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The Synthetic Liquid Fuel Potential of Oklahoma

Description: Report documenting the suitability of Oklahoma for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest.
Date: June 15, 1951
Creator: Ford, Bacon, and Davis
open access

The Synthetic Liquid Fuel Potential of North Carolina

Description: Report documenting the suitability of North Carolina for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest.
Date: February 15, 1951
Creator: Ford, Bacon, and Davis
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The Synthetic Liquid Fuel Potential of Indiana

Description: Report documenting the suitability of Indiana for plant locations to produce synthetic liquid fuels, based on raw materials such as oil shale, natural gas, and coal.
Date: March 15, 1951
Creator: Ford, Bacon, and Davis
open access

Hydrogeochemical and Stream Sediment Reconnaissance Basic Data for Fresno Quadrangle, California

Description: "Field and laboratory data are presented for 1038 sediment samples from the Fresno Quadrangle, California. The Samples were collected by Savannah River Laboratory; Laboratory analysis and data reporting were performed by the Uranium Resource Evaluation Project at Oak Ridge, Tennessee." (Abstract)
Date: October 15, 1981
Creator: National Uranium Resource Evaluation Program
Location: None
open access

Hydrogeochemical and Stream Sediment Reconnaissance Basic Data Ely Quadrangle, Nevada and Utah

Description: "Field and laboratory data are presented for 1937 sediment samples from the Ely Quadrangle, Nevada; Utah. The samples were collected by Savannah River Laboratory; laboratory analysis and data reporting were performed by the Uranium Resource Evaluation Project at Oak Ridge, Tennessee." (Abstract)
Date: October 15, 1981
Creator: National Uranium Resource Evaluation Program
Location: None
open access

Hydrogeochemical and Stream Sediment Reconnaissance Basic Data Sacramento Quadrangle, California

Description: "Field and laboratory data are presented for 1890 sediment samples from the Sacramento Quadrangle, California. The samples were collected by Savannah River Laboratory; laboratory analysis and data reporting were performed by the Uranium Resource Evaluation Project at Oak Ridge, Tennessee." (from Abstract)
Date: October 15, 1981
Creator: National Uranium Resource Evaluation Program
Location: None
open access

Hydrogeochemical and Stream Sediment Reconnaissance Basic Data for Milbank NTMS Quadrangle (Minnesota, North Dakota, South Dakota)

Description: "Results of a reconnaissance geochemical survey are reported for the Milbank Quadrangle, Minnesota; North Dakota; South Dakota. Statistical data and areal distributions for uranium and uranium-related variables are presented for 662 groundwater and 319 stream sediment samples. Also included is a brief discussion on location and geologic setting." (from Abstract)
Date: June 15, 1981
Creator: National Uranium Resource Evaluation Program
Location: None
open access

High heat flux heater development status report

Description: The development of a high heat flux heater for use in corrosion rate and stress-rupture tests of fuel cladding materials in a sodium environment is described.
Date: June 15, 1968
Creator: McKisson, R. L. & Babbe, E. L.
open access

Chlorotriammineplatinum(II) Ion : Acid Hydrolysis and Isotopic Exchange of Chloride Ligand

Description: Abstract: The acid hydrolysis of [Pt(NH3)3Cl] has been shown to occur to a measurable extent. for this reaction: [APt(NH3)cCl]+ + H2O [chemical equilibrium symbol with rate constant k-1 above and k1 below] [Pt(NH3)c(H2O)]++ + Cl-, the equilibrium quotient was measured at 25 degree C and 35 degree C. At 25 degree C this quotient was 8.4 x 10-5 at [Mu] (ionic strength) = 0 and 25 x 10-5 at [mu] = .318 M. This variation is consistent with the expected changes in activity coefficients. [Delta]H for the reaction was found to be approximately 0. The rate constant, k1 was 2.3 x 10-5 sec.-1 at 25 degree C and it was nearly independent of ionic strength. The acid hydrolysis provides a mechanism for the exchange of the chloride ligand and Cl-. Exchange experiments with Cl36 showed that in addition to the acid hydrolysis, a process, first order in both, [Pt(NH3)3Cl] and Cl- with a rate constant of 6. 10-5 sec.-1M.-1 contributes to the exchange. The behavior of the entire series of chloro-ammines of platinum(II) toward acid hydrolysis and chloride exchange has been summarized, and a likely mechanism for the process has been discussed.
Date: May 15, 1961
Creator: Aprile, Ferruccio. & Martin, Don S., Jr.
open access

Beta Radiation Processing at Rigorous Conditions

Description: Introduction: The literature reflects ever expansive studies of radiation chemistry over the past twenty years However, in the application of radiation processing to chemical reactions, in general and excepting a few isolated cases, the yield of useful products have been so low as to preclude practical utilization. Thus, for many reactions,radiation alone at ambient conditions is not a sufficient agent for economical production. Hence, we are led to the investigation of radiation effects on reactions at elevated temperatures and pressures where the thermodynamics favor more extensive reactions that may be induced by radiation. the probability of developing a successful practical radiation process is increased when applying radiation at rigorous conditions. To have a commercial advantage, a radiation process usually must replace an expensive catalyst system, generate a reaction at somewhat less rigorous conditions than is usually employed or yield a better or unique product of high value. In our investigations, we have examined only the potential of radiation as a replacement for contact catalyst. Results: We have worked with coal extract rather than coal because it can be melted or dissolved to facilitate pumping into the processing unit and, in general, permits easier handling than a solid. From numerous radiation runs with coat extract in the liquid phase, treated with 5000 psi of hydrogen pressure, temperatures up to 430 degree C, and total dose of up to 6 megarand, we have disappointingly but conclusively observed red that radiation does not induce hydrogenation beyond that obtain by thermal reaction alone.
Date: November 15, 1963
Creator: Yavorsky, P. M. & Gorin, E.
open access

The Air-Launched Balloon System (ALBS) Development Program, Phase 2

Description: Abstract: The circumstances leading to the second phase of the Air-Launched Balloon System Development Program are described, along with the governing design constraints. Individual component development efforts and system design modifications are described in turn: the procurement and testing of the new dewar, the qualification of the updated cryogenic unit recovery system. The complicated command, control, and telemetry subsystem is also described in detail. The results of component tests and a system dress rehearsal system tests are summarized. Preparations for two full-scale system tests conducted in 1981 are covered in considerable detail. The results of those tests are presented and the test data are analyzed. It is concluded that the system's air-launch and mid-air inflation techniques are acceptable. The balloon requires structural reinforcements, however, before the system can be said to be fully developed.
Date: December 15, 1981
Creator: Carten, Andrew S., Jr.
open access

Ionium Recovery Plant Design Report: Topical Report

Description: The following report documents the study of the recovery of thorium by solvent extraction in pilot plant pulse columns, using a filtered liquor from nitric acid digestions of the raffinate cake produced by the ethyl ether extraction of uranium from pitchblende.
Date: April 15, 1959
Creator: Edwards, R. M.; Fariss, R. H. & Werkema, R. G.
open access

Mass Spectrographic Analysis of Solids

Description: Technical report regarding he purpose of the investigation was to evaluate the Chicago mass spectrograph as an analytical instrument for solids.
Date: November 15, 1945
Creator: Garrison, Warren Manford, 1915-
open access

The Spontaneous Fission of Plutonium-240

Description: The spontaneous fission rate of plutonium-240 has been redetermined and found to be 1.51 X 106 events/g/hr.
Date: April 15, 1953
Creator: Kinderman, E. M.
open access

The Identification of the Angular Inclusions Present in Rolled Uranium

Description: Hanford uranium contains minute angular inclusions which affect the microstructure, reactivity, and other important factors controlling the serviceability of the metal. Small quantities of the inclusions have been isolated by chemical means, and the x-ray diffraction patterns and chemical analyses of the isolated materials have been determined. As a first step in the identification of the inclusions present in rolled uranium, a search was made for a chemical method of separating the inclusions from the matrix metal.
Date: May 15, 1953
Creator: Scott, F. A.
open access

Removal of the Compound Layer From Decanned Hanford Uranium Slugs by the Use of Sodium Hydroxide

Description: About twenty-five to thirty per cent of the uranium slugs canned in the Metal Preparation Section do not meet specifications and are rejected. These rejected slugs are recovered by a chemical process and prepared for re-canning. The current recovery process consists essentially of a sodium hydroxide-sodium nitrate bath for chemically removing the aluminum can and the bonding medium, followed by hydrofluoric acid and nitric acid baths to remove the remaining compound layer and to pickle the slugs before they are returned to the process canning line. Recent studies have indicated the possibility of using a more economical means of recovery. this includes the mechanical removal of the aluminum can and most of the bonding medium, followed by a chemical removal of the residual compound layer by a solution of sodium hydroxide.
Date: May 15, 1953
Creator: Brandt, H. L.
open access

Physical Properties of Uranyl Sulfate Solutions

Description: Abstract: Measurements are reported of the solubility of uranyl sulfate in water at several temperatures, of the density of uranyl sulfate solutions as a function of concentration, of the variation of density of uranyl sulfate solutions of three different concentrations over a temperature range from 0[degree]C. to about 93[degree]C., and of the pH of uranyl sulfate solutions as a function of concentration as well as of temperature. The pH measurements were taken on uranyl sulfate samples prepared in several different ways and some conclusions are drawn as to the purity of theses samples.
Date: December 15, 1943
Creator: Helmholz, Lindsay. & Friedlander, G.
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