Report issued by the Argonne National Laboratory discussing progress made on reactor development. Progress made on the core, pressure vessel and shield, and the power plant are presented. This report includes tables, and illustrations.

Report issued by the Argonne National Laboratory discussing selected physical properties of various solids, liquids, and gases of interest in nuclear reactor heat transfer and fluid flow analysis. In most cases, values for thermal conductivity specific heat, density, viscosity, and Prandtl numbers are given as functions of temperature. This report includes tables, and illustrations.

Report issued by the Argonne National Laboratory discussing a summary report of work completed between April and October, 1958. Summaries of the studies conducted and work completed are presented. This report includes tables, and illustrations.

Report issued by the Argonne National Laboratory discussing the shielding of radiation produced by nuclear reactors. As stated in the introduction, "these lectures will be an attempt to discuss the design of a reactor shield and the solution of the associated shielding problems by simple hand-computing methods" (p. 19). This report includes tables, and illustrations.

Report issued by the Argonne National Laboratory discussing high-flux research reactor design studies. As stated in the summary, "this report presents a reactor design to meet the needs of the basic research program at Argonne National Laboratory. The program requires some irradiation in thermal flux...and some beam experiments..." (p. 5). This report includes tables, and illustrations.

Report issued by the Argonne National Laboratory covering a summary report of the work conducted by the Idaho Division. Experimental work and progress made on reactors are presented. This report includes tables, illustrations, and photographs.

Report issued by the Argonne National Laboratory discussing a summary report of the Particle Accelerator Division. As stated in the summary, "this report outlines two methods applicable respectively to longhand and computer calculations" (p. 4). This report includes tables, illustrations, and photographs.

Report issued by the Argonne national Laboratory discussing a technical and economic evaluation of a direct-cycle light-water boiling reactor designed for natural circulation and internal steam-water separation. The reference 100-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. This report includes tables, and illustrations.

Report issued by the Argonne National Laboratory discussing irradiation tests of an aluminum alloy-clad, aluminum-uranium alloy fuel plate. As stated in the introduction, "calculations were made to determine the lowest possible pressure which would allow the maximum possible local boiling on the plate and still assure a margin of safety against burnout" (p. 9). This report includes tables, illustrations, and photographs.

Report that provides "an understanding of the status of gas-cooled reactors as used for unclassified applications" and determining "phases of advanced research and development needed in the field and from these to recommend a program for high-temperature, gas-cooled reactors" (p. 5).

Report issued by the Argonne National Laboratory discussing a summary of projects conducted with the Idaho Division. Descriptions of each project are presented. This report includes tables, and illustrations.

Report issued by the Argonne national Laboratory discussing centrifugal casting of thin uranium plates. The applicability of the centrifugal casting technique to the production of multiple castings of fuel pins of small diameter and of thin fuel plates was investigated. This report includes tables, illustrations, and photographs.

Report estimating the merits of a variety of nuclear reactor concepts for use as external superheaters to be added on to a steam-producing nuclear power plant.

Report regarding the fabrication of a transparent meltdown facility for the purpose of photographing simulated meltdowns.

Report describing the EBR-II shield and the methods employed in arriving at the final design. The major shield design problems for that reactor are enumerated and discussed.

Report describing the helium atmosphere system in the Argonne National Laboratory's Facility 350. The atmosphere's ability to remove moisture, oxygen, and other impurities, how the atmosphere is purified, and experimental data regarding the use of activated carbon to absorb oxygen from helium are discussed.

Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during March 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.

Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during April 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.

Report that "describes an investigation of the flow characteristics in a horizontal, converging-diverging nozzle for a two-phase, two-component system" (p. 1) using air and water and "attempting to determine the effects of accelerating the liquid phase by the gaseous phase" (p. 1).

Report describing the development, fabrication, and nondestructive and destructive evaluation of stainless steel-clad fuel plates, the evaluation of fuel subassemblies, and the assembly of fuel element components at Argonne National Laboratory.

Annual report issued by the Argonne National Laboratory discussing work conducted by the Metallurgy Division during 1963 including progress related to experiments, programs, and studies. This report includes tables, illustrations, and photographs.

Report describing a pilot plant constructed at Argonne National Laboratory for studying two major process steps for the recovery of uranium and plutonium from spent nuclear fuels of power reactors. A major objective is the demonstration of optimum process conditions for the two steps for synthetic reactor fuel compositions, including those containing mixtures of inactive fission products.

Report issued by the Argonne National Laboratory discussing the performance of magnetohydrodynamic generators. As stated in the abstract, "an experimental study was made of the performance characteristics of a liquid metal MHD generator utilizing single-phase sodium-potassium and two-phase sodium-potassium-nitrogen fluids. The purpose of this study was to compare the generator performance with theory for single-phase flow and to determine the effects of the introduction of the gaseous phase on the generator output and efficiency" (p. 9). This report includes tables, illustrations, and photographs.

Report showing "that the Graetz Problem pertaining to the cocurrent-flow, double-pipe, heat exchanger can be studied analytically by extensions of familiar mathematical techniques" (p. 7).