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.

A chemical flowsheet is proposed for recovery of strontium and rare earths from Purex wastes. The iron in the waste is first complexed with tartrate and the pH is adjusted with caustic. Strontium and rare earths are extracted by a solvent comprised of di(2-ethylhexyl)phosphoric--sodium di (2-ethylhexyl) phosphate--tributyl phosphate -- Amsco 125-82. and are stripped with nitric acid. Processing the strip product through additional solvent extraction cycles yields isolated, concentrated strontium and rare earth fractions.

This bibliography contains 37 references on self-shielding cross sections. The bibliography is limited to the period from 1951 through November 1959 with the references arranged alphabetically by title. The sources used in compiling this bibliography were: Abstracts of Classified Reports Nuclear Science Abstracts

From introduction: The present report is a summary of the experimental work on a laboratory scale to date involving the ammonia reduction and the one step TF4 processes.

This report follows ciritical-assembly studies on: the effect on reactivity caused by changes in axial reflector materials; the effect on reactivity and the power perturbation caused by fast safety control-blade guides; the effect of changes in fuel-element material composition; the effect of changes in fuel-elements spacing designed to produce uniform radial power-generation rates.

This report explores the production of beta silicon carbide, a low-temperature, cubic modification of cubic silicon carbide. The temperature, heating time, type of starting material, and proportion of starting materials were all varied in order to test yields of beta silicon carbide.

Report discussing "the reduction of uranium(VI) with a slight excess of chromous sulfate followed by a potentiometric titration of the uranium(IV) with standard ceric sulfate in an atmosphere of carbon dioxide." This method cannot be used at room temperature.

After shutdown heating rates have been calculated for the target, control plates, and the beryllium reflector of the HFIR. Hilvety previously calculated the after shutdown heating rates in the element and his results are reported in ORNL CP-60-4-110. Decay times of 1.0 10, 10^2, 10^3, 10^4, and 10^5 seconds have been considered, and heat fluxes have been computed for all of the mentioned components. The greatest heat fluxes were found to be at the surfaces of the control plates and the permanent beryllium reflector.