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Chemical Research Section Progress Report for January 1950

Description: The following documents are progress reports that follow chemical research studies in subjects such as ruthenium tetroxile distillations, extraction-scrub studies of zirconium and niobium, and oxidation of plutonium and stabilization of plutonium(VI) during extraction of IAF solutions.
Date: February 15, 1950
Creator: Albaugh, F. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Clarification of Redox Feed (1AF) by Filtration : A Semi-Works Study Progress, Redox Technical Data Study No. 8

Description: The following report was made to determine the effective clarity improvement, flow rate characteristics, and operational problems encountered on passing Redox uranium feed solution through sintered, modified Type 304 stainless steel filter elements.
Date: October 15, 1948
Creator: Cooper, V. R. & Coleman, E. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion of Stellite in Redox Streams

Description: The following report provides results from laboratory tests on the corrosion resistance of various types of stellite facings on astenitic stainless steel T-347 to Redox streams.
Date: May 15, 1950
Creator: Koenig, W. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Determination of Americium

Description: The following report describes a successful procedure used for the determination of americium in the presence of plutonium. Provided are articles listed that describe the research done in developing the method.
Date: October 15, 1952
Creator: Schmidt, H. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Mechanism of Carrying Pu(III) on Lanthanum Fluoride

Description: From introduction: "Analytical procedures for the determination of plutonium samples from the extraction and concentration plants utilize the carrying of the hydroxylamine-reduced trivulent plutonium by coprecipitation on lanthanum fluoride. Most other plutonium procedures also take advantage of the efficient carrying on lanthanum fluoride."
Date: April 15, 1952
Creator: Ralphs, Delbert Lloyd
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recovery of Plutonium From Slag and Crucible

Description: Report evaluating different methods of preparing nitric acid solution and different methods of separating plutonium from this nitric acid solution of slag and crucible. Methods are explained and experimental data is given.
Date: June 15, 1951
Creator: Groot, C.; Hopkins, H. H. & Schulz, W. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Laboratory Demonstration of Redox Feed Head-End Treatment ; Ruthenium Volatilization and Manganese Dioxide Scavenging

Description: From introduction: "The prime motive behind the experiments described in this report and in those preceding it in this series is the desire to reduce the number of Redox cycles necessary for decontamination from fission products of the plutonium and uranium streams sufficient to allow final disposition of these two products...This report deals with the mechanics of manganese dioxide handing, laboratory development of manganese dioxide scavenging, and a series of experiments at multicurie level … more
Date: July 15, 1951
Creator: Hicks, H. G.; McCormack, C. G. & Roake, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Electroless Nickel Plating

Description: Summary: "This investigation showed that a sound , weather-resistant coating can be applied to uranium that the surface to be plated is cleaned and etched properly. Using the proposed two-bath plating method at 80 C., a four-mil nickel coat can be deposited in thirteen hours."
Date: November 15, 1950
Creator: Groot, C. & Hopkins, H. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Hydrolysis Products of Tributyl Phosphate and Their Effect on the Tributyl Phosphate Process for Uranium Recovery

Description: This report follows an investigation on how hydrolysis products of tributyl phosphate (such as dibutyl and monobutyl phosphoric acids, orthophosphoric acid and butanol) effect the tributyl phosphate process for uranium recovery.
Date: April 15, 1951
Creator: Wagner, R. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analytical procedures for the plutonium Metal Fabrication Process

Description: A report describing a the results of a fluorimetric and volumetric method for the determination of fluoride. This method was developed for the determination of ionizable fluorine in gases in the range of 1-500ppm. This method was chosen because the determination depends on the generation of a color rather than the bleaching effect or on a change of color.
Date: January 15, 1951
Creator: Kendall, L. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of Furnance Pressures on Quality of Remelted Uranium : Final Report, Production Test 314-59-M

Description: The following report follows a test for remelting and casting uranium scrap specified that a pressure of 25 microns or less must be attained within the furnace before a charge is melted. The report was made to evaluate the effect of furnace pressures upon the quality if recast uranium metal.
Date: February 15, 1951
Creator: Kattner, W. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Note on Power Recovery From Warm Water

Description: Several studies of power recovery from Hanford pile effluents have been made, from which the conclusion can be drawn that, while recovery of power is feasible, it is costly because of the large volume of vapor which must be handled per kilowatt-hour of energy provided. This note is to call attention to the possibility of developing cheaper machinery than the conventional low-pressure turbine stages considered in previous studies through use of a water expansion cycle.
Date: November 15, 1956
Creator: Wood, E. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects on the Inhour Equation for Reactors Fueled with Mixtures of Fissionable Material

Description: The determination of various parameters such as thermal utilization, resonance escape probability, control rod calibrations and etc. is often accomplished by the measurement of the pile period due to some given perturbation. With the present thoughts being directed towards plutonium fueled reactors, it was felt worthwhile to discuss a few of the basic differences in pile neutron behavior due to the smaller fraction of delayed neutrons per fission of Pu239 and the larger fraction of delayed neut… more
Date: June 15, 1956
Creator: Astley, E. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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NO₂ Exposures from Operations in the 224 U Building

Description: As recommended in a previous report a study of the NO₂ and HNO₃ exposures of plant personnel in the 224 U Building has been made. Concentrations of NO₂ and HNO₃ from the 224 U roof stack, in the concentrator cells, and in the calcining pot rooms have been determined. The problems have been outlined and recommendations have been made for its alleviation.
Date: May 15, 1956
Creator: Gill, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Ionium (Thorium-230) for Radioisotope Preparation (Status Report)

Description: For many years effort has been directed toward the development of means for the practical utilization of the heat evolved from the radioactive decay of certain fission and irradiation products. Fission products, in view of their availability in the plentiful, high-level wastes resulting from the processing of irradiated, nuclear reactor fuels have been most intensively studied for applications where their heat of decay might be converted into useful energy such as electricity for the operations… more
Date: December 15, 1959
Creator: Coppinger, E. A. & Rohrmann, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Irradiated Rupture Prototype (IRP) Design

Description: One of the problems involved in the design of NPR is the method to be used for decontamination, Considerable effort has been made in both laboratories and pilot plants in developing and evaluating decontamination processes under ideal conditions. Promising processes must be tested under prototypical conditions of velocity, water quality, manner of make-up, type and degree of contamination, addition of decontaminating solutions, and so on.
Date: February 15, 1960
Creator: Neibaur, G. E. & Stice, N. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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