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Filters to Provide Nearly Monoenergetic X-Rays
Abstract: Four filters for use with a 250 KVP pulsating X-ray machine were constructed to calibrate radiation detection instruments in the energy region below 200 KEV. Approximately monoenergetic beams of 63, 105, 150, and 180 KEV were produced. The spectral distribution was computer suing the formula of Kulenkampff. The energies were found to drop rapidly from the peak values. The average values were checked from absorption curves obtained experimentally and found to deviate from the computed peak values by 10%.
Final Coathanger Design
We have decided to try pressure-moulding coathangers, and this is a report on the specifications and tolerances R. R. Rau and I have calculated
Final Contract Report for September 1, 1959 to August 31, 1960 .
"As presented in the original proposal the project consisted essentially of three parts: Phase I, Development and refinement of a radiochemical flow counting technique for the study of kinetics of reactions in solution ; Phase II, The application of this technique to the detailed study of the mechanism of solvolysis of sulfonium salts in mixed solvents ; Phase II, The further application of this kinetic technique, as a longer term aim, to other reacting systems of biochemical or other interest. This report covers the work of the contractual period 1 Sept. 1959 to 31 Aug. 1960."
Final Design of Sodium-Heated, Modular, Steam Generators for the SCTI
Abstract: The following report covers the final design of the modular steam generators.
Final Design Report: DR-1 Gas Loop
Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.
Final Report: 300 KWe Capsule Nuclear Power Plant Study
This document presents the results of investigations concerned with the conceptual design of a 300 KWe "Capsule" nuclear power plant.
Final Report A CG-791 Containment Test
This report describes and evaluates the Hanford 105 reactor building structures' ability to withstand an internal pressure increase. The means by which their roof and wall surface would contain a pressure buildup 0.3 psi, and prevent contaminant release which might accompany a nuclear incident are discussed. Prototypes of the B, D, DR, F, and H reactor block wall configuration, the corrugated transite roof of the K reactors, and the corrugated transite walls of the K and C reactors are evaluated. Methods of securing certain building components are described, and a comparison of several candidate sealant coatings presented for consideration. These tests were performed at the request of the Design Operation, as part of CG-791, an existing reactor containment program. This series of tests represents only a part of the overall modifications program. A study of the reactor building containment design criteria is available in a Hanford document, HW-59236, by T. O. Brown.
Final Report Chicago Operations Office Steam Separation Program, February-March, 1960
A program of free-surface steam-water separation at 600 psig was carried out in support of the design for operation of the Experimental Boiling Water Reactor at 100 MW thermal. Reduced test data are presented without evaluation since the ANL technical representative received an original copy of the data for evaluation with respect to the EBWR design.
Final Report: Geological, Geophysical, Chemical, and Hydrological Investigations of the Sand Springs Range, Fairview Valley, and Fourmile Flat, Churchill County, Nevada
Report on an evaluation of the Sand Springs Range as a possible location for an underground nuclear study (Shoal Event). Various tests to determine the site's suitability included aerial photography and mapping of the area through various means; drilling and bulldozing to conduct mineralogical and other physical evaluations; gravity, aeromagnetic, and refraction surveys; and studies related to the hydrology of the location and surrounding areas.
Final Report: Investigation of Boiling Flow Regimes and Critical Heat Flux
From abstract: A program to investigate the mechanism of the critical heat flux condition from the standpoint of flow regimes has been initiated at Dynatech for the AEC. This report covers the work done on this investigation in the first year.
Final Report : Large Reactor Study for Sea Water Distillation
From introduction: This report presents the results of a study of large nuclear reactor systems for supplying energy for the distillation of sea water.
Final Report of Piping Components for Organic Coolants
Organic compounds with high boiling points and low corrosion qualities have been considered for use as reactor coolants and moderators. Those being considered, however, have a greater tendency to leak than does water. A program to evaluate mechanical closures to be used for a leak-tight system for organic fluids has been established. Report HW-59446 covered descriptions of the facility used in this study and the primary results of tests covering two liquids, fittings, and instrumentation. This report will cover final results and other pertinent information.
Final Report on Re-entry Flight Demonstration Number Two
Abstract: RFD-2 was the second of Sandia's operational safety flight tests of systems for nuclear auxiliary power.
Final Report: The Cesium-137 Power Program
From introduction: The technology of isotopic power generation, though recent, is a logical extension of the search for power from the atom. Controlled fission of uranium utilizes only a fraction of the total energy made available from this nuclear process.
Final Safeguards Summary Report for the Piqua Nuclear Power Facility
Summary: This report contains a description of the final design of the Piqua Nuclear Power Facility (PNPF); an outline of the test and operating procedures, and the organization and responsibilities; and a summary of the hazards and safeguards analyses that have been conducted to evaluate the safety of the facility operations.
Final Safety Analysis Report: SNAP 1A Radioisotope Fueled Themonuclear Generator
The following report is the final safety analysis report for the Task 2 Radioisotope Powered Thermoelectric Generator prepared by The Martin Company. It presents analyses, tests and evaluation of the operational safety criteria for the generator.
Final Safety Analysis Report: SNAP III Thermoelectric Generator
From summary: An analysis has been performed to determine the ability of the fuel container to withstand the various thermal, mechanical and chemical forces imposed upon the generator by vehicle failures. Where theoretical analysis was impossible, and where experimental evidence was desired, capsules and generators were tested under simulated missile-failure conditions. Thus, the safety limits of SNAP III in a satellite application were defined.
Final Safety Analysis: Ten-Watt Strontium-90 Fueled Generator for an Unattended Light Buoy, SNAP-7A
From introduction: A prototype Strontium-90 fueled generator will be used to fulfill the power requirements of an unattended automatic light buoy...Primary objectives are to provide continuous absolute containment of the radiostrontium fuel...and biological shielding of the direct radiation from the heat source.
Final Safety Analysis: Ten-Watt Strontium-90 Fueled Generator for an Unattended Meteorological Station, SNAP-7C
From introduction: The primary objectives in designing a nuclear safe radiostrontium generator are: continuous absolute containment of the radiostrontium fuel, which is a relatively insoluble and chemically stable fuel compound, and biological shielding of the direct radiation from the heat source. This report evaluates the safety aspects of a prototype Strontium-90 fueled generator which will be utilized by the U.S. Navy to power and unattended automatic meterological station.
Final Summary Report of the Gas-Cooled Reactor Experiment-1
Report describing the Gas-Cooled Reactor test facility, its ongoing testing and evaluations of a test reactor, and its operating conditions and characteristics.
Fire Test of Wooden-Jacket Shield for Radioisotope Shipping Container
"This report covers fire tests conducted on an experimental design of a wooden-jacket shield for radioisotope shipping containers" (p. i).
Fire Tests of Precast Cellular Concrete Floors and Roofs
From Abstract: "The results of an investigation of lightweight, precast cellular concrete planks are given. Fire tests were made of two floor and five roof specimens made up of these planks. Variables, included density of the cellular concrete, thickness and span of the planks, reinforcement, and cover for the latter."
First Quarterly Report - The Study of the Potential Applications of Radioisotope Technology to Water Resource Investigations and Utilization
The objective of the study which is being carried out under contract AT(30-1)-2477 is the exploration of all aspects of research in water resources and supply to determine the potential for using radioisotope technology in this research. Problem areas in the application of tracers in this research are being investigated through the evaluation of past experimentation with radioisotopic techniques and through discussions with those who are active in this work. A series of suggestions relating to these techniques will de drawn up to indicate which techniques should be developed further in order that more extensive applications may be found for them.
Fission Fragment Energy Deposition Efficiency
Technical report describing how to estimate the energy deposition efficiency of the kinetic energy of recoiling fragments from nuclear fission in a chemically reacting system. Since it is not always possible to directly measure the deposition the report describes how to estimate through the aid of fission fragment range data.
Fission Product Activity in SM-1 Core I Primary System and Surface Contamination on SM-1 Type Fuel Elements. Task XVIII, Phases 2 and 3
Abstract; The fission product data obtained during SM-1 Core I operation (June 1957 - May 1960) is reviewed briefly and interpreted. Evidence is presented to indicate that a fuel element defect was responsible for the high fission product activity level observed in the primary coolant. Relative escape coefficients are calculated and the defect size estimated. Anticipated fission product levels during SM-1 Core II and SM-1A Core I operation are estimated from alpha surface contamination data on completed fuel elements. The importance of in-line sampling for monitoring fission product activity is stressed as well as the need for failed fuel element detection methods.
Fission-Product Release from UO2
Release of fission products from UO2 with emphasis on fuel elements operated at higher surface temperatures and lower external pressures than those for pressurized-water systems.
Fission Product Release from UO2 and by High Temperature Diffusion and Melting in Helium and Air.
The experimental demonstration of fission product release from over heated reactor fuel is necessarily subject in many respects to the arbitrary conditions imposed by the experimenter. Since an almost infinite latitude exists in the choice of materials, atmospheres, gas, velocities, temperatures etc., some allowance for an extrapolation to alternate conditions is definitely in order. The conditions imposed in this study are best described as those most likely to maximize fission product release. Two of the most important variables not investigated in the present report are the influence of metal cladding and the difference in internal nuclear heating as opposed to external radiant heating. In addition a significant uncertainty exists in the understanding of diffusion through large masses such as might result from a scaled-up melt down in a reactor.
The Fixation of Caesium on Australian Minerals. Part 1, Vermiculite Minerals
Samples of vermiculite from Young River, W.A., and Kingaroy, Qld., have tested for cation exchange capacity using batch and column experiments. The better material, Young River vermiculite, was given more exhaustive column tests to determine the optimum particle size and to investigate its selectivity for caesium ions in the presence of higher concentrations of competing ions. At the optimum particle size of (-30+60) B.S.S. the cation exchange capacity of Young River vermiculite was approximately 70 meq/100g. With competing cations in solution caesium breakthrough occurs after a very small volume of influent has passed through the bed. It was concluded that neither of these vermiculite minerals would be suitable of medium level radioactive waste treatment.
The Fixation of Caesium on Australian Minerals. Part 2, Zeolite Minerals
Samples from possible zoolite bearing deposits have been tested for cation exchange capacity using batch and column experiments. The best material, Eagleton Quarry pink shale, was given more exhaustive column tests to determine the effect of mineral particle size, influent flowrate, and the presence of competing cations on caseium breakthrough. Diffusion of caesium ions through the mineral particle controls the ion exchange process. At the optimum size of (-30+36) B.S.S. the cation exchange capacity of Eagleton Quarry pink shale is approximately 60 meq/100g. With competing cations in solution the caesium breakthrough occurs after very small influent volumes have passed through the mineral bed and it was concluded that non of the minerals tested would be suitable for medium level radioactive waste treatment. A sample of clinoptilolite from Hector, California was also test for caesium selectivity.
Flame Spectra of Vanadium, Niobium, Rhenium, Titanium and Molybdenum
Abstract Line spectra of vanadium, niobium, titanium, molybdenum and rhenium of sufficient intensity to allow detection at the 1–10 p.p.m. level can be excited in fuel-rich, oxy-acetylene flames. For the strongest lines of tungsten, the sensitivity of detection is 90 p.p.m. Weak lines of zirconium, hafnium, osmium, tantalum and uranium are also observed in these flames. Recordings of the spectra are given along with wavelength tables of the strongest lines.
Flammability Characteristics of Combustible Gases and Vapors
From Introduction: "The purpose of this bulletin is to present a general review of the subject of flammability, and to supply select experimental data and empirical rules on the flammability characteristics of various families of combustible gases and vapors in the air and other oxidizing atmospheres."
Flight Data and Results of Radiochemical Analyses of Filter Samples Collected During 1961 and 1962
Report containing "flight data and (...) results of radiochemical analyses of stratospheric and tropospheric air filter samples collected during Project Star Dust. This report contains data for samples collected during June 1961 to December 1962, the first year and a half of the project" (p. 2).
The Flora of Healthy Dogs: [Part] 1. Bacteria and Fungi of the Nose, Throat, and Lower Intestine
Report documenting the isolation and identification of microorganisms found in the noses, throats, and lower intestines of twenty two dogs. The most frequently observed organisms were E. coli and S. viridans.
Flora of Healthy Dogs: [Part] 2. Isolation of Enteroviruses from Lower Intestines
Fecal specimens from apparently healthy dogs were inoculated into MK, DK, HeLa, and CP cells. Twenty-six cytopathic agents were isolated in MK, 11 in HeLa, and 4 in CP, but none in DK cells. Neutralization tests indicated that all but one of the viruses were either strains of ECHO type 6 or were closely related to it. Twenty-one of 29 dogs were carrying the virus.
Flora of Healthy Dogs: [Part] 3. Incidence and Distribution of Spirochetes in the Digestive Tract of Dogs
Report documenting microorganisms found in dog feces.
Flow Characteristics of a Circular Weir in a Centrifugal Field
Technical report outlining the use of circular weirs in solvent extraction between liquid phases of nuclear fuel elements. From Abstract : "A correlation of the experimental coefficients was developed to allow calculation of general weir performance."
Flow-Regime Transitions at Elevated Pressures in Vertical Two-Phase Flow
Two-phase flow-regime transitions at elevated pressures for a single-component, trichloromonofluoromethane, were investigated for forced-circulation, upward flow in a vertical, rectangular conduit with internal dimensions of 0.380 by 1.050 inches.
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.
Flow Stability of Gas-Solids Suspensions: Final Report
From abstract: One of the principal purposes of the work reported was to study the stability of gas-solids suspensions in the presence of a thermal gradient. Previously reported experience with unstable suspensions is summarized.
Fluidized-Bed Calcination Studies with Stimulated ICPP Waste Solution
At the present time, high-radioactivity-level wastes at Hanford are neutralized and stored as liquid in underground tanks lined with mild steel. This method of storage is relatively inexpensive and is satisfactory on a short-term basis. However, on a long term basis, liquid storage is less desirable than solid storage because of the greater mobility of the liquid. In addition, storage as aa solid would significantly reduce the volume of waste stored. Consequently, various research and development studies have been undertaken in an attempt to develop a practical waste solidification.
Fluorimetric Assay of α-Chymotrypsin
The enzymolysis by α-chymotrypsin of the substrates, N-acetyl-L-tryptophane ethyl ester and N-acetyl-L-tyrosine ethyl ester, was followed by means of fluorescence whose intensity increased fourfold and threefold per mole respectively as substrate was transformed into amino acid. The assay by fluorescence was several orders of magnitude more sensitive than the assay by differential absorption spectra of these substances and was in agreement with it in those concentration regions where both methods overlap. To maintain linearity between concentration and fluorescence intensity, the concentration of substrate should be no greater than 10-4 M/1. In such solutions the rate of esterolysis could be followed with the enzyme at 10-11 M/1.
Fluorine Micas
From Abstract: "In the report, detailed data and descriptions are given on compositions, syntheses, products, and uses, and on the properties including physical, dielectric, chemical, X-ray, optical, and structural."
Fluoroscopic Crystal Investigation
"An investigation was carried out on the possibility of increasing the light output of single crystals by applying an electric field throughout the crystal lattice. Pulses of frequency 2.5 x 10/sup 5/ cps were used with a voltage gradient of 10/sup 4/ volts/cm, and gamma radiation from Cs/sup 1//sup 3// sup 7/ and Co/sup 6//sup 0/ was used to excite the crystals. Tests were run on many types of scintillators. The visible light output was found to be increased by electric pulses for many of the scintillators, the best results being obtained with ZnS(MnCl/sub 2/, AgCl) crystals."
Flux Control for Irradiation Experiments
Abstract: This report reviews various means which have been used to control experimental conditions in irradiation experiments, and presents the concept of local flux control.
Fluxes and Reaction Rates in the Presence of Interferring Resonances
The effects of competition between resonances of different isotopes were investigated. Flux and reaction rate calculations on a Pu/sup 239/-- U/sup 238/ system revealed that U/sup 238/ exhibits both self-shielding and interference effects, the latter becoming noticeable at enrichment of a few per cent. Gold activation was also found to be depressed by the presence of U, but was insensitive at low enrichment values, Investigation of the Pu/sup 239/ resonance integral showed an asymmetric effect involving both interference between potential and resonant scattering and interference with resonance absorption in another isotope. The interference scattering arising in each resonance level had a notable effect on the average change in the Doppler coefficient. (D.C.W.)
Foam-Drive Process for Increasing the Recovery of Oil
Report issued by the Bureau of Mines over tests conducted on the foam-drive process of oil-recovery. Discussion of the foam-drive process is presented. This report includes tables, graphs, and illustrations.
Foam Suppression of Radioactive Iodine and Particulates
" A reliable, efficient and economical method is needed to remove radioactive halogens such as iodine and bromine and particulates from air in many atomic energy installations. One method we have developed which is particularly suited to reactor containment vessels or other large confined areas is foam containment. In this method an ether lauryl sulfate foam containing an iodine reactant is generated, rapidly filling the entire containment volume. This provides a tremendous surface area to which the encapsulated gases and particles can diffuse and be removed."
The Foote Creek and Dutton Creek Formations, Two New Formations in the North Part of the Laramie Basin, Wyoming
A report about two new geologic formations in Wyoming. The Foote Creek Formation consists of beds of fine-grained sandstone with shale, siltstone, and coal beds. The Dutton Creek Formation consists of beds of coarse-grained locally conglomeratic sandstone.
Foothills Mine, Idledale District, Jefferson County, Colorado
Discussing the geologic setting of the Foothills Mine, Idledale District, Jefferson County, Colorado
Foraminifera From the Northern Olympic Peninsula, Washington
From introduction: This report deals with the stratigraphic and ecologic significance of Foraminifera contained in a Tertiary sequence that crops out in the northern part of the Olympic Peninsula, Wash. (pl. 1). The work was done as a part of a program of geologic investigations for oil and gas possibilities conducted by the U.S. Geological Survey.
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