranium Deposits, Central Wyoming: "This report presents the results of Multidisciplinary investigations of uranium deposits in the Copper Mountain District of central Wyoming."
Surface Sample Site Locations in the Escalante Quadrangle: Map showing locations of 637 surface sediment samples collected from the National Topographic Map Series (NTMS) Escalante 1 x 20 quadrangle for the National Uranium Resource Evaluation Program (NURE).
Errata Sheet for NUREG/CR-1660: Compilation, Assessment and Expansion of the Strong Earthquake Ground Motion Data Base: The compilation, assessment, and expansion of the Strong Earthquake Ground Motion Data Base.
Compilation, Assessment and Expansion of the Strong Earthquake Ground Motion Data Base: Seismic Margins Research Program (SSMRP): A catalog had been prepared which contains information for world-wide, ground-motion accelerograms, the accelerogaph sites where these records were obtained, and the seismological parameters of the causative earthquakes.
Reno 1° x 2° NTMS Areas, Nevada: Data Report: The following data report presents results of ground water and stream sediment reconnaissance in the Reno quadrangle, Nevada.
[Reno 1° x 2° NTMS Areas, Nevada: Data Report: Plates 8 and 9]: Graphs plotting the uranium and conductivity distribution in the ground waters of the Reno quadrangle.
Whidbey Island Intertidal and Shallow Subtidal Benthos: The following report discusses results from two years of sampling the flora and fauna in three habitats on the west coast of Whidbey Island. Included is an analysis of species richness, diversity, community structure, seasonal changes and dominant forms.
Ground Water Sample Site Locations in the Escalante Quadrangle: Map showing locations of 35 ground water samples collected from the National Topographic Map Series (NTMS) Escalante 1 x 20 quadrangle for the National Uranium Resource Evaluation Program (NURE).
National Uranium Resource Evaluation, Ashland Quadrangle, Wisconsin, Michigan and Minnesota: A report regarding evaluations done of the Ashland Quadrangle to find favorability for uranium occurrences in the quadrangles geologic environments. "No favorable areas could be identified or delineated on the basis of available data, and it is concluded that geologic environments in the Ashland Quadrangle are unfavorable for uranium."
[National Uranium Resource Evaluation, Ashland Quadrangle, Wisconsin, Michigan and Minnesota: Appendices]: Report discussing lake-bottom sediment sampling; radon soil gas surveying, and chemical analyses for rock, stream-sediment, ground, spring-water, lake-water, and stream-water samples collected for a report discussing the favorability for uranium occurrences in geologic environments of the Ashland quadrangle of Wisconsin, Michigan, and Minnesota.
[Digitized Accelerogram and Earthquake Tables]: Computer printout listings of three data tables (Digitized Accelerogram, Recording Station, and Earthquake) organized alphabetically by country.
Appendix E. Post Irradiation Examination Results: Report presenting the results of nondestructive and destructive examinations of four fuel rods from Test RIA 1-2.
Appendix F. Wizard Code: Report detailing the computer code used to calculate the cladding temperatures (WIZARD code) from the observed oxidation of the cladding for Test RIA 1-2.
The Role of Secondary Electrons in Photoconductivity: This work treats the influence of the dark conduction on the reinforcement and saturation of photo electric currents in crystals.
Surface Sample Site Locations in the Wells Quadrangle: Maps showing locations of 134 surface sediment samples collected from the National Topographic Map Series (NTMS) Wells 1 x 20 quadrangle for the National Uranium Resource Evaluation Program (NURE).
Negative Ions of Rubidium and Cesium: While investigating the composition of ions formed in a gaseous discharge in the vapors of LiCl, NaI and KI, the authors observed the occurrence of negative ions of lithium, sodium and potassium in the discharge.
Wells 1° x 2° NTMS Areas, Nevada: Data Report (Abbreviated): The following data report presents results of ground water and stream/surface sediment reconnaissance in the Wells quadrangle, Nevada.
Photoconductivity of Some Intermetallic Compounds: The article discusses the photoconductivity possessed by the intermetallic compounds of fixed composition, ZnSb and Mg3Sb2 and their spectral distribution of photoconductivity is measured.
Geology of the Wells Quadrangle: Map showing the geologic features of the Wells quadrangle project area in Nevada, Utah, and Idaho. Scale 1: 250,000.
Ground Water Sample Site Locations in the Wells Quadrangle: Map showing locations of 126 ground-water samples collected from the National Topographic Map Series (NTMS) Wells 1 x 20 quadrangle for the National Uranium Resource Evaluation Program (NURE).
Plane Elastic-Plastic Problem : Plastic Regions Around Circular Holes in Plates and Beams: The paper determines the shape of the elastic regions around circular holes and also determines the stresses in the plastic and the elastic regions.
Ionic Migration in a Counter-Current as a Basis for Electrochemical Exchange Process: The principle and theoretical basis for an electrolytic counter-current process for the enrichment of isotopes is presented.
Some Additional Corrections to the Modern Theory and Nomenclature of Complex Compounds: In this paper the author will give more detailed consideration to the applicability of concepts in the care of the formation of complex compounds. In a previous paper a number of criteria which must be considered in judging the stability of a chemical compound, particularly recommended comparison of electronic and nuclear structures for compounds having atomic bonds.
The Method of Molecular Spectra and the Fractionating of the Rare Earths: The reasons are listed which are in favor of direct visual spectrochemical analysis even of those rare earths which have no characteristics absorption spectrum within the visual range of the spectrum.
About the Electrolytic Production of Dichloroethylene: The information about electrolytic representation of dichloroethylene is presented in this study.
Zrclad Zirconium-Uranium Alloy Rod for Heat Thru-Put Test: The purpose of this work was (1) to investigate the possibility of producing zirconium-clad zirconium-uranium alloy objects by casting the core alloy directly into zirconium and zirconium-3 w/o tin jackets, producing a diffusion bond at the jacket-core interfaces, and (2) to produce small scale heat thru-put test specimens by this method.
Corrosion of Plutonium Alloys in NaK: A plutonium-aluminum alloy containing 4 atom per cent aluminum showed no attack after exposure to purified NaK for one month at 400 C in the absence of any oxide. The same specimen and other plutonium alloys, including pure plutonium, showed marked deterioration in shorter exposure in the presence of oxide films from a welded stainless steel container. Pure uranium was resistant even in the presence of such oxides.
The Manufacture of Aluminum Clad Aluminum-Plutonium Alloy Irradiation Specimens: This report describes the manufacture of 25 Aluminum clad, 10 w/o plutonium-aluminum alloy and 5 w/o plutonium-aluminum alloy cored specimens for Argonne National Laboratory-University of California irradiation tests in the Materials Testing Reactor. The manufacturing method: preparation of cores and cladding material, assembly and welding of compacts, outgassing, roll bonding, shearing, identification marking and final fabrication into napkin "rings" is described in detail. Of ninety-six specimens fabricated, ninety-one were completed as finished specimens. Forty-four of these contained 5 w/o plutonium alloy cores and forty-seven contained 10 w/o plutonium alloy cores. Five specimens ere rejected for bond blistering.
Plaster of Paris Replicas of Reactor Fuel Slugs: A method is described for preparing plaster of Paris replicas of irradiated fuel slugs. An impression mold is made by pouring the plaster about a fuel slug held in a specially designed holder. The slug is removed from the holder and the impression mold issued to cast a replica, also made of plaster of Paris. The replicas, including one end only, are accurate reproduction of the original slug for surface features down to about one-half mil and for dimensions within one or two mills. Two dental impression plasters were found to give satisfactory results. With the limits mentioned, the process will serve the purpose of preserving models of radioactive specimens for use as "museum pieces." However, the procedures are very exacting in achieving such results.
Reactor Engineering Division Quarterly Report March 1, 1953 through May 31, 1953: Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Chemistry Division Section C-1 Quarterly Report, October, November, And December 1952: Report describing the research and development activities related to nuclear chemistry and radiochemistry and basic chemistry conducted by the Argonne National Laboratory Chemistry Division, Section C-1.
Refractive Indices of the Systems Uranium Hexafluoride-Bromine Trifluoride and Uranium Hexafluoride-Bromine Pentafluoride: A spectrometer has been used with a hollow prism electrically heated to 70 C to measure the refractive indices of solutions of uranium hexafluoride in bromine trifluoride and uranium hexafluoride in bromine pentafluoride. The refractive indices of the two binary systems have been expressed as a function of composition.
Rupture Kinetics of Zircaloy-Clad Fuel Elements in High Temperature Water and Steam Interim Report 6 Effects of Carbon and Zirconium Content on Uranium Corrosion and Rupture Mechanism: This is the sixth in a series of interim reports describing various phases of the study of fuel element rupture kinetics and mechanisms. Previous reports issued are: No. 1- Experimental Methods and Procedures, HW-61378, No. 2- Coextruded Rod Elements with Pinhole Defects, HW-61379, No. 3 - Mechanism of the Uranium-Water Reaction, HW - 61799, No. 4 Coextruded Tube Elements with Pinhole Defects and Various Annular Spacings, HW- 62348, No. 5- Comparison of In-Reactor and Ex-Reactor Ruptures, HW-62766. This work is being done in cooperation with the Fuel Element Design Operation of the Hanford Laboratories Operation. J. W. Goffard has been particularly helpful in supplying samples and useful discussions of the results.
Feasibility Report on Fast Exponential Experiment: The general program established at Argonne National Laboratory in connection with the Fast Power Breeder Reactor (PBR) includes performance of exponential experiments on assemblies having compositions which may exist in the reactor core. This report deals with that phase of the program known as the Fast Exponential Experiment which may be described very briefly as follows. An assembly of fissile (U-235) and fertile material (too small to be self-critical) intermixed with poisons (such as are encountered in the mechanical structure and coolant system of a self-sustaining reactor) is fed with neutrons from an auxiliary source. By measurements of the neutron flux within the assembly, important parameters can be calculated which are necessary to the proport design of an actual critical reactor of the same composition.
Zirflex Dissolution of the Annular Cladding of Simulated Power Fuel Elements: The current interest in a tube-in-tube type Zircaloy-2 clad UO2 fuel element for use in the power reactors provided the incentive for a study of the dissolution of cladding from an annular space. The objectives of the study were to compare the estimated rate of dissolution in the annuli with rates on fully exposed metal. Because of an interest from the design standpoint, heat balance data from the study are reported.
Classification of PuO2 Particles: The Biology Operation, Hanford Laboratories, required plutonium dioxide particles in five different micron and sub-micron size ranges. These were to be supplied as a water suspension in small containers. It was necessary to design equipment, suitable for hood operation, which would give a satisfactory separation of these particles.
The Recovery of Fission Product Rare Earth Sulfates from Purex LWW: A research and development program aimed at devising processes for the economical recovery of the potentially valuable long-lived fission products from Purex waste has been under wat at Hanford for several years. When this work has begun, the concentrated waste was primarily a nitric acid solution (6 to 10 M HNO3) containing the fission products and relatively small concentrations of iron, sulfate, and other corrosion products. Flowsheets based on classical separation schemes and rather similar to processes used by the Isotopes Division at the AEC's Oak Ridge operation served to separate the desired fission products from one another and from the corrosion products (1,2,3).These separation schemes employed careful step-wise pH adjustment to precipitate first the iron and then to separate the desired fission products from one another. The flowsheets were demonstrated on a pilot-plant scale with full-level plant waste. However, since the earlier work was complete, plant operations have been modified....
A Geologic Report on the Sand Wash Drilling Project, Moffat and Routt Counties, Colorado: The purpose of this report is to summarize the information obtained by the project, to make geologic interpretations of the information, and to transmit the information and interpretations of the information to the U.S. Department of Energy and the Geology Division of Bendix Field Engineering Corporation, Grand Junction Colorado.
[Appendix B: Petrographic Photomicrographs]: Photomicrographs of core samples submitted for petrographic analysis from Moffat and Routt Counties in northwest Colorado collected for the Sand Wash Basin Drilling Project, which identified areas in the region favorable for uranium occurrences.
Homogeneous Circulating Fuel Reactor Power Plant: Conceptual Design Study Report: The purpose of this report is to present a conceptual design study on a low power electrical and heat generating plant powered by nuclear energy. The nuclear reactor used in this study is the homogeneous circulating fuel type.
The Interaction of Aqueous Be(NO3)2 Solutions With Some Organic Acids: 1. A study was made of the interaction between beryllium ions (Be(NO3)2) and oxalic, malonic, succinic, lactic, citric, maleic, and salicylic acids by determining the H+ ion concentration. It was established that the degree of interaction between Be2+ ions and organic acids can be arranged in the following series: oxalate = malonate > salicylate > maleate + citrate > tartrate > succinate > lactate. 2. The inability of the Be2+ ion to form only slightly disassociated compounds in the reaction with oxalic acid can be used in the determination of aluminum in the presence of beryllium.
Salicylic Acid as a Reagent for the Spectrophotometric Determination of Beryllium: 1. The reaction between beryllium salts and salicylic acid was studied by the spectrophotometric method in the ultra violet portion of the spectrum. The optimum pH value for this process was found to be 9.0 to 9.5. 2. Two independent methods showed that beryllium and salicylic acid form a compound in the ration 1:2. The instability constant was determined for the a complex of the formula (Be OH Sal2)3- names (4.9 +- 0.6) x 10-18. 3. The stability of the complex and the availability of the reagents makes the reaction investigated a suitable one for analytical applications.
Nuclear Applications for Graphite Impermeable to Gases and Liquids: The possibilities of producing graphite impermeable to gases and liquids, and suitable for nuclear applications, are discussed. The physical properties of such graphites depend on the different sealing processes and starting materials developed especially for the purpose. In the development of reactor grade graphite, described in a previous article, Germany was well behind other countries. As far as the making of impermeable graphite is concerned, however, advanced processes for and experience in the manufacture of impermeable materials for the chemical industry were available here before the publication of other research in this field. Liquid -- and gas -- impregnation methods are discussed mainly. The problems of sealing and the degree of impermeability that can be obtained are shown using different measuring techniques. Finally, a description is given of "pyrographite", a newly rediscovered old graphite material.
Flow Resistance and Heat Transfer in Annuli with Roughened Inner Tubes: Pressure drop and heat transfer in annular tubes have been measured. The surface of the inner tube was artificially roughened. The investigation covered a range of Reynolds numbers from 200 to 100,000. The maximum heat flux, directed from the inner tube to the fluid, was about 316 W/cm2 or 2.7 x 10(6) kcal/m(2) h. The heat transfer medium was water. The hydraulic diameter of the annular tube served as characteristic length in the dimensionless Reynolds and Nusselt number. The results of all experiments are presented in graphic form. Heat transfer and pressure drop increase with the degree of roughness and depend on the type and arrangement of the roughness elements chosen.
Helium Researches VIII : a Method of Quantitative Measurement of Small Amounts of Helium: A method of gas measurement in the volume range 10(-4) - 10(-8)cc utilizing Töpler gas transport and Pirani-Stern hot-wire manometer principles is described. Sources of error are discussed and methods of avoiding them are given.
Some Separations of Radioisotopes Using Ethylenediaminetetraacetic Acid: EDTA is an eluant with many possibilities for analytical chemistry. The authors present the results obtained in the separation of carrier-free radioisotopes; separation of Ba, Sr, Y, La; preparation of 228(Ra) from thorium; separation of Ca, Sr, Ba, and Ra. All the results were obtained with Dowex 50.
Determination of Stability Constants in Stepwise Complex Formation: It has been shown by studying the possibilities for determining the constants in stepwise complex formation by the interaction of hydrolyzed metal ions and ligands, that in a vast number of cases the direct measurements of metal ion and ligand activities ae necessary. Complete formulae for calculation are given and the conditions which allow some simplifications are established.
Reactor Engineering Division Quarterly Report September 1, 1952 through November 30, 1952: Report issued by the Argonne National Laboratory covering the quarterly report from the Reactor Engineering Division. A summary of reactor programs, designs, development, and experiments are presented. This report includes tables, illustrations, and photographs.
Chemistry Division, Section C-1, Quarterly Report July, August, and September 1952: Report describing the research and development activities related to nuclear chemistry and radiochemistry and basic chemistry conducted by the Argonne National Laboratory Chemistry Division, Section C-1.
Appendix A. Mineral Occurrences: Table listing the 1,073 known mineral occurrences in the project area, the Dillon, Butte, Hamilton, and Elk City 1º x 2º NTMS Quadrangles. Included is an additional table indexing abbreviations and terms used the mineral occurrence table for host or associated rocks, deposit types, and commodities.

Technical Report Archive & Image Library (TRAIL) - 32,741 Matching Results

Search Results

Add Filters

Applied Filters