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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
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
Trans-Plutonium Isotope Buildup by Neutron Irradiation of Plutonium (open access)

Trans-Plutonium Isotope Buildup by Neutron Irradiation of Plutonium

Graphs for estimation of plutonium and trans-plutonium isotopic content of irradiated plutonium reactor fuel of various initial isotopic compositions.
Date: December 15, 1958
Creator: Brauer, F. P. & Burley, Helen H.
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
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
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
Production of Xe135 for Laboratory Purposes.  Irradiation of Uranium Hydroxide:  Final Report on Production Test 305-15-P (open access)

Production of Xe135 for Laboratory Purposes. Irradiation of Uranium Hydroxide: Final Report on Production Test 305-15-P

The construction and operation of a fission gas generator, containing about 25 grams of uranium in the form of a powder with a high specific surface, are described in detail. The purpose of the work discussed in this report was to examine the feasibility of producing, separating, and assaying samples of Xe135 in preparation for a proposed measurement of the neutron cross section of this isotope. Krypton and xenon are separated by selective adsorption on charcoal at reduced temperature while iodine is removed by charcoal sorption at room temperature.
Date: July 15, 1953
Creator: Culvahouse, J. W.; Finnigan, J. W.; Lefevre, H. W. & Peterson, R. E. (Russell Edwin), 1927-
System: The UNT Digital Library
A Report on Dissolved O2 in the Primary Coolant of the Ker Loops (open access)

A Report on Dissolved O2 in the Primary Coolant of the Ker Loops

A series of tests conducted in an attempt to reduce the observed O2 content of primary recirculation loop water to a value of <0.14ppm by the current loop method which is a combination of pressurizer degasification and venting flow.
Date: April 15, 1959
Creator: Eikum, Leon M.
System: The UNT Digital Library
Scouting Studies in a 5.05-Inch Diameter Redox Pulse Column (open access)

Scouting Studies in a 5.05-Inch Diameter Redox Pulse Column

Investigation of principles of pulse-column design and effects of operating variables.
Date: January 15, 1951
Creator: Figg, W. S. & Bradley, J. G.
System: The UNT Digital Library
Plating Thickness Tester (open access)

Plating Thickness Tester

An electromagnetic eddy current instrument is described that is capable of measuring copper and nickel plating 1 to 8 mils thick plated on bismuth mandrils of various sizes and shapes.
Date: November 15, 1957
Creator: Fitch, C. E., Jr.
System: The UNT Digital Library
Water Temperatures for the Columbia River Above the Hanford Reactors, September, 1946 Through December, 1958 (open access)

Water Temperatures for the Columbia River Above the Hanford Reactors, September, 1946 Through December, 1958

The ambient temperature of the Columbia River is of interest to the Aquatic Biology Operation since it provides a basis for controlling the temperatures in various experimental tanks which contain Columbia River organisms and since it provides some indication of whether conditions are favorable for the valuable species of fish living in the river. Since the start-up of the plant, temperatures of the river water have been taken in the several water treatment plants.
Date: April 15, 1959
Creator: Foster, R. F.
System: The UNT Digital Library
Design Criteria for PRTR High Pressure Loop Project CAH-841 (open access)

Design Criteria for PRTR High Pressure Loop Project CAH-841

The PRTR pressure loop is an experimental facility to be installed in the Plutonium Recycle Test Reactor, Building 309, for use in testing the feasibility of reactor cooling systems utilizing high pressure water or steam as the coolant. It will furnish operating experience with such systems and serve to test fuel elements and components designed to operate in such environments.
Date: October 15, 1959
Creator: Fox, J. C.; Jakub, M. T. & Kelly, W. S.
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
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
The Hanford Remote Pipetter (open access)

The Hanford Remote Pipetter

The Hanford Remote Pipetter has developed into a very useful tool for routine pipetting by semi-skilled non-technical personnel. Radiation exposure to the operators has decreased to normal background levels as proper shielding exists between the sample and the operator. The results achieved by the pipetter have demonstrated its flexibility and simplicity of operation.
Date: January 15, 1954
Creator: Hammill, K. H.
System: The UNT Digital Library
Division of Reactor Development Programs Monthly Report- March 1959 (open access)

Division of Reactor Development Programs Monthly Report- March 1959

Basic Studies. It has been reported previously that mixed crystals of PuO2 and UO2 have a higher sintering rate than UO2 alone. However, results to the contrary were obtained on addition to 1/4, 1/2, 1, 2, 5, and 10 w/o PuO2 to PWR grade UO2. Pellets of the above concentrations were heated for one hour in hydrogen at 100 C intervals from 1000 to 1600C.
Date: April 15, 1959
Creator: Hanford Laboratories Operation Fuels Preparation Department, Irradiation Processing Department
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
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
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
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
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
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
Division of Reactor Development Programs Monthly Report- May 19599 (open access)

Division of Reactor Development Programs Monthly Report- May 19599

Plutonium Fuels Development Basic studies. Experiments to determine the effect of plutonium dioxide additions on the sinterability of UO2 have continued. PuO2 has been added to ball milled PWR grade UO2 as a physical mixture, and in the form of the mixed crystal oxide.
Date: June 15, 1959
Creator: Lewis, M.
System: The UNT Digital Library
Division of Reactor Development Programs Monthly Reports-June 1959 (open access)

Division of Reactor Development Programs Monthly Reports-June 1959

Basic Studies. Sinterability experiments in the system UO2-PuO2 have continued, and data are available at one hour hold times across the UO2-PuO2 composition limits. Sintered densities appear to be markedly dependent on pressed densities with densification occurring very rapidly at higher pressing pressures. The following table illustrates the effect of one hour at temperature on final density for pure plutonium dioxide pressed to both 40 and 60 percent of theoretical density.
Date: July 15, 1959
Creator: Lewis, M.
System: The UNT Digital Library