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.

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.

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.

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.

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.

Report that communicates a new permissible activity level of plutonium and uranium.

The following report discusses laboratory investigations of the suitability of some commercially available limestone for neutralization of slightly acidic distillates.

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."

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.

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 grade chemicals used in making up the various aqueous process streams, by hydrolysis or radiation decomposition of carbon tetrachloride (a promising diluent for tributyl phosphate), or by incomplete removal of the hydrochloric acid employed in some flowsheets for effecting the dissolution of certain difficulty soluble nuclear reactor fuel elements.

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 of crystallites. The extent of crystallites size and perfection will be indicated by the width of a diffracted X-ray beam. Since separation of these two caus4es would require a detailed analysis, the observed broadening was interpreted on the assumption of crystallite size effects alone. However, the variable factor in preparation method was temperature, and it is to be expected that crystallite growth with annealing will occur in part at the expense of energy stored in nonequilibrium states of the crystal, i.e., imperfections. The objectives of this study were to establish a convenient method for determination of PuO_2 crystallite size and to obtain estimates of the crystallite sizes of seven given samples.

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 and recoating by a normal regeneration cycle. Such a procedure could be utilized only if there is sufficient dead space in the bottom of the reactor to hold the wash solution.

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.

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.

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.

Quarterly progress report on metallurgy research operations at Hanford Atomic Products Operation in Richland, Washington.

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 soil.

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.

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 this document to up-date and elaborate the information contained in the two previous documents (1). . It is the further purpose to define the program required to implement the design concept developed by the Reactor Design and Development Unit (2) utilizing carbon steel as the primary loop structural material.

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.

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.

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.

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.