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Gas-Cooled Reactor Project Semiannual Progress Report: March 1965
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.
Type 316 Stainless Steel, Inconel, and Haynes Alloy No. 25 Natural-Circulation Boiling-Potassium Corrosion Test Loops
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.
Instrumentation and Controls Division Annual Progress Report for the Period Ending September 1, 1966
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.
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1965
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.
Molten-Salt Reactor Program Quarterly Progress Report: April 1959
Report documenting ongoing experiments, designs, and tests undertaken by the Oak Ridge National Laboratory for the Molten-Salt Reactor Project.
Physics Division Annual Progress Report, January 31, 1964
Report containing ongoing research and development of the Oak Ridge National Laboratory's Physics Division.
Procedures for Fabricating Aluminum-Base ATR Fuel Elements
Report concerning the relatively inexpensive fabrication of an aluminum-based fuel element for the Oak Ridge National Laboratory's 250-Mw Advanced Test Reactor.
Oak Ridge National Laboratory Radioisotopes Procedures Manual
Manual for the Oak Ridge National Laboratory's Isotopes Development Center. Includes procedures for the production, storage, and shipment of radioisotopes.
Laboratory Development of Processes for Fixation of High-Level Radioactive Waste in Glassy Solids. [Part] 3, Wastes from the Purex Solvent Extraction Process
Report concerning the fixation and disposal of toxic waste derived from the Purex solvent extraction process.
Electronuclear Research Division Annual Progress Report, December 31, 1963
Report containing ongoing research and development taking place at the Oak Ridge National Laboratory's Electronuclear Division.
Engineering Development of a Foam Column for Countercurrent Surface-Liquid Extraction of Surface-Active Solutes
Report documenting the problems, design, and operation of countercurrent liquid-foam columns.
In-Pile Test of Prototype ML-1 Fuel Elements
Report documenting the testing of prototype fuel elements used in a mobile nuclear power plant. Includes descriptions and evaluations of the test.
A New Model Concept for Large Nuclear Reactors
Report regarding the computer assisted model for a large nuclear reactor. This includes formulas and relevant procedures.
Thin Wall Tubing Tests Using Ultrasonic Shear Waves: Part 2 - Production Test Equipment, Its Operation and Test Results
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).
Graphite Burnout Monitoring: Part 1, Monitor Preparation and Handling Techniques
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.
Welding Plutonium-Containing Fuel Elements
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).
Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961
Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
An Alpha, Beta, Gamma Hand and Shoe Counter - Model 2
Experimental combination hand and shoe counter redesign as a compact, simplified, register readout instrument no larger than the present Five-Fold called Model 2.
In-Pile Radiation Corrosion Experiments with Zirconium, Titanium, and Steel Alloys in 0.17 m UO2SO4 Solutions at 280°C
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.
Final Report on Design Tests PR-50 and PR-51: Reactor Piping Seal Testing and Reactor Piping Structural Integrity
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.
Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility
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.
Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor
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.
Reference Design Report LMFRE-1: June 1958, Liquid Metal Fuel Reactor Experiment
Conceptual design of experimental liquid metal fuel reactor.
Plutonium Recycle Test Reactor Preliminary Safeguards Analysis
Report describing the Hanford Atomic Works' Plutonium Recycle Test Reactor, its siting concerns, operation, and safety concerns.
Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy
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.
Irradiation Effects in the EGCR Fuel
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."
Liquid Metal Fuel Reactor: Research and Development Program
Work required, proposed schedule, and an estimate of the costs for complete program to build first LMFR power plant.
Darex Process: Processing of Stainless Steel-Containing Reactor Fuels with Dilute Aqua Regia
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."