This report describes progress in testing nonaqueous methods for extracting uranium and vanadium from Western ores. Acetone leaches were found to be effective.

From abstract: "This report summarizes the past year of study of fine, molded, multicrystalline graphites with particular reference to the interrelation among certain properties with the composition, fabricating techniques, and thermal treatments found to influence them."

Quarterly report describing progress on a project to develop and evaluate high-temperature tungsten alloys. This report discusses initial experiments to compare different alloy combinations.

Report discussing part of a study that aims to understand plasma stability and confinement in mirror geometries.

"Engineering was continued on the development of sodium cooled, graphite moderated type reactors. General studies were carried out as well as studies specifically devoted to the following: a. full scale poser-only plant, b. thirty-mega watt pilot plant, the SGR, c. sodium reactor experiment, the SRE. This work consisted of theoretical analysis of various aspects of nuclear performance; economic investigations of different fuel element, cooling system and plant arrangements; and experimental investigations related to the properties of certain materials and to the development of components. Preliminary consideration was given to alternative reactor arrangements employing liquid hydrocarbon moderators and high temperature coolants other than sodium. In addition to a summary of the general design features of the SRD, a program was prepared outlining the proposed use of this installation.

Abstract: Solid ferric chloride reacts with solid uranium tetrachloride to form a complex iron-uranium chloride compound at approximately 263°C. The vapor pressure of this compound is nearer to that of uranium tetrachloride than to the vapor pressure of ferric chloride.

Abstract: "The Calutron has been successfully employed to separate the stable isotopes of twenty-one elements. The standard Beta M-2 unit modified to handle charge materials of various temperature ranges has proven adequate for a majority of separations. The problem of K life has received considerable attention but is still to be solved. Other operational problems are similar in most respects to those of uranium. The E design has, of necessity, varied greatly from the "Beta Gloria" type. A desire to keep construction simple, yet adequate for efficient collection and readily adaptable for use with many elements, has dictated the trend in E design. Water cooling on the receiver pockets was necessary with many of the elements separated. The chemical purification of the separated samples, although following a general pattern, varies with the type of pockets used and the element collected."

High speed data handling and computing systems are coming into increasing use in the automatic control of complex industrial processes. One of the next significant developments in reactor design is believed to be the application of high speed data handling and control systems to nuclear reactors. This document is a study of such a system intended for use with the Plutonium Recycle Test Reactor.

This article presents data on the effects of gamma radiation on the physical properties of a number of different classes of plastics materials of construction which were screened to determine their capabilities and limitations for service in applications where ionizing radiation exists. The irradiations were carried out in air at ambient temperature at normal atmospheric pressure to various gamma radiation doses up to 1*10^9 r depending upon the stability of the materials to radiation exposure. The different classes of materials and materials within a class are compared.

The design of NPR shows large quantities of carbon steel pipe and fittings in the front and rear face areas. These are also the area where the most work must be done during an outage, and consequently lower radiation levels are needed here than elsewhere in the piping system. A single pass decontamination of the front and rear piping without going through the entire loop is desirable. Because of the quantities of chemicals and available down time, an effective shorty interval process is needed. This report gives some recent laboratory data on this subject.

Abstract. A summary of the effect of metal, carbon, silicon, and oxygen impurities upon the various sulfide refractories is given and the proper procedures for elimination of the impurities are discussed. CeS which is properly prepared can be handled in air without danger of catching fire or appreciable oxidation. 650 satisfactory crucibles have been made to date using sulfides which were screened and pressed in air with less than 0.5% oxygen pickup. The other cerium and thorium sulfides are even more inert to oxidation than is CeS. Phase diagram possibilities are discussed for the cerium and thorium sulfide and oxy-sulfide systems. Further study of the ThS has shown that ThS crucibles are the highest melting and least volatile of the sulfide crucibles and ThS may be used for remelting of some metals up to 2000 degrees C. ThS crucibles appear to be the most suitable containers for metal reductions.

Abstract. Some recent analysis of certain Lid Tank fast neutron dose rates measured in oil and water indicates that there are some basic inconsistencies with reported oxygen and carbon removal cross sections and the reported data. These inconsistencies may be explained in several ways: (1) The reported carbon removal cross section is wrong. (2) The reported oil composition is wrong. (3) The reported oxygen removal cross section is wrong since it is based on an assumed rather than a measured oil composition. (4) Some of the experimental data are wrong. It is not possible to determine which of the above is most likely on the basis of analysis alone but the possibilities are pointed out and, based on the assumption that all the experimental data are correct, it appears most likely that the oil composition assumed in ORNL 2197 was in error.

The angular distribution of charged pions from 100 = 30 Mev neutron bombardment of C12 and Be9 has been measured. These data may be used to infer, by subtraction, the identity, within limits, of the [formula] and [formula] angular distributions.

A fuel element assembly in which a uranium slug is bonded to an impact extruded aluminum can by means of aluminum-silicon eutectic, and in which the can is capped with a thin aluminum disc, brazed and welded to the can, may contain,(a) imperfections common to brazed and welded metal sections, and (b) inhomogeneities arising from oxidation of uranium, and alloy formation between uranium, aluminum and silicon.