Abstract: A method for separating small amounts of scandium (1 to 10 mg.) from a gram of uranium depends upon formation of insoluble uranium peroxide while the scandium in solution is complexed with ethylenediamine-tetraacetic acid. The precipitated peroxide carries down less than 30 p.p.m. of scandium. Uranium left in solution, less than one milligram in amount, does not interfere when the scandium is precipitated as ammonium scandium tartrate and determined gravimetrically by ignition of the tartrate to the oxide.

Report discussing a proposed electron probe that is connected to the discharge current from a device called the Perhapsatron. "The Perhapsatron is an apparatus for the study of the type of magnetic containment known as the 'pinch effect.'"

Abstract: "A method for determining hydrogen in lithium hydride by heating samples with lead at 600 C, was developed. The hydrogen evolved during thermal decomposition of the hydride is purified and oxidized to water with cupric oxide at 400 C. The analysis is completed by collecting and weighing this water. Success in development of the analytical procedure has depended upon a careful design and assembly of equipment for handling samples in a dry, inert atmosphere. For seven pure hydride samples analyzed by the recommended method the estimates of the standard deviation varied between 0.12 and 0.41 percent lithium hydride (or 1.3 and 4.2 parts per thousand) for 8 to 18 determinations on each sample. The procedure is relatively insensitive to variations in certain conditions. For single-piece samples weighing 0.2 to 0.5 gram it was found to be more satisfactory than a method which uses mercury in place of lead for sample decomposition. For powdered lithium hydride samples the lead and mercury methods are equally satisfactory."

The Uranium Recovery Process (TBP Process) at Hanford extracts and decontaminates uranium from the Metal Waste produced in the Bismuth Phosphate Process. Aqueous waste, approximately equal in volume to that of the Metal Waste itself, results from the process. Although of several years' age, these wastes are still sufficiently radioactive that they must be returned to underground tanks for storage. For several years aqueous wastes of low radioactive content have been discharged to ground at Hanford. Polyvalent cations are strongly absorbed by the soil. Monovalent cations are poorly absorbed if present in solutions of high salt content. Ground waters migrate toward the Columbia River very slowly. These observations point out the desirability of removing, from wastes to be cribbed, those long-lived radioactive constituents which are poorly absorbed by soil. Cesium (Cs-137) and strontium (Sr-90) are the principal constituents of Hanford wastes which possess these characteristics. Strontium, while more hazardous biologically, is of somewhat less concern than cesium because it is better absorbed from high-salt solutions by soils. This report describes research done to develop on inexpensive process for the removal of fission products, especially cesium, from Uranium Recovery Process Wastes. 4 refs., 13 tabs.

From abstract: The purpose of this preliminary electrical resistivity investigation of Holiday Mesa, Monument Valley region, San Juan County, Utah, was to determine the feasibility of a detailed survey to delineate channels cut into the Moenkopi formation and filled with sediments of Shinarump conglomerate. These structures are in many places related to the localization of uranium ore.

The following report follows the studies of electroplating on uranium and concurrent metallurgical clodding.

From abstract: "A method for fabricating 30-in.-long stainless steel - uranium dioxide sheet was developed and the properties of the fabricated sheet were investigated."

In accordance with the policy that a centralized inventory shall be kept of all radioactive waste liquid discharged to ground, it is recommended that the volumes of condensate from the SX-farm, the dates or periods of discharge, and the activity densities of radioisotopes in the condensate discharged be determined by Separations Section and reported regularly to the Radiological Standards Unit. This paper is a description of the condensate system, with recommendations for sampling and analysis.

A common and useful assumption is that the front-to-rear power distribution is a shortened cosine curve. This fact led to the calculation of slug factors'' for the longer charges to be used at K-Pile. It is hoped that the publication of these numbers will save time and prevent duplication of effort by those concerned in any way with slug power, surface temperatures, reactivity effects, etc. For the sake of completeness, slug factors for the older piles are included. Another useful ideal is that tube power distributions can be approximated by the assumption of a cylindrical pile and a cosine distribution of power outside of a central flattened region. This led to another double set of numbers since the values for the 2004 tube piles were again included for completeness. 2 figs., 6 tabs.

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Abstract: A visualized electron beam has been reflected by a conventional magnetic mirror. Visualization of the beam path from the electron gun to and including the region of reflection was achieved by the "thread ray" technique of Wehnelt. The total current passing through a magnetic mirror has been measured as a function of the beam energy and angular momentum for H₂ over a range of pressures from 0.5 to 5 microns.

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."

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Free-flight drop vehicle tests have been made to investigate devices for measuring ambient pressure in the vicinity of a high-fineness-ratio weapon shape throughout the transonic speed range. Various types of nose probes and trailing probes were tested.

Abstract: Reconnaissance mapping in the Ruby Quadrangle, Arizona, indicates the existence of a complex assemblage of volcanic rocks and associated sediments, divisible into a younger and older series.

This is a progress report of the production reactors on the Hanford Reservation for the month of April 1954. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

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"A series of thermal neutron diffusion length measurements has been made on non-multiplying lattice of lead-cadmium alloy rods in D2O. One-inch diameter rods in square lattice spacing of 4, 9, 6, 9, and 12 inches were used. Excellent agreement was found between theoretical and experimental values of the diffusion length. The analysis o the diffusion length measurement required a correction for the epithermal neutrons entering the exponential tank. These epithermal neutrons provided a distributed source of thermal neutrons upon slowing down in the lattice."

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Herman Lurie's weekly report for the sugar market. Details include prices, distribution, sugar tons, and refiners.

Herman Lurie's weekly report for the sugar market. Details include prices, distribution, sugar tons, and refiners.

Results of preliminary tests with photographic emulsions using a lip target are discussed. Some methods for the search of heavy mesons are suggested. The preliminary tests with photographic emulsions were designed to investigate exposure conditions inside the Bevatron. These were carried out with stationary targets, since injected targets were not available at that time. The first exposure was designed to study the shielding required for emulsions placed in the direct beam (9 inches from the magnet conterline) during the entire acceleration cycle. Three 200{micro} Ilford G5 emulsions embedded in various thicknesses of brass were exposed for 30 pulses. Nominal maximum energy of beam was 3.5 Bev. During the second and third exposure (nominal maximum beam energies 4.1 and 6 Bev respectively) a lip target was placed in front of the emulsions. This was designed so as to dampen out the radial oscillations in the first section (.36 inches thick, 1/2 inch radial length). The beam should then hit the second section (.9 inches thick, .75 inch radial length) which is designed to reduce the beam orbit by {approx} 1 1/4 inches and then hit the emulsions on the next turn. 1/2 inch brass absorber was placed ahead of the emulsions.

A preliminary evaluation of the hazards associated with a 20-Mw boiling reactor for the purpose of determining site requirements is presented. The Boiling Experimental Reactor design, safety features, and performance are given and the surroundings of the site at Argonne National Laboratory are described. (T.R.H.)