From introduction: "This report covers work performed in the Solid State Division for the quarter ending May 10, 1952." Topics covered include radiation metallurgy, engineering properties, solid state reactions, crystal physics, and special projects.

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."

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 ongoing research at the Oak Ridge National Laboratory as a part of the Aircraft Nuclear Propulsion Project. Topics discussed include reactor theory and design, [part two is not included], materials research, and appendixes with information on analytical chemical studies.

This quarterly progress report discusses in detail the work done by the Analytical Chemistry Division at Oak Ridge National Laboratory. In particular, this report discusses the research and development work ongoing at the X-10 Site and the Y-12 Site.

This quarterly progress report discusses ongoing work at the Metallurgy Division at the Oak Ridge National Laboratory. Topics discussed include thorium research, the preferred orientation of uranium, studies in the ceramics laboratory, the homogenous reactor program, studies in the x-ray laboratory, studies in the metallographic laboratory, the experimental plate-cladding program, and fuel and control element fabrication.

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."

Report documenting the ongoing research and developments of the Oak Ridge National Laboratory's Homogeneous Reactor Project.

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

This quarterly progress report describes the ongoing research at the Metallurgy Division at the Oak Ridge National Laboratory. In particular, this report discusses the thorium research program, the slug problem, the preferred orientation and anisotropy in metals, fundamental studies of alloying, and the ANP program.

From abstract: "This report presents the laboratory development of the MTR-RaLa Process for the production of barium140 from Materials Testing Reactor assemblies." The laboratory studied four possible chemical schemes with the final process being chosen "on the basis of chemical yield and purity of product, ease of recovery of uranium235, simplicty of equipment, and overall time required for processing" (from introduction).

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."

Report issued by the Oak Ridge National Laboratory discussing the production separation for the radioisotope program. As stated in the abstract, "a general description is given of five years' experience in routine production of fission products of high concentration and high activity levels for the radioisotope program. Details of construction and production processes are given for two systems which were built on ion-exchange principle" (p. 2). This report includes illustrations, and photographs.

From introduction: "The tube arrangement covered in this report was proposed in June, 1950, as a means of halving the weight and volume required for the heat exchanger. Ideally, the pressure drop across this arrangement should be little more than that required to overcome the skin friction on the tube surfaces. If the pressure drop across the tube spacers and in the cross-flow regions can be kept low, this ideal can be approached. much of the test work covered in this report was devoted to this phase of the problem."

"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."

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 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.

Report discussing the progress of various research projects by members of the Mathematics Panel at Oak Ridge National Laboratory for the quarter ending April 30, 1952.

Technical report calculating "effective removal cross sections" for Pb, Fe and O from measurements of fast neutron does in the water surrounding the BSF reactor. The values for Pb and Fe agree quite well with those previously determined from Lid tank data, whereas that for O is somewhat lower. [From Abstract]

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: "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."

This quarterly progress report details the ongoing research happening at the Oak Ridge National Laboratory. In particular, this report discusses the current status of the Homogenous Reactor Experiment, boiling reactor and slurry studies, and general homogenous reactor studies.

From abstract: "The methods of applying results of bulk-shielding measurements to the design of reactor shields is outlined. Geometrical transformations for the more common shapes are derived, as are approximate means of calculating leakage of radiation. As an illustration of the methods, the ORNL Lid Tanks and Bulk Shielding Facility data are transformed to a standard geometry and compared. Two direct calculations of water attenuation, using cross sections described in the previous article, are finally compared with the experimental data."

This report presents "Results of a critical literature review on pressure drop due to isothermal turbulent flow in noncircular geometries" (introduction).