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Chemical Research Section Progress Report for January 1950 (open access)

Chemical Research Section Progress Report for January 1950

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.
System: The UNT Digital Library
Clarification of Redox Feed (1AF) by Filtration : A Semi-Works Study Progress, Redox Technical Data Study No. 8 (open access)

Clarification of Redox Feed (1AF) by Filtration : A Semi-Works Study Progress, Redox Technical Data Study No. 8

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.
System: The UNT Digital Library
Corrosion of Stellite in Redox Streams (open access)

Corrosion of Stellite in Redox Streams

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.
System: The UNT Digital Library
Determination of Americium (open access)

Determination of Americium

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.
System: The UNT Digital Library
Irradiated Process Slug Film Sampling Apparatus (open access)

Irradiated Process Slug Film Sampling Apparatus

"An apparatus was designed and fabricated to obtain film samples from irradiated process slugs. This apparatus has been used to obtain film samples from slugs of the sodium dichromate elimination test."
Date: October 15, 1952
Creator: Wilson, C. D.
System: The UNT Digital Library
A Report of Particle Contamination, October-December 1951 (open access)

A Report of Particle Contamination, October-December 1951

Report discussing a study on the number of radioactive particles in the atmosphere by Hanford Works. The study's l procedures and results are included.
Date: February 15, 1952
Creator: Paas, H. J. & Thomas, C. W.
System: The UNT Digital Library
The Mechanism of Carrying Pu(III) on Lanthanum Fluoride (open access)

The Mechanism of Carrying Pu(III) on Lanthanum Fluoride

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
System: The UNT Digital Library
The Determination of Americium in Plutonium Product Solutions (open access)

The Determination of Americium in Plutonium Product Solutions

The following report describes the process to determine the method for determination of americium in the presence of plutonium and uranium.
Date: August 15, 1952
Creator: Chetham-Strode, A., Jr.
System: The UNT Digital Library
High Amperage Slug Welding : Final Report [on] 313-120-M (open access)

High Amperage Slug Welding : Final Report [on] 313-120-M

This report presents data recorded during a program made to improve uranium slug quality in January, 1952, to determine what improvements could be made in the welding process.
Date: August 15, 1952
Creator: Lingafelter, J. W.
System: The UNT Digital Library
Recovery of Plutonium From Slag and Crucible (open access)

Recovery of Plutonium From Slag and Crucible

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.
System: The UNT Digital Library
Infrared Measurements on the System Hexone-Water-Uranyl Nitrate (open access)

Infrared Measurements on the System Hexone-Water-Uranyl Nitrate

The following report observes infrared measurements in the region of OH bands, the C2O band vicinity, the low frequency end of the spectrum, and the region of the UO2 band on the system hexone - water - uranyl nitrate.
Date: July 15, 1950
Creator: Burger, L. L. & Moore, R. H.
System: The UNT Digital Library
Apparent viscosity of neutralized and concentrated raw slurry : TBP HW-no. 4 and HW flowsheet (open access)

Apparent viscosity of neutralized and concentrated raw slurry : TBP HW-no. 4 and HW flowsheet

Report describing how the neutralized aqueous waste from the TBP Metal Recovery Process will be concentrated by evaporation to minimize the requirements for underground storage tank capacity.
Date: August 15, 1950
Creator: Allen, A. W. & Harmon, M. K.
System: The UNT Digital Library
Retention of Iodine in Process Solutions by Mercuric Salts (open access)

Retention of Iodine in Process Solutions by Mercuric Salts

Report discussing a study of various types of mercuric salts in order to determine which salt prevents the evolution of iodine which results from sparging.
Date: June 15, 1951
Creator: Holm, C. H.
System: The UNT Digital Library
Laboratory Demonstration of Redox Feed Head-End Treatment ; Ruthenium Volatilization and Manganese Dioxide Scavenging (open access)

Laboratory Demonstration of Redox Feed Head-End Treatment ; Ruthenium Volatilization and Manganese Dioxide Scavenging

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 combining ruthenium volatilization and manganese dioxide scavenging in stainless steel equipment."
Date: July 15, 1951
Creator: Hicks, H. G.; McCormack, C. G. & Roake, W. E.
System: The UNT Digital Library
Electroless Nickel Plating (open access)

Electroless Nickel Plating

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.
System: The UNT Digital Library
The Hydrolysis Products of Tributyl Phosphate and Their Effect on the Tributyl Phosphate Process for Uranium Recovery (open access)

The Hydrolysis Products of Tributyl Phosphate and Their Effect on the Tributyl Phosphate Process for Uranium Recovery

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.
System: The UNT Digital Library
Analytical procedures for the plutonium Metal Fabrication Process (open access)

Analytical procedures for the plutonium Metal Fabrication Process

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.
System: The UNT Digital Library
Effects of Furnance Pressures on Quality of Remelted Uranium : Final Report, Production Test 314-59-M (open access)

Effects of Furnance Pressures on Quality of Remelted Uranium : Final Report, Production Test 314-59-M

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.
System: The UNT Digital Library
The Application of Nuclear Track Emulsions to the Analysis of Urine for very Low Level Plutonium (open access)

The Application of Nuclear Track Emulsions to the Analysis of Urine for very Low Level Plutonium

The following document analyzes plutonium in urine which uses nuclear track film for evaluation of the quantity of separated plutonium.
Date: November 15, 1951
Creator: Schwendiman, L. C.; Healy, John W. & Reid, D. L.
System: The UNT Digital Library
Ionium (Thorium-230) for Radioisotope Preparation (Status Report) (open access)

Ionium (Thorium-230) for Radioisotope Preparation (Status Report)

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 of certain devices in place of chemical batteries . In addition other materials having desired radioactive properties may be produced by neutron bombardment of readily available elements.
Date: December 15, 1959
Creator: Coppinger, E. A. & Rohrmann, C. A.
System: The UNT Digital Library
The Irradiated Rupture Prototype (IRP) Design (open access)

The Irradiated Rupture Prototype (IRP) Design

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.
System: The UNT Digital Library
Division of Reactor Development Programs Monthly Report- August 1959 (open access)

Division of Reactor Development Programs Monthly Report- August 1959

Sinterability studies on mixtures of UO2 and PuO2 powders have been continued. All of the censities from previous sintering experiments have been recalculated utilizing a somewhat different water immersion technique. Since densities of pellete obtained by physical dimensions are inaccurate due to chipping, and water immersion does not account for the open porosity, the pellets were coated with clear krylon before being immersed in water. This effectively sealed the open pores. Plots of density versus composition still indicate a drastic reduction in UO2 sinterability with even the slightest additions of PuO2 and a rapid increase with PuO2 contents greater than 20 weight percent. The following table compares densities of pure UO2 and PuO2 after an eight hour soak time:
Date: September 15, 1959
Creator: McEwen, L.H.
System: The UNT Digital Library
PRTR High Pressure Loop Hazards Survey of Preliminary Scope Design (open access)

PRTR High Pressure Loop Hazards Survey of Preliminary Scope Design

Conceptual design studies conducted at HAPO indicate that the improved thermal efficiencies which can be obtained in a high pressure, high temperature, nuclear-electric power plant might reduce unit power costs substantially. The Plutonium Recycle Test Reactor (PRTR) is designed primarily to investigate various facets of plutonium recycle operation. In order to increases the usefulness of the PRTR as an experimental tool, it is desirable to include facilities for testing materials and fuel concepts under a variety of conditions, including the high temperatures and pressures which may be encountered in future water-cooled power reactors.
Date: October 15, 1959
Creator: Walkup, P. C.
System: The UNT Digital Library
The Spontaneous Fission of Plutonium-240 (open access)

The Spontaneous Fission of Plutonium-240

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.
System: The UNT Digital Library