The Determination of Fluoride in Plutonium Metal by Thorium Titration (open access)

The Determination of Fluoride in Plutonium Metal by Thorium Titration

Abstract: "A titrimetric method for the determination of fluoride in plutonium is reported. Prior to a steam distillation of the fluoride, the bulk of the plutonium is separated by precipitation of the sulfate. The fluoride in the distillate is titrated at a pH of 3.2 with 0.001 M thorium nitrate, using chrome azurol-S indicator. Applied to samples containing 1 to 15 parts per million fluoride, the recovery is 87% and the precision on the 95% confidence level is +/- 0.65 ppm."
Date: May 4, 1954
Creator: Ferguson, W. S. & Newell, D. M.
System: The UNT Digital Library
Trip Report of Visit to Puget Sound Naval Ship Yard for Drilling Uranium Slugs (open access)

Trip Report of Visit to Puget Sound Naval Ship Yard for Drilling Uranium Slugs

The following report describes a trip made to Puget Sound Naval Shipyard (P.S.N.S.) for the purpose of having several uranium slugs machined for this purpose.
Date: 1952
Creator: Jones, S. S.
System: The UNT Digital Library
Guide to Application of the X-ray Photometer in Chemical Analysis (open access)

Guide to Application of the X-ray Photometer in Chemical Analysis

From summary: "The relative absorptions of X-rays by various substances are listed as a guide to the application of the X-ray photometric method in chemical analysis and to the estimation of interference by extraneous substances."
Date: June 20, 1952
Creator: Lambert, Maurice C.
System: The UNT Digital Library
Monitoring Survey : Richland to Arco, Period May 9-11, 1952 (open access)

Monitoring Survey : Richland to Arco, Period May 9-11, 1952

This report follows an investigation of a cargo truck found contaminated by various radioactive material on a routine trip from Arco, Idaho to the Hanford plant on May 8, 1952. The report analyzes the truck's route in an attempt to find the location of the contaminating region.
Date: June 20, 1952
Creator: Honstead, J. F.
System: The UNT Digital Library
Liquid-Liquid Dispersions and the Significance of the Disengaging Test (open access)

Liquid-Liquid Dispersions and the Significance of the Disengaging Test

From introduction: "The purpose of this report is to summarize some of the observations on the dispersion and rate of disengaging of liquid-liquid systems and suggest some possible lines of future work."
Date: July 10, 1952
Creator: Burger, L. L.; Dillon, R. L. & Johnson, W. F.
System: The UNT Digital Library
Hanford Works Radiological Sciences Department, Research and Development Activities, Quarterly Progress Report: April - June, 1952 (open access)

Hanford Works Radiological Sciences Department, Research and Development Activities, Quarterly Progress Report: April - June, 1952

Introduction: "This eleventh quarterly report of the research and development activities of the Radiological Sciences Department, Hanford Works, as before, includes some items charged to control but included for general interest. Such are identified as "not charged to research". The previous report of this series was numbered: HW-24131 - April 16, 1952."
Date: 1960
Creator: Hanford Works. Radiological Sciences Department.
System: The UNT Digital Library
A Description of the Acetone-Dye Solution Method of Demarcating a Leak Process Tubing While in the Pile (open access)

A Description of the Acetone-Dye Solution Method of Demarcating a Leak Process Tubing While in the Pile

Abstract: "A method has been devised and successfully used for marking a leaking pile process tube prior to its removal from the pile, such that subsequent location of the leak is more easily accomplished. An acetone solution of Testor's Dark Red Airplane Dope is poured into the suspect tube. The solution leaks from the hole and stains the surrounding area a light pink. To date the method has been used on tubes 3573F, 0486F, 0867F, and 3670F."
Date: July 16, 1952
Creator: DeHollander, W. R.
System: The UNT Digital Library
A Two-Group Calculation of the Transients in an Externally Driven Reactor with Reflector (open access)

A Two-Group Calculation of the Transients in an Externally Driven Reactor with Reflector

Summary: "Expressions for the fast and thermal flux in the core of an externally driven, symmetrical infinite slab reactor with a reflector are derived as a function of the reflector thickness. The driver is represented by an inward current of fast neutrons through the outer boundary of the reflector. The flux distribution curve is plotted for several values of reflector thickness. The object is to determine the effect of changing reflector thickness on the flattening of the flux inside of the core of such a reactor."
Date: 1960
Creator: Norbeck, Edwin
System: The UNT Digital Library
Investigation of Sulfamic Acid Tank Valve Failures (open access)

Investigation of Sulfamic Acid Tank Valve Failures

This report examines the failure of two 18-8 grade stainless steel gate valves used in sulfamic acid and determines the cause of the failures through a series of tests.
Date: November 13, 1952
Creator: Endow, N.
System: The UNT Digital Library
In-Line Scintillation Gamma Monitor : Preliminary Specifications (open access)

In-Line Scintillation Gamma Monitor : Preliminary Specifications

From introduction: "The following recommendations represent the best estimate, based on present knowledge, of the requirements for generally applicable or "universal" instrument for the continuous monitoring of radioactive process streams in terms of their gamma activity."
Date: January 22, 1953
Creator: Upson, U. L. & Connally, R. E.
System: The UNT Digital Library
Corrosion of 2-S Aluminum in Potassium Tetraborate Solution (open access)

Corrosion of 2-S Aluminum in Potassium Tetraborate Solution

From summary: "A laboratory test was conducted to determine the feasibility of using an uninhibited solution of potassium tetraborate in steam condensate as a material for a pile ink facility. The evaluation was made from the standpoints of 2-5 aluminum corrosion, the rate and composition of film build-up on aluminum flow surfaces, and the change of solution composition."
Date: 1957
Creator: Miller, N. R.
System: The UNT Digital Library
Transformation and Magnetic Phenomena Occuring in Boron Stainless Steel Vertical Safety Rods (open access)

Transformation and Magnetic Phenomena Occuring in Boron Stainless Steel Vertical Safety Rods

Summary: "The low carbon 18-8 stainless steels containing approximately 1.7 per cent boron used for vertical safety rods at Hanford were found to be structurally stable in the temperature range 0-450 C. The addition of boron decreases the stability of this metastable austenitic alloy. Sufficient ferrite formation is induced by sub-zero temperature treatments to result in dimensional changes and a magnetic alloy. The difficulties encountered in machining this material are believed to be due primarily to segregation in the castings resulting in small areas of the hard intermetallic compound, FeB."
Date: February 6, 1953
Creator: Hueschen, R. E.
System: The UNT Digital Library
Neutron Diffusion and Random Walk (open access)

Neutron Diffusion and Random Walk

The following report analyzes random walks and whether or not they can be used to shed any light on problems of neutron diffusion.
Date: February 5, 1953
Creator: Duvall, G. E.
System: The UNT Digital Library
A Method for the Analysis of Radionuclide Mixture Using a Gamma-Beta Scintillation Spectrometer (open access)

A Method for the Analysis of Radionuclide Mixture Using a Gamma-Beta Scintillation Spectrometer

The following report describes a beta and gamma scintillation detector similar to what was used in previous decay studies, yet was modified to make it suitable for the analysis of mixtures of radio-nuclides.
Date: February 27, 1953
Creator: Leboeuf, M. B. & Connally, R. E.
System: The UNT Digital Library
The Analysis of TBP Process Streams for Calcium with the Flame Photometer (open access)

The Analysis of TBP Process Streams for Calcium with the Flame Photometer

Summary: A method was found for determining calcium concentrations in TBP process streams in spite of serious interferences bysodium, ferrous, uranyl, sulfate, phosphate, and sulfamate ions as well as by TBP. The precision attainable varied from sample to sample, depending upon its composition. In general, errors of 20% or greater occurred. The smallest determinable amount of calcium was about 10 mg/1.
Date: February 20, 1953
Creator: Brite, D. W.
System: The UNT Digital Library
Corrosive Effects of Heavy Metal Ions on Aluminum (open access)

Corrosive Effects of Heavy Metal Ions on Aluminum

From summary: The object of the study was to determine if the heavy metal ions within the concentration ranges normally found in pile cooling water were responsible for corrosion of aluminum.
Date: March 17, 1953
Creator: Fujioka, G. S.
System: The UNT Digital Library
Factors Affecting the Concentration of TBP Plant Wastes (open access)

Factors Affecting the Concentration of TBP Plant Wastes

Introduction: "The problem of determining the properties and necessary controls on the TBP Plant waste disposal to eliminate transport line plugging and to permit higher concentration prior to return of this to the tank farms was studied. A report of preliminary findings was made to L. W. Finsh on January 31, 1953. This report compiles information in the aforementioned report and findings since its issuance. Previous studies related to this problem are summarized in the U. R. Technical Manual, HW-19140."
Date: March 25, 1953
Creator: Shepard, D. F.
System: The UNT Digital Library
Investigation of Explosive Characteristics of Purex Solvent Decomposition Products (Red Oil) (open access)

Investigation of Explosive Characteristics of Purex Solvent Decomposition Products (Red Oil)

Abstract: "Laboratory production of an explosion between UNH and "red oil" under calcination conditions has been accomplished. Attempted production of a vapor phase explosion was unsuccessful below 150-160 C. Since such severe conditions are necessary to obtain an explosive reaction, it appears that present Purex plant design is adequate to avoid explosive conditions."
Date: March 17, 1953
Creator: Wagner, Robert M.
System: The UNT Digital Library
General Flattening and Power Curves (open access)

General Flattening and Power Curves

Introduction: "In the evaluation of pile designs it is necessary to know how the production varies with the number of tubes. It has been possible to solve the problem in terms of some general parameters whose values may be quickly computed for any specific design when the pertinent information is available."
Date: March 30, 1953
Creator: Gast, Paul F.
System: The UNT Digital Library
Corrosion Data for LaBour R-55 and Worthite in UO₃ Process Streams (open access)

Corrosion Data for LaBour R-55 and Worthite in UO₃ Process Streams

Introduction: "A corrosion test program, to determine the suitability of LaBour B-55 and Worthite for use in the construction of circulating pumps for th UO3 process has been completed and the data are appended."
Date: April 4, 1951
Creator: Sanborn, K. L.
System: The UNT Digital Library
Corrosion Tests on Stainless Steel Plate-Waste Metal Recovery Process (open access)

Corrosion Tests on Stainless Steel Plate-Waste Metal Recovery Process

Introduction: A limited test progress on Alloghany-Ludlum type 347 stainless steel plate which failed the Huey test (ASTN A-262-44T) has been completed.
Date: April 9, 1951
Creator: Sanborn, L.
System: The UNT Digital Library
Corrosion of Austenitic Stainless Steel in Mixed Acids (open access)

Corrosion of Austenitic Stainless Steel in Mixed Acids

Introduction:"A corrosion test program in support of the Redox Project was carried out during the second quarter of 1950 to determine the corrosion rates of several austenitic stainless steels in simulated 202-B Waste Storage solution containing HF, HN03, and H2SO4 acids. The results of this program are contained herein and all original data are recorded in laboratory notebook HW-3282-T."
Date: June 5, 1950
Creator: Koenig, W. W.
System: The UNT Digital Library
The Absorption and Translocation of Several Fission Elements by Russian Thistle (open access)

The Absorption and Translocation of Several Fission Elements by Russian Thistle

Abstract: An investigation was conducted to determine the absorption and translocation of fission products by Russian thistle from a localized spot of contaminated soil. The amount and identity of the radioactive elements absorbed and translocated by the Russian thistle is given along with the location of these elements in the plants. Beta radioactivity to the amounts of 10 microcuries per gram caused no visible effects on the growth habits of sectioned material are included.
Date: June 8, 1950
Creator: Selders, A. A.
System: The UNT Digital Library
Determination of Radiocesium with Chloroplatinic Acid (open access)

Determination of Radiocesium with Chloroplatinic Acid

The following report examines a rapid method used to eliminate the possibility of explosive perchlorate-organic mixtures in a control laboratory in order to determine radiocesium. These methods include the usage of chloroplatinic acid as a precipitate of radocesium.
Date: June 22, 1950
Creator: Erwing, R. E.
System: The UNT Digital Library