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Neutralization of HNO₃ in Redox ICU an IAW Streams

Description: The following memorandum outlines the procedures used on the neutralization of HNO3 in redox ICU and IAW streams, and the factors influencing their choice. The procedures involve a) hexone removal by evaporation in the presence of a retardant, b) destruction of the retardant, c) nitric acid elimination by boiling with aluminum and d) concentration of the remaining solution by evaporation.
Date: December 10, 1948
Creator: Curtis, M. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Initial Investigation of the Mechanical Properties of Uranium at Elevated Temperatures

Description: Introduction: "Knowledge of the mechanical properties of uranium at elevated temperature is essential in order to understand and predict the fabrication characteristics and pile behavior of this metal. This report presents the experimental data obtained from beta heat-treated specimens which were originally machined from one production, alpha-rolled uranium rod."
Date: December 2, 1952
Creator: Hueschen, R. E. & Pitt, C. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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X-ray Photometric Assay of Plutonium in Metal Castings

Description: This following report discusses certain topics pertinent to the x-ray photometric method, such as the optimum size of sample and of sample concentration, the technique of measurement for high precision, the use of easily prepared uranium standards for future calibrations and corrections for extraneous substances, and it compares results obtained by both x-ray and chemical assays.
Date: December 12, 1952
Creator: Lambert, M. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nitration Reactions of Shell Spray Base under Purex Waste Recovery Process Conditions

Description: Abstract: "Experiments were performed to characterize the types of nitro compounds that might be formed by reaction of Shell Spray Base with nitric acid, to determine the extent of their formation, if any, and their path under conditions of nitric acid recovery in the Purex Process. It is concluded that the instability of Shell Spray Base to nitration, under conditions to prevail in the plant, presents neither a disposal problem nor a safety problem."
Date: December 5, 1952
Creator: Wagner, R. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Heavy Aggregate Investigation

Description: This report follows a manuscript report made in January 11, 1952, and provides results of a survey that gives corrections as well as suggestions for new and local sources of aggregate material in comparison to the original report. These reports were made in response to a heavy desire of improvement in reactor design and shielding.
Date: December 19, 1952
Creator: Brown, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experimental Rolling of Uranium : Lackawanna No. 3

Description: The following report is one of a series of rolling tests to establish the rolling process for Feed Materials Production Center at Fernold, Ohio. The primary objective of this program is to find a mechanically feasible process for continuous rolling of uranium.
Date: December 13, 1951
Creator: Riches, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Valve-Actuated Pulse Column Design and Operation

Description: The following report describes a countercurrent extraction column, which employs timed solenoid valves and pressurized feeds to provide a pulsing action to disperse the phases. This report further describes the 4-stage cycle of the column operation.
Date: December 3, 1951
Creator: Burger, L. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Physical Properties of the System Uranyl Nitrate - Aluminum Nitrate - Nitric Acid - Water - Hexone: Part 6. Distribution Coefficients of Plutonium(IV) Nitrate

Description: Report discussing the properties of plutonium and plutonium's distribution between hexone and aqueous phases, which relates to the function of Redox plants
Date: December 1, 1950
Creator: Groot, C.; Rehn, I. M. & Slansky, C. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Field Handling Study of Heavy Aggregate Concrete

Description: Purpose: "This test was conducted to gain information and experience in the handling of heavy aggregate concrete. The results from this test were to establish procedures for a subsequent program -- "Construction Test of High Density Concrete Shielding.""
Date: December 7, 1951
Creator: Emmons, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Short Time Corrosion Tests of Bronze, Mild Steel, T-304 Stainless Steel and 2S Aluminum in 10% Potassium Tetraborate Solution

Description: Report summarizing corrosion tests meant to determine the corrosion rates of bronze, mild steel, T-304 stainless steel and 2S aluminum in 10% potassium tetraborate solution. Tests were completed under the boiling point of each solution except for 2S aluminum, which was tested at 40C, the approximate temperature in a pile.
Date: December 14, 1951
Creator: Katayama, Y. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Densities of Tributyl Phosphate - Carbon Tetrachloride Solutions Containing Uranium and Nitric Acid

Description: The following report provides the analysis of a large number of unreported data--taken during a study described in report HW-15230--containing density values obtained for solutions of uranium and nitric acid in tributyl phosphate-carbon tetrachloride solutions.
Date: December 20, 1949
Creator: Moore, Robert Lee
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HAPO IB Fission Product Shipping Cask Design Evaluation Report

Description: As a result of the interest in fission products for use as heat sources and/or radiation sources, in early 1960. Hanford was authorized to supply a semi-refined cerium-144 rare earth product to Oak Ridge National Laboratories. Facilities were installed for collecting this product and a cask war designed for shipping this product as a stabilized, dry powder. Since that time, numerous improvements have been made in the design of the HAPO I cask as described in Revision O of this document. In add… more
Date: December 28, 1962
Creator: Smith, C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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