Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."

Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."

"The St. Louis Refinery produced its first UO3 and UO2 in 1942, and its first UF4 and U metal in 1943. The accent has always been on production, and the function of the extremely small research and development groups has been to aid the production units in their job. ... Recently, there has been a growing realization of the need for a broader and more detailed knowledge of both the chemical and technological aspects of all phases of work. ... This is the first of a series of quarterly progress reports on the research and development activities at the St. Louis Refinery."--p. 6

This quarterly progress report details ongoing work at the Oak Ridge National Laboratory as part of the Aircraft Nuclear Propulsion Project. Topics of discussion include reactor theory and design, shielding research, materials research, appendixes with information on ongoing analytical chemical studies.

From abstract: "A continuous countercurrent solid-liquid contactor has been developed which retains the desirable features of the conventional fixed bed and gains the advantages of countercurrent flow. It can be adapted to many solid-liquid mass-transfer processes such as ion exchange, silica gel adsorption, and ore leaching."

From abstract: "The extraction of acids with long-chain amines is described. Preliminary results on the extraction of the amine salts of polonium, plutonium and uranium are given."

From abstract: "Two samples, each containing an estimated 10 curies (2 mg) of polonium-210, were purified by vacuum distillation and evaporated onto oblique sections of X-ray targets made of copper. Four lines of the K series and ten lines of the L series of the X-ray spectrum of polonium were recorded with a one-meter transmission crystal spectrograph and a 25-centimeter Bragg spectrograph, respectively. Measured wavelengths agree approximately with values predicted by extrapolation of Moseley's law and with those claimed by Hulubei. Decay of polonium-210 (half life = 138 days) and growth of lead-206 (stable) were observed over a period of 180 days."

From abstract: "The variation of the reactivity of a pile as a function of width of a transverse gap is obtained. The method involves first finding the boundary condition satisfied by the flux at the gap face. This, in principle, provides enough information for a complete solution of the pile equations. A method for calculating the reactivity change is presented. The calculated reactivity is compared with experiment and a brief discussion of the validity of the approximations is given."

From summary: "The hazards due to possible chemical explosion and detonation of the dissociation gases in homogeneous-reactor systems have been considered."

From introduction: "The ORNL-ANP liquid-to-liquid heat exchanger design and development effort has been based on an exceptionally high performance matrix of closely-spaced small diameter tubes that permits practically pure counter-flow operation. In the course of full-scale aircraft power plant design work a number of charts for this type of heat exchanger has been prepared. These charts were intended in part to show the effects of the various parameters in a readily understandable form, and in part to simplify and to reduce markedly the chore of making detailed design calculations. These charts have proved so helpful it seemed very worthwhile to assemble them into a report along with brief explanations and sample calculations."

"This symposium is concerned with the basic aspects of radiation effects. When we turn to the genetic effects of radiation in mammals, there are so few aspects on which there is any information that the problem of sorting out the fundamental findings has hardly arisen. In this paper it will, therefore, be possible to survey most of what is known and pass on to a consideration of what is needed next. Since one of the purposes of this symposium is an interchange of views between investigators in different fields, an attempt will be made to avoid technical details. Among the practical needs in mammalian radiation genetics is a pressing one for more data on which to base estimates of the genetic hazards of radiation in man. The present paper will be concerned largely with this problem. Our own work is directed primarily in this direction, our objective being to uncover some of the basic facts in at least one mammal-the mouse. Before discussing the experimental work, however, it seems desirable to consider some of the general features of the genetic hazard of radiation."

From summary: "The influence of the structure of phosphate esters on the distribution coefficient of uranium between solutions of these esters in carbon tetrachloride and aqueous nitrate solutions has been studied. Esters of secondary alcohols showed higher distribution coefficients than primary alcohols. Phenyl esters extracted less uranium than alkyl esters, and the presence of other negative groups also resulted in less extraction. Compounds containing carbon to phosphorus bonds gave higher distribution coefficients than the corresponding esters, and the distribution coefficients increased with the number of such carbon to phosphorus bonds. Tributyl phosphine oxide (with three carbon to phosphorus bonds) showed high distribution coefficients with many salts, including uranyl nitrate, uranyl sulfate, uranyl chloride, thorium nitrate, plutonium (IV) nitrate and some of the fission products in nitrate solution. It is planned to study these and similar compounds further."

From abstract: "Relocation of the ion source in the 86-inch cyclotron has increased the available beam energy substantially. Modifications have also been made to permit the use of targets of 100 square inches. Proton currents of one milliampere can now be obtained readily at ~24 Mev. The 63-inch cyclotron has been completely assembled and checked. In rf tests a 75 kv dee-to-dee voltage has been maintained, under vacuum, for long periods without evidences of failures, thus exceeding the 60 kv design specification. In an investigation of proton beam distribution on the 22-inch cyclotron it has been shown that almost all of the loss of protons form the beam occurs within one-half of the maximum radius. The ration of H3+ to H1+ ions in the beam increases at lower at lower arc intensities in the ion source. Accelerated corrosion was found in an Inconel tube containing #14 eutectic (ARE) after a six-hour bombardment with 20 Mev protons at 4,500 watts/cc. Installation of facilities for the preparation of plutonium isotopes is nearing completion; preliminary tests are being made."

From abstract: "On the 86-inch cyclotron a 41-kw beam has been calorimetered at a net ion loading efficiency of 40%; the average proton current was 1.85 ma at 22.5 Mev. Practical specific yields have been determined for (p,2n) reactions on zinc and bismuth. The investigation of products of proton-induced fission of uranium has been continued and new techniques are being used in measuring angular distribution of reaction products. The 63-inch heavy particle cyclotron is now in operation; N+++ particles have been accelerated to ~25 Mev. In preliminary tests, induced activities have been detected in carbon, nitrogen, and oxygen targets. A hot-cathode ion source is ready for test operation. The 22-inch cyclotron is being used in an investigation of the problems associated with the use of rf and dc electrodes for the acceleration of protons from the ion source into the dees. Radiation-induced corrosion in Inconel tubing containing #21 eutectic (ANP) has been produced by proton irradiation in the 86-inch cylclotron; it is shown that the corrosion was not due to thermal effects. Approximately 150 grams of highly purified U 238 (< 5 ppm U 235) have been prepared, and two grams of thorium 230 (ionium) has been enriched to 90.6%."

This quarterly progress details the ongoing work of the Protective Equipment Evaluation Program at the Oak Ridge National Laboratory. Topics discussed include aerosol generation, penetration studies, particle size measurement, and an appendix with analytical methods.

This progress report discusses the work during the fourth quarter of 1951. During this quarter, "the uranium raw materials program at ORNL has been devoted to studies of uranium chemistry and to the development of processes for deriving uranium and byproducts from various types of ores" (From introduction).

From abstract: "This report presents the progress in the laboratory development of a continuous solvent recovery process for the tributyl phosphate-diluent mixture used in the Purex Process. Investigations were made with 1/2" diameter pulse columns, using a nine foot sodium carbonate contacting column and a four foot water wash column."

From introduction: "During the second quarter of fiscal year 1952, the Isotope Production and Process Development Department placed primary emphasis on the collection of lithium, iron and calcium isotopes."

From abstract: "This report describes the decontamination of Oak Ridge National Laboratory Purex Pilot Plant facilities and presents an appraisal of the decontaminating techniques and reagents which were employed."

From abstract: "The following report presents a summary of operating experience with decelerating receivers for ion beam reception. Sample calculations for design of such a receiver for the isotopes of lithium are presented. Estimates of maximum production and requirements to attain such production are given. The maximum ion beam envisioned is 17 amperes obtained from extrapolation of experimental results."

Technical report presenting preliminary results obtained in the static corrosion test program to screen promising construction materials for a proposed liquid fuel power breeder reactor.

Technical report describing the downtime of the Brookhaven National Laboratory nuclear reactor and changes made to the reactor facility in March 1952.

From summary: "During 1951 NDA has, at the request of ORNL, been studying the supercritical-water reactor as proposed for aircraft propulsion in Wash-24...This study has concerned itself only with the reactor and shield." The report describes the reactor and the processes involved in developing it. The goal of the development of this reactor is identified as a path to supersonic flight.

From abstract: "Data obtained in laboratory studies of the 'fumelses dissolving' of irradiated uranium are presented. Procedures for handling dissolver off-gases are proposed."