This report summarizes the research and development work carried out during June, July, and August, 1959, for Budget Activity 2790- Separations Development for Non-Production Reactors. The effort on Activity 2790 - Separations Development for Non-Production Reactors. The effort on Activity 2790 will enable Hanford to begin reprocessing in January, 1962, the fuel elements from power reactors which employ depleted or slightly enriched uranium fuels.

This report summarizes experimental results obtained for the General Electric Company under terms of Design, Development and Research Contrast DDR-33. A discussion of the results, the manner in which they were obtained and their probable accuracy are included. Suggested improvements or modifications of properties of this nature be contemplated.

Describes the design criteria, design details, and final installation of a high precision temperature and intimate contact monitor.

Experimental combination hand and shoe counter redesign as a compact, simplified, register readout instrument no larger than the present Five-Fold called Model 2.

From introduction: "This report provides background information regarding the study results presented in the first volume of this report and provides information resulting from the studies made on the gas cooled reactor concept."

Study of factors, such as the average particle size and particle-size distribution, which affect the fluidization properties of uranium trioxide powders.

Comparison of experimentally determined relaxation lengths to the value calculated from the concrete composition.

Graphs for estimation of plutonium and trans-plutonium isotopic content of irradiated plutonium reactor fuel of various initial isotopic compositions.

By radiation dosimetry, we will mean the determination of the energy deposited per unit mass of irradiated material by ionizing radiation. Usually the material of interest in tissue and the results are to be applied to a radiobiological experiment, a radiotherapy treatment, or the protection of personnel from radiation hazards. The same methods, however, are applied to such engineering problems as the production of heat by reactor radiations, the use of radiation in chemical reactions or food processing, etc.

Because of the relative simplicity of the X-Ray spectra and recent improvements in instrumentation, analytical applications of X-Ray of spectrography are becoming very popular. The method us applicable to both qualitative and quantitative determinations of all elements heavier than sodium. Elements in multicomponent systems, such as alloys and minerals, and elements such as, W, Pt, Nb, Ta, Hf, Zr, and the rare earths, which are difficult to separate or determine by other methods, can usually be determined directly without special sample treatment. The method is rapid and precision is comparable to wet chemical analyses. It is applicable over the very wide concentration range from parts per 10,000 to 100 percent, and can be applied to the analysis of all kinds of samples- metals, drillings and thin films, powders, glasses, or liquids. The method is described and its advantages and limitations are discussed. Typical analyses are mentioned and sensitivity limits for determination of the various elements are illustrated as a guide to possible uses of X-ray spectrography.

Accurate knowledge of the lattice parameters comprised in the four factor formula k∞=η∈Pi are required for optimum designing of reactors. In the special case of cluster fuel elements conventional handbook formulas are of little use. It is the intent of this paper to report the results of some recent improvements in the calculation of these parameters. By the addition of certain refinements in the calculation of these parameters. By the addition of certain refinements to the conventional calculational methods considerable success has been obtained in the correlation of theory with experiment.