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Quarterly Progress Report, Research and Development Activities Fixation of Radioactive Residues: April-June 1965

Description: Introduction: "This progress report is the twenty-sixth in a series presenting research and development activities in the field of radioactive wastes. Experimental work charged to programs other than those of the Division of Reactor Development is included for general interest and completeness; such work is identified in the headings."
Date: September 1965
Creator: Pacific Northwest Labortoary. Chemistry Department.
Partner: UNT Libraries Government Documents Department
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Fission-Product Release from UO2

Description: Release of fission products from UO2 with emphasis on fuel elements operated at higher surface temperatures and lower external pressures than those for pressurized-water systems.
Date: September 13, 1960
Creator: Cottrell, W. B.; Culver, H. N.; Scott, J. L. & Yarosh, M. M.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Annual Progress Report, May 31, 1968

Description: Report documenting the ongoing research of the Oak Ridge National Laboratory's Chemical Technology Division. This report includes tables, diagrams, graphs, and articles related to chemical technology.
Date: September 1968
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Annual Progress Report, July 1, 1960

Description: Report documenting ongoing research and development undertaken by the Metallurgy Division of the Oak Ridge National Laboratory.
Date: September 30, 1960
Creator: Oak Ridge National Laboratory. Metallurgy Division.
Partner: UNT Libraries Government Documents Department
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Degassing Sparger Plate Screening Tests

Description: Results of tests to remove fission gases, xenon and krypton, formed during the operation of a nuclear reactor.
Date: September 1958
Creator: Starkweather, D. C.
Partner: UNT Libraries Government Documents Department
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Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model

Description: Report that describes Hanford Laboratories' overall N-Reactor plant simulation model and its use to study the characteristics of the plant, plant operational procedures, and the effects of plant, operator, and control system malfunctions.
Date: September 1, 1964
Creator: Swanson, C. D.; Coughren, K. D.; Dionne, P. J. & Thieme, G. G.
Partner: UNT Libraries Government Documents Department
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6144-Channel Time-of-Flight Analyzer

Description: Report describing a 6144-channel analyzer designed and built for the purpose of analyzing time-of-flight during studies of slow neutron scattering at Hanford Laboratories. This includes descriptions of the analyzer, its logic and circuits, and its test mode.
Date: September 1964
Creator: Walker, R. A. & Russell, J. T.
Partner: UNT Libraries Government Documents Department
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Analog Computer Simulation of a Pulsed Extraction Column

Description: Report describing "computer techniques used in the simulation and parameter determination, how the data were prepared for inclusion in the computer simulation, (and) methods used in presenting the results" (p. 3-4).
Date: September 1964
Creator: Benham, R. D. & Wilburn, N. P.
Partner: UNT Libraries Government Documents Department
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Solidification of High-Level Radioactive Fuel Reprocessing Wastes by Spray and Pot Calcination: Hot-Cell Pilot Plant Studies

Description: Report regarding the calcination of full level Purex and Redox waste carried out "in a remotely operated pilot plant consisting of a radiant-heat spray calciner and a pot calciner and their associated off-gas equipment" (p. 4). This contains details of the calcination, effects on the waste, and difficulties encountered.
Date: September 1964
Creator: Allemann, R. T.; Roberts, F. P. & Upson, U. L.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Annual Progress Report, May 31, 1961

Description: Report documenting the ongoing research and developments of the Chemical Technology Division of the Oak Ridge National Laboratory.
Date: September 21, 1961
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
Partner: UNT Libraries Government Documents Department
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Failure Test of a Double Chambered NaK-Filled Irradiation Capsule

Description: Report describing tests "in which a double chambered irradiation capsule containing NaK (sodium-potassium alloy) in its inner chamber was deliberately perforated to allow NaK (the heat transfer medium) and water to react within the capsule chambers" (p. 2). The report includes descriptions of the materials used in the tests, test procedures, and results.
Date: September 1961
Creator: Kosut, B. S.; Leggett, R. D. & Marshall, R. K.
Partner: UNT Libraries Government Documents Department
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Thermal Conductivity of UO2

Description: Report discussing the thermal conductivity of uranium dioxide. The first part of the report includes the thermal effects on the substance's physical form, while the second part describes the experimental details.
Date: September 1962
Creator: Daniel, J. L.; Matolich, J., Jr. & Deem, H. W.
Partner: UNT Libraries Government Documents Department
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Portable Radiation Survey Instrument

Description: Report describing a portable radiation survey instrument, its design, and usage.
Date: September 1963
Creator: Sheen, E. M. & Spear, W. G.
Partner: UNT Libraries Government Documents Department
open access

Gas-Cooled Fast Reactor Concepts

Description: Report describing the performance characteristics of gas-cooled fast reactors, which compare well with those of sodium-cooled fast reactors. With oxide fuel and helium, CO2, and SO2 coolant at pressures of 1000 to 1500 psia, the reactors have slightly higher breeding ratios than comparable sodium-cooled reactors.
Date: September 1964
Creator: Oak Ridge National Laboratory. Reactor Division. Gas-Cooled Reactor Project.
Partner: UNT Libraries Government Documents Department
open access

The H-3 Irradiation Experiment: Irradiation of Experimental Gas Cooled Reactor Graphite, Number 2

Description: Report documenting "the long-term irradiation stability of the graphite used as the moderator in the Experimental Gas Cooled Reactor (EGCR) at Oak Ridge" (p. 1) by irradiating capsules at the General Electric Test Reactor. This includes the design and construction of the experiment, experiment procedures, and results of irradiation. Appendices begin on page 83.
Date: September 1964
Creator: Helm, J. W.
Partner: UNT Libraries Government Documents Department
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