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Preliminary Designs for Four Integrated Gas-Cooled Ceramic-Fueled and -Moderated Reactor Core and Steam Generator Units

Report containing preliminary designs for four reactor core and steam generator units. The units, their difficulties, and the layout of the reactor building are described.

Date: 1962

Creator: Fraas, A. P.

Partner: UNT Libraries Government Documents Department

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Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1962

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile, low-power, nuclear power plant for Military field operation.

Date: August 17, 1962

Creator: Aerojet-General Corporation

Partner: UNT Libraries Government Documents Department

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Evaluation of Properties of Irradiated Zircaloy-2 Pressure Tube from KER Loop 1

Report describing the evaluation of the effects of irradiation on a high pressure water loop that ruptured while testing fuel elements. Includes photographs of the damaged tube as well as chemical analyses.

Date: December 1962

Creator: Defferdin, L. J.

Partner: UNT Libraries Government Documents Department

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Thermal Conductivity of UO2

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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Strength and Metallurgical Properties of the Zircaloy-2 Pressure Tubes for the Plutonium Recycle Test Reactor

Report describing the properties of the Zircaloy pressure tubes at the Plutonium Recycle Test Reactor. Topics include the fabrication of these tubes, their mechanical properties, and operating stresses.

Date: March 1962

Creator: Knecht, R. L. & Pankaskie, P. J.

Partner: UNT Libraries Government Documents Department

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Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements

Report regarding the study of the calculated costs of fabricating plutonium-enriched fuel elements for Hanford Laboratories' Plutonium Recycle Program. Topics include descriptions of the process, design study of plants that use U235 and plutonium enriched fuel, and estimates of costs.

Date: August 1962

Creator: Hanthorn, H. E.

Partner: UNT Libraries Government Documents Department

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In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 2, May and June, 1962

Report containing the results of a two year program wherein the 85 zircaloy-2 pressure tubes in Hanford Laboratories' Plutonium Recycle Test Reactor (PRTR) were monitored. Experimental procedures and results are described.

Date: August 1962

Creator: Doman, D. R. & Pankaskie, P. J.

Partner: UNT Libraries Government Documents Department

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A Device for Recording Fuel Element Dimension on Punched Paper Tape

Report that "describes a system for translating the position of a strip-chart recorder potentiometer shaft into decimal digital form" (p. ii).

Date: December 1962

Creator: Driver, G. E.

Partner: UNT Libraries Government Documents Department

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Determination of the Effect of High Excess H2SO4 Concentrations on the Radiation-Induced Corrosion of Zirconium and Titanium Alloys in 0.17 m UO2SO4

Study of the effects on Zircaloy-2 radiation corrosion of a high concentration of excess H2SO4 in a uranyl sulfate test solution using an in-pile loop experiment.

Date: May 1, 1962

Creator: Jenks, G. H.

Partner: UNT Libraries Government Documents Department

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In-Pile Loop Investigations of Corrosion of Zircaloy-2 and Other Possible Reactor Materials in 0.04 m UO2SO4 AT 280°C

One of a series of experiments to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various radiation intensities, temperatures, solution compositions, and velocities of flow past specimens.

Date: May 5, 1962

Creator: Jenks, G. H.

Partner: UNT Libraries Government Documents Department

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Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution

Comparison of the economics of mechanical shear-leach and Sulfex decladding-core dissolution head end treatments for processing typical tubular bundles of stainless steel-jacketed UO2 nuclear fuels.

Date: April 23, 1962

Creator: Adams, J. B.; Benis, A. M. & Watson, C. D.

Partner: UNT Libraries Government Documents Department

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In-Pile Loop Irradiation of Aqueous Thoria-Urania Slurry at Elevated Temperature : Design and In-Pile Operation of Loop L-2-27S

Report describing the design and operation of Loop L-2-275, which was used in the irradiation an aqueous thoria-urania slurry.

Date: 1962

Creator: Savage, H. C.; Compere, E. L.; Baker, J. M.; DeCarlo, V. A. & Shor, A. J.

Partner: UNT Libraries Government Documents Department

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Health Physics Research Reactor Hazards Summary

Report describing the design and operation of the Health Physics Research Reactor, its core, and its support structures.

Date: 1962

Creator: Lundin, M. I.

Partner: UNT Libraries Government Documents Department

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Gas-Cooled Reactor Project Quarterly Progress Report: December 1961

Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.

Date: April 6, 1962

Creator: Oak Ridge National Laboratory

Partner: UNT Libraries Government Documents Department

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Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 4, Gas-Cooled Loop Anaysis

Plutonium Recycle Test Reactor (PRTR) final safeguards analysis involving a gas-cooled loop.

Date: March 1962

Creator: Wittenbrock, N. G.

Partner: UNT Libraries Government Documents Department

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Plutonium Recycle Critical Facility: Final Safeguards Analysis

Report discussing the Plutonium Recycle Critical Facility (PRCF). The reactor, building, associated equipment, operating program, safety, and operating procedures are described.

Date: February 1962

Creator: Anderson, J. K. & Winegardner, W. K.

Partner: UNT Libraries Government Documents Department

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Research and Development Activities in the Radiological Sciences, Physical Sciences Portion, January - December 1961

Report regarding ongoing research and development undertaken at Hanfdord Laboratories' physics and instruments laboratory and chemical laboratory.

Date: January 15, 1962

Creator: Junkins, R. L. & Brown, J. E.

Partner: UNT Libraries Government Documents Department

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Magnetic Force Welding Sintered Aluminum Powder Materials

Report discussing the use of sintered aluminum powder for nuclear fuel cladding. This report includes descriptions of pertinent materials and experimental procedures.

Date: March 1962

Creator: Mills, L. E.

Partner: UNT Libraries Government Documents Department

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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."

Date: June 7, 1962

Creator: Kitts, F. G. & Clark, W. E.

Partner: UNT Libraries Government Documents Department

19 Matching Results

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Preliminary Designs for Four Integrated Gas-Cooled Ceramic-Fueled and -Moderated Reactor Core and Steam Generator Units

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1962

Evaluation of Properties of Irradiated Zircaloy-2 Pressure Tube from KER Loop 1

Thermal Conductivity of UO2

Strength and Metallurgical Properties of the Zircaloy-2 Pressure Tubes for the Plutonium Recycle Test Reactor

Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements

In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 2, May and June, 1962

A Device for Recording Fuel Element Dimension on Punched Paper Tape

Determination of the Effect of High Excess H2SO4 Concentrations on the Radiation-Induced Corrosion of Zirconium and Titanium Alloys in 0.17 m UO2SO4

In-Pile Loop Investigations of Corrosion of Zircaloy-2 and Other Possible Reactor Materials in 0.04 m UO2SO4 AT 280°C

Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution

In-Pile Loop Irradiation of Aqueous Thoria-Urania Slurry at Elevated Temperature : Design and In-Pile Operation of Loop L-2-27S

Health Physics Research Reactor Hazards Summary

Gas-Cooled Reactor Project Quarterly Progress Report: December 1961

Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 4, Gas-Cooled Loop Anaysis

Plutonium Recycle Critical Facility: Final Safeguards Analysis

Research and Development Activities in the Radiological Sciences, Physical Sciences Portion, January - December 1961

Magnetic Force Welding Sintered Aluminum Powder Materials

Darex Process: Processing of Stainless Steel-Containing Reactor Fuels with Dilute Aqua Regia