Report containing ongoing research and development taking place at the Oak Ridge National Laboratory's Electronuclear Division.

Technical report covering the work done to explore heat transfer analytically and experimentally in liquid metals in turbulent flow within the thermal entrance region of circular tubes having uniform well temperature. Includes implications of this research. [From Summary]

Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Gas-Cooled Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.

In-pile loop experiments L-2-15 and L-4-16 were two of a series designed to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various conditions of radiation intensities, temperatures, solution compositions, and velocity flow past specimens.

Report issued by the Oak Ridge National Laboratory discussing annual progress made by the Instrumentation and Controls Division during 1966. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.

Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.

Technical report presenting a consideration of the characteristics of fused salt-ThF4 solutions suitable for use in homogeneous reactors. Presented in tandem with a brief survey of the literature pertaining to such solutions and a summary of the experimental work accomplished. [From Abstract]

From foreword: "This is a documentation of the experiments performed and the data accumulated during the early period of the Experimental Gas-Cooled Reactor (EGCR) fuel element design."

Report issued by the Oak Ridge National Laboratory discussing revisions to previously issued conversion coefficient tables. The revised tables are presented. This report includes tables, and graphs.

From abstract: Liquid alkali metals were circulated in a series of structural alloy loops under reactor radiation at high temperature. The first of these loops was a lithium-stainless steel (type 316) system, and the remainder were sodium-Inconel. No effect of radiation other than radioactivation was found. Mass transfer and metallurgical processes attributable to the operating temperatures were observed."

Technical report covering the metallurgy of thorium and on fabrication techniques. Report investigates the stability and corrosion resistance of thorium exposed to eutectic NaK, extrusion as a means of fabrication of thorium tubes or rods, and corrosion of large single metal crystals by liquid metals. [From Summary]

Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.

Report documenting ongoing experiments, designs, and tests undertaken by the Oak Ridge National Laboratory for the Molten-Salt Reactor Project.

Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Progress of operations, construction, engineering analysis, and development is presented. This report includes tables, illustrations, and photographs.

Report containing material from several Oak Ridge National Laboratory groups regarding nuclear safety.

From introduction: "This is the ninth of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."

Report documenting ongoing research and development carried out by the Instrumentation and Controls Division of the Oak Ridge National Laboratory.

Report containing ongoing research and development of the Oak Ridge National Laboratory's Physics Division.

Report containing reports from the Physics Division of the Oak Ridge National Laboratory that cover a wide variety of subjects.

Report issued by the Oak Ridge National Laboratory discussing natural-circulation corrosion test loops. As stated in the abstract, "an investigation was undertaken to determine the compatibility of conventional nickel, iron, and cobalt-base high-temperature alloys with boiling potassium. The tests were designed to obtain quantitative information on the dissolution of the container alloys by condensing potassium and the subsequent deposition of solute in the subcooled liquid region of the test device" (p. 1). This report includes tables, illustrations, and illustrations.