Certain oralloy (Oy) lattices were immersed in infinite water for determining critical masses at various low-Oy densities. Three Oy unit sizes were used. In a broad sense the experiment shows safe and unsafe conditions for handling heterogeneous Oy-water mixtures.

Report issued by the Bureau of Mines over operations of an oil-shale pilot plant. As stated in the summary, "this report describes the step-by-step development of the Gas-Combustion retort and the various modifications and means of air admission used to obtain a workable unit" (p. 2). This report includes tables, graphs, and illustrations.

The installations of the beam deflector in the ORL 86-inch Cyclotron is sufficiently complete to allow initial testing the system permits the optional use of high-current internal targets. A survey of [illegible] cross sections made with 14-Mev neutrons indicates qualitative agreement with statistical theory. An internal-conversion ion spectrograph and a fission-fragment spectrograph were built and put in operation. The [illegible] functions severed proton-induced reactions of possible use in isotope production were measured. A capsule-type target is being used for the irradiation of chemical compounds. Nuclear physics research with 26-Mev nitrogen lens from the ORNL 63-inch Cyclotron concerned the following: a theoretical interpretation of elastic nitrogen-nitrogen scattering a detailed investigation of some nitrogen-nitrogen nuclear reactions; the measurement of reactions across sections in boron and aluminum; and the identification and the energy spectre of protons and alpha particles resulting from nitrogen-induced reactions with light elements. A study is being made of the practicality of a fixed-frequency cyclotron to accelerate protons to about 1 [illegible] for application in [illegible] research. Phase compensation would be obtained with an unusual magnetic-field configuration which has eight [illegible] cycles with about 72 deg of spiral, Also, a proposal was made to convert the 44-in. proton cyclotron a …

Report discussing the investigation of the chemical composition of sandstone-type uranium ores and unmineralized sandstones of the Colorado Plateau. Spectrographic and chemical analyses was used.

Abstract: "Static measurements have been made of the currents produced by Co-60 gamma irradiation of solid dielectric RG 8/U cable. Sensitivity curves are presented as a function of the magnitude and polarity of the collection voltage to 90 volts. It is shown that the current is due to a polarity- and voltage-sensitive ionization component and to a polarity- and voltage-insensitive component attributed to the Compton process. The total cable sensitivity at -90 volts, with saturation not achieved, was (11 +/- 1) x 10-(-12) coulomb per roentgen-meter of cable, or 0.08 percent of what one would expect from ionization in an air dielectric cable of this volume."

The primary purpose of these researches was to clarify the various functions of organic substrates in bacterial photosynthesis. The following aspects were investigated; (1) metabolic pathways under photosynthetic and oxidative conditions, (2) energy transfers occurring during the metabolism in cell free extracts, and (3) the relationship between photosynthetic rate and light intensity for selected organic substrates. The results of these investigations were summarized in a paper entitled "The Application of Carbon-14 to Studies on Bacterial Photosynthesis" which was submitted to the United Nations as a contribution to the International Conference on the peaceful Uses of Atomic Energy, Geneva, Switzerland, August 8-10, 1955. A reproduction of this paper constitutes a major portion of this report.

Report issued by the Bureau of Mines over studies conducted on the copper-nickel deposits of Lake County, Minnesota. As stated in the introduction, "this report describes the procedures and results of the drilling program as well as the metallurgical work and laboratory studies" (p. 1). This report includes tables, maps, and illustrations.

From abstract: "Sediments of the inner part of the southern Atlantic Coastal Plain have been sampled and examined for monazite." The report provides sections on general geology, field and laboratory methods, distribution of monazite, and other mineral products.

A report regarding monazite in part of the southern Atlantic Coastal Plain. This report concerns work done on behalf of the Division of Raw Materials of the U.S. Atomic Energy Commission.

This technical report describes a simple way to calculate numerical values of K and l shell photoelectric absorption coefficients (averaged over subshells) for highly ionized atoms.

Abstract: Concentration of secondary uranium minerals, some of which are commercially significant, have been found in three formations of Tertiary age in the Gulf Coastal Plain area of southern Texas: the Fayette sandstone of the Jackson formation, the Catahoula tuff, and the Oakville sandstone.

A report about uranium alloys, fuel element development,, zirconium-uranium alloys, zirconium erosion, and the development of reactor materials.

This report presents a study investigating the possibility of designing a somewhat advanced power reactor using existing and proven technology insofar as possible. It covers a preliminary analysis of a 500 mw reactor.

From abstract: A refraction seismic survey was made on Holiday Mesa, San Juan County, Utah, between May 21 and June 11, 1954, prior to an exploratory drilling program made by the U.S. Atomic Energy Commission to delineate channel trends in the area.

The water plant for a high temperature reactor must be capable of providing several purities of water to the various components of the installation. The actual treatment methods will depend on the location and size of the reactor, the size and sources of the water and the ease of disposal of radioactive wastes. This document examines the needs for the various water purities. It also defines the area of future work to provide the information necessary for the design of water plants for high temperature reactors or for the conversion of existing reactors to recirculation cooling.

The following document describes suggestions on the application of the A-48 ion accelerator beam currents to the Sherwood Program.

In the reference document, a statistical method for analyzing run to rupture tests involving two metal types, a test material and a control standard, is presented. It often happens that more than two metal types are involved in a production test. In this document, the statistical procedure recommended for this situation is presented.

Two methods were developed for the determination of uranium metal in UF3 with other fluoride compounds. A simplified method of determination which has a relatively high degree of precision (coefficient of variation 2 per cent) is carried out by decomposing the hydride in an atmosphere of carbon dioxide and subsequently measuring the hydrogen over an aqueous solution of potassium hydroxide. The ignition of the hydride in an atmosphere of oxygen and volumetric measurement of the water at reduced pressures provide a more sensitive method of determination. The coefficient of variation of the latter procedure is 7 per cent. The yield of gas from the reaction of the hydride with ammonia and gaseous hydrogen chloride was found to be neither stoichiometric nor reproducible.

From foreword: The objective of this study is to determine the practical and economic use of nuclear for the production of electric power in the Pittsburgh district.

From July 7 to August 31, 1955, 20 tons of uranium and 1,200 g of plutonium were recovered in 47 days of plant operation at an average rate of 833 lb/day of uranium and at a cost of $2.60/lb of uranium. Uranium and plutonium recoveries were, respectively, 99.9 and 95.5 per cent.

LITR Fluoride-Fuel Loop. — The inconel loop was dismantled for removal of the samples and for recovery of the uranium by using the remote cutting tools installed in a half cell of the Solid State Building. Disassembly proceeded without incident. An electric-arc cutting technique was developed for removal of the stainless steel enclosure around the pump bowl. Fission power and maximum flux were determined by irradiating a simulated loop, by heat-balance calculations, by radiochemical analyses for fission products in the fuel, by measuring the activation of cobalt foils attached to the loop, and by activation of the loop tubing itself. The determination of the power by these various methods gave 2.5 to 2.8 kw during operation of the loop, and the maximum power density was 0.4 kw/cc. Chemical analyses of the fuel were carried out to determine U, Zr, and the major constituents of inconel: Ni, Cr, and Fe.

The penetration rates of thorium metal by boiling nitric acid were measured as a function of the concentration of fluoride catalyst and of nitric acid. Dissolved thorium and aluminum were found to inhibit the reaction. Thoris exhibited penetration rates much lower than those of thorium metal. In addition to the specific rate measurements, pot type batch dissolvings were carried out to estimate plant time cycles. An empirical mathematical equation was devised which correlates the results of these batch dissolvings and facilitates application of the data to other types of dissolvers.

The possible hazards from the refining and processing of thorium are of wide interest in atomic energy work. A review of the data available was made at Hanford in the last year to support consultations on the hazards of radioisotopes with other plants which may handle thorium. Since a major discrepancy between the published values of air MPC's and the metabolic data was noted, a review of the calculations on thorium was made in order to obtain the best estimates available. This document tabulates the pertinent data and applies them to the calculation of the MPC of thorium.

A direct titrimetric method for the determination of trivalent uranium in uranium trifluoride and mixtures of fused fluoride salts was developed. The method is based on the stoichiometric oxidation of trivalent uranium to the tetravalent oxidation state with an acidic solution of methylene blue. The sample containing trivalent uranium is dissolved at room temperature in an excess of standard methylene blue solution in a carbon dioxide atmosphere; the excess oxidant is variation of the method is 1.5 per cent for 5 mg quantities of trivalent uranium. The method was applied to various mixtures of fluoride salts containing both trivalent and tetravalent uranium.