Theoretical investigation on the nature of ion exchange of acidified uranyl sulfate solutions with Dowex 21K, a strong base ion exchange resin.

From abstract: The temperature of molten uranium was measured indirectly by an infrared radiation pyrometer. The emissivities of graphite and molten uranium were determined, and a series of equations correlating pyrometer readings with melt temperatures was derived.

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

From introduction: "This brief paper deals with the subject of radial temperature differences for heat transfer to fluids flowing through concentric annuli under the following conditions and assumptions: a. constant heat flux; b. fully-established turbulent flow; c. heat transfer through inner wall only; d. physical properties independent of temperature."

Technical report outlining the differences in conductivity of AGOT graphite and AGHT graphite.

Technical report outlining the nature and effects of energy loss and radiation in biological materials during radiobiological processes.

Technical report outlining the effects of chromosomal abnormalities in tetraploid Argentine flint maize pollination, and subsequent generations.

From introduction: This report has been prepared to present the details of the heavy water cooled power reactors, including cost estimates, plant design studies, and other work directly related to the current status of D2O reactors.

Abstract: By use of a modified thermobalance and reactor as the primary experimental tool for sample preparation and evaluation, a process has been developed by which parent uranium feed materials of a widely variable reactivity and composition may be converted to a uniformly reactive uranium dioxide.

Abstract: The measurement and calculation of the reactivity absorbed by Xe135 as functions of time after shutdown for the SRE are described.

Corrosion of anode assembly materials in fluorine generators is pronounced, therefore, selection of the proper materials for construction is important. Several metals and alloys have been tested for corrosion resistance when anodic in a fluorine test cell. In general, copper, copper alloys and magnesium alloys offer the best corrosion resistance.

Abstract: Because of the outstanding heat transfer efficiency of sodium, it is necessary in sodium-cooled reactors to consider and attempt to prevent the occurrence of adverse stresses as a result of thermal transients in the system.

Abstract: Surface and near-surface acceleration and strain were measured on a deep underground nuclear burst (Rainier Shot; 900 ft; 1.7 kt) to permit extrapolation of results to nuclear detonations of other yields under different test or employment conditions.

Abstract: A 3000 kw (thermal) bayonet duplex tube model steam generator was performance-tested in a liquid metal test loop at MSA Research Corporation, Callery, Pennsylvania, under the cognizance of Atomics International.

Technical report. Three extractions of a diethyl ether solution of uranyl nitrate with small portions of water are effective in removing rare earths, as is shown by radio-gadolinium and radio-europium tracer experiments. A study of representative ethers, alcohols, ketones, and esters showed that diethyl ether and a mixture of 85% ethyl methyl ketone with 15% xylene are the best solvents for the extraction.

Technical Report: A generalized review of the chemical problems and researches related principally to the heavy water homogeneous pile is presented herewith. The report covers researches performed principally by the Columbia Group who initiated the study. This report contains a chronological outline of the development, a discussion of some special topics whose significance is paramount in any slurry pile discussion, and finally an outline of important research problems remaining, roughly graded in order of their importance. No attempt has been made to be either complete or detailed in the discussion. The emphasis has been principally on furnishing a broad guide to those who may t some future date take up this work.

Technical report abstract. A rapid procedure for the preparation of very pure carrier-free Zr and Nb tracer involves the chloroform extraction of the cupferrides of Zr and Nb activities from process solutions. Zr and Nb form very stable chloroform soluble cupferrides in acid solutions (CK-993) and are separated from other fission elements almost quantitatively to yield pure mixture of Zr and Nb activity. A minimum of operations is required and the method is easily adaptable to remote control.

From introduction: "The discovery of element number 96, curium, was realized by the preparation and identification of the isotope Cm-242 by G. T. Seaborg, R. A. James and A. Ghiorso by cyclotron bombardment of Pu-239 with helium ions."

Report presenting data tables which summarize neutron cross sections for elements from hydrogen to bismuth. This data was to be available on September 1, 1947. Purpose and acknowledgements are given as well as criteria for omitting measurements and explanation of the material.

Abstract: This report presents the results of plant optimization studies and cost estimates of the reference design for a natural uranium, graphite moderated, gas-cooled reactor and power plant which was described in NAA-SR-1833.

This report discusses two methods used for experimental determination of the interfacial tension of an immisible aqueous-organic system where the density of the organic phase is less than that of the aqueous phase. The methods discussed are the falling drop method and the Donnan modification/rising drop method.

This report for November, 1947 describes progress regarding chemical work on shales and organic precipitants for uranium.

Introduction: "This paper presents in formula form IBM computational procedure for averaging cross-section data and for calculating reflected spherical reactors by the linear by the linear multigroup numerical method developed by the Physics Section of the ANP Central Design Group. The adjoint reactor numerical procedural is included."

"The following report is meant to serve a two fold purpose. First, it is the quarterly report of the homogeneous reactor project for the Technical Division of Oak Ridge National Laboratory. Secondly, it is a description and general feasibility discussion of a 200-1000 K.W. pilot model, homogeneous reactor."