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 documenting the problems, design, and operation of countercurrent liquid-foam columns.

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.

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 concerning the fixation and disposal of toxic waste derived from the Purex solvent extraction process.

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.

This report describes a computer program--Oak Ridge Thermal Ellipsoid Plot program (OR TEP)--for drawing crystal structure illustrations with a mechanical plotter.

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.

Report describing Hanford Laboratories' second report regarding thin wall tubing tests. This part covers "the production [of] test equipment developed, its operation, and test results" (p. 2).

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

Report that describes graphite oxidation monitors and their proper storage and handling, as well as the losses encountered when moving the monitors between the laboratory and the reactor.

Report documenting the testing of prototype fuel elements used in a mobile nuclear power plant. Includes descriptions and evaluations of the test.

Report regarding the computer assisted model for a large nuclear reactor. This includes formulas and relevant procedures.

Manual for the Oak Ridge National Laboratory's Isotopes Development Center. Includes procedures for the production, storage, and shipment of radioisotopes.

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

Report concerning the relatively inexpensive fabrication of an aluminum-based fuel element for the Oak Ridge National Laboratory's 250-Mw Advanced Test Reactor.

Report discussing the manual and automatic welding techniques for fuel elements containing plutonium with Zircaloy-2 aluminum, and stainless steel cladding, 0.013 to 0.0889 cm (0.005 to 0.350 in.) thick" (p. 3).

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.

From abstract: "The Darex process developed for the recovery of uranium from stainless steel-containing reactor fuels consists of three steps: (1) dissolution of the fuel material in dilute aqua regia, (2) removal of chloride from the solution to prevent corrosion of downstream stainless steel process equipment, and (3) adjustment of the nitrate solution to solvent extraction feed conditions."

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

Report describing a 300-Mw(e) Supercritical Pressure Power Reactor's facilities, physics, economics, and problems encountered during its development. Appendix begins on page 103.

A series of calculations are described which evaluated the heat transfer and fluid flow aspects of the Plutonium Recycle Test Reactor Pressurized Gas-Loop Facility.

This purpose of this report is to establish a means of determining the mean effective temperature at which any specimen of Al-Si had been annealed.

A test program conducted to develop high integrity piping and seal components for Plutonium Recycle Test Reactor installation. Methods of preventing leakage of costly D2O coolant and maintaining operational safety were investigated.