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Regeneration of Silver Reactors

Description: A study of the variables involved in regeneration was undertaken to determine means of improving the regeneration efficiency and increasing the useful life of a reactor. Information gained from regeneration studies on a 4-inch-diameter by 8-foot-high column indicates that the present regeneration procedure is optimum as to quantity, concentration, and rate of addition of regenerant solution. It appears feasible to restore a plugged reactor by washing off all the silver nitrate from the packing … more
Date: December 27, 1955
Creator: Amos, L. C.
Partner: UNT Libraries Government Documents Department
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Potential Nitrate Decomposition High Level Waste Storage

Description: It is recommended that self-concentration of Purex wastes should not be started until much more complete knowledge is obtained of the conditions and reactions in these wastes. The presently planned tests in the Semi-Works will be a practical demonstration of the problems but will be of little value on the initial Purex wastes as these tests are being run almost concurrent with the filling of the first Purex storage tank.
Date: April 27, 1955
Creator: Anderson, C. R.
Partner: UNT Libraries Government Documents Department
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Pile Periods and the Inhour Equation Accounting for Delayed Neutron Groups from Fission of U²³⁵ and Pu²³⁹

Description: Calculations are presented regarding the effect of delayed neutrons in reactors fueled with mixtures of Pu²³⁹ and U²³⁵. Results are plotted to illustrate the change in thermal flux as a function of time for various positive or negative step changes in reactivity.
Date: April 27, 1956
Creator: Astley, E. R.
Partner: UNT Libraries Government Documents Department
open access

Neutralization of Acidic Distillates with Limestone

Description: The following report discusses laboratory investigations of the suitability of some commercially available limestone for neutralization of slightly acidic distillates.
Date: November 27, 1950
Creator: Brandt, H. L. & Burns, R. E.
Partner: UNT Libraries Government Documents Department
open access

Corrosion of Stainless Steel, Titanium, and Tantalum in Plutonium - Nitric Acid Solutions

Description: The letter E. R. Irish/W. H. Swift to R.E. Burns and H. H. Hopkins, dated August 15, 1956, subject Plutonium Concentration Problems, requested information on corrosion of stainless steel, titanium, and tantalum in plutonium nitrate-nitric acid solution, with and without sulfate ion. Experimental conditions and results of tests designed to yield the requested information are given below.
Date: November 27, 1956
Creator: Brunstad, A.
Partner: UNT Libraries Government Documents Department
open access

An Alpha Energy Analyzer

Description: This report provides an overview of a gridded ionization chamber, instructions on how to operate the instrument, and then discusses the performance of the instrument so far.
Date: January 27, 1956
Creator: Campbell, Don A.
Partner: UNT Libraries Government Documents Department
open access

Air Sample Activity vs Flow Rate

Description: A bibliography on the subject of air sample activity vs flow rate has been prepared. The findings in two documents reviewed have been applied directly to this problem. It is concluded that air sample activity is not dependent on flow rate when sampling particles whose average diameter in 0.06 micron or greater.
Date: December 27, 1954
Creator: Clark, R. G.
Partner: UNT Libraries Government Documents Department
open access

Collection and Analysis of Active Particles

Description: Abstract: This report gives the results of a radiochemical analysis of particles collected by electrostatic precipitation from ventilation air of the "B" plant at Hanford Works.
Date: January 27, 1950
Creator: DeLong, C. W.
Partner: UNT Libraries Government Documents Department
open access

Urine Analysis for Tritium Oxide

Description: This report analyzes a procedure based on the production of acetylene from the active water, with subsequent measurement of the ionization caused by the tritium beta particle. This eliminates the troublesome absorption on the chamber walls when hydrogen is used, and provides a rapid method for the preparation of the urine samples.
Date: July 27, 1949
Creator: Healy, J. W.
Partner: UNT Libraries Government Documents Department
open access

Outgassing Tests of Uranium Slugs

Description: During the canning of slugs for Production Test 313-105-3-M, a high number of rejects were caused by gas voids in the A1-S1 bonding layer. Since the heat treatment of the slugs in a molten salt bath resulted in a chemically altered surface, an investigation was made to determine the volume of gas evolved from salt-bath heat-treated slugs as compared to other types of slugs. This test was designed as a preliminary test to determine if there were a significant differences.
Date: May 27, 1953
Creator: Johnson, H. A.
Partner: UNT Libraries Government Documents Department
open access

Canning depleted uranium : production test 313-110-M, final report

Description: From summary: "Uranium billets deficient in U235 were subjected to the normal successive steps in the slug fabrication process; viz., rolling, machining, and canning. No unusual behavior was observed at any point in the process, thus indicating that the depleted metal from the standpoint of mechanical properties can be considered equivalent to normal uranium."
Date: March 27, 1951
Creator: Jones, T. S.
Partner: UNT Libraries Government Documents Department
open access

Analysis of vegetation for I¹³¹

Description: Report detailing an analysis of the deposition of I-131 on vegetation. Analysis was necessary to determine the potential hazards of the gases from the dissolution of the metal on vegetation.
Date: January 27, 1950
Creator: Leboeuf, M. B.
Partner: UNT Libraries Government Documents Department
open access

Analysis of Broadened X-ray Diffraction Peaks

Description: This report is a manual describing the methods developed by Stokes (1) and Warren and Averbach (2) (3) for the determination of the effects of cold work by x-ray diffraction methods. Only the method of mathematical analysis is presented while the method of obtaining the necessary x-ray diffraction patterns is not mentioned. This manual will be used for an experimental study of irradiation damage to uranium.
Date: July 27, 1955
Creator: Merckx, K. R.
Partner: UNT Libraries Government Documents Department
open access

The Suppression of Chlorine Volatilization in Nitric Acid Distillation

Description: Description of Invention: Chloride-induced corrosion is a serious problem in the Purex acid recovery operation and in the evaporative concentration of process streams and waste solutions. In the case of Purex acid recovery, it has been shown that trace chloride will volatilize with the nitric acid and reflux in the acid fractionator, thus causing especially severe corrosion at that point. These traces of chloride may enter the process form several sources, i.e., as an impurity in the technical … more
Date: July 27, 1956
Creator: Moore, R. L.
Partner: UNT Libraries Government Documents Department
open access

Crystallite Sizes of PuO_2 Powders

Description: In connection with studies of the chemical reactivity of PuO_2 to hydrofluorination, samples were examined by X-ray diffraction for crystallite size and perfection. The PuO_2 was formed by thermal decomposition of the oralate. The reactivity of this oxide, as well as that of other solid oxides is affected by the conditions of preparation. Besides the obvious influence of surface, including lattice strain and other structural irregularities in the particles. Each particle is composed of a number… more
Date: July 27, 1956
Creator: Pallmer, P. G.
Partner: UNT Libraries Government Documents Department
open access

Carbon Steel Program for High Temperature Reactor Systems

Description: The Reactor Design and Development Unit has just completed a design concept for an intermediate capacity dual purpose reactor plant utilizing carbon steel for the primary loop portion outside the reactor. This design concept is reported in HW-33157 AD (2). The economic and engineering gains are of sufficient magnitude to justify an accelerated and extensive test program to completely evaluate the remaining unknowns in utilizing carbon steel as a stainless steel substitute. It is the purpose of … more
Date: April 27, 1955
Creator: Pearl, W. L.
Partner: UNT Libraries Government Documents Department
open access

Observations on a Zircaloy-Uranium-Aluminum System at High Temperatures

Description: A brief series of experiments was performed to study the high temperature reaction of the Zircaloy-uranium-aluminum system at the request of Reactor Engineering Operation, Irradiation Processing Department. Knowledge of the high temperature behavior of this combination of materials is important to the evaluation of reactor behavior during possible accidental over-heating of a fuel channel.
Date: May 27, 1960
Creator: Scott, A. J.
Partner: UNT Libraries Government Documents Department
open access

Heat Transfer Study for Self-Boiling Radioactive Wastes

Description: The temperature characteristics associated with the handling of self-boiling radioactive wastes from the separations extraction processes in the Chemical Processing Department have necessitated several heat transfer studies. Earlier studies 1,2,3 defined the feasibility of self-concentration in existing waste storage facilities by determining the rate of heat generation from the decay of stored fission products and by defining the rate of heat loss from existing storage tanks to the surrounding… more
Date: April 27, 1959
Creator: Stivers, H.W. & Taylor, H.W.
Partner: UNT Libraries Government Documents Department
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The Separation of Trace Amounts of Radioactive Cs From Macro Quanitites of Sodium and Potassium Salts

Description: Summary: A method for the separation of cesium from macro quantities of sodium and potassium using an ion exchange resin, Dowex 50, has been developed. A 95% recovery of cesium with a reduction of the solid content of 95% was found possible. Curves illustrating the effect of acidity, column length, and flow rate are presented in the report. The sodium form, hydrogen form and ammonium form of Dowex 50 were investigated; the hydrogen form was found to give the best separation.
Date: January 27, 1950
Creator: Thorburn, R. C.
Partner: UNT Libraries Government Documents Department
open access

An Ultrasonic Method for Bond Testing Reactor Fuel Elements

Description: Ultrasonic testing has been investigated as a possible non-destructive method for checking the bond integrity of certain type fuel elements. Equipment has been developed to inspect experimental fuel elements for various research programs. Circuits have been devised to discriminate the size of defects and to map the areas which are unbonded.
Date: November 27, 1956
Creator: Worlton, D. C.
Partner: UNT Libraries Government Documents Department
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