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Irradiation Performance of Thoria-Urania Fuel Materials: Quarterly Technical Report, Number 2, October - December 1964 (open access)

Irradiation Performance of Thoria-Urania Fuel Materials: Quarterly Technical Report, Number 2, October - December 1964

From introduction: "Complete exploitation of the advantages of thorium as a fertile material in thermal and particular resonant spectrum reactors has been inhibited by the lack of quantitative physical property data for thoria and thoria-urania fuels."
Date: October 1964
Creator: Babcock & Wilcox Company
System: The UNT Digital Library
Liquid Metal Fuel Reactor Experiment Quarterly Technical Report: July - September 1958 (open access)

Liquid Metal Fuel Reactor Experiment Quarterly Technical Report: July - September 1958

Report containing research and development undertaken regarding the Liquid Metal Fuel Reactor Experiment.
Date: October 1958
Creator: Babcock & Wilcox Company
System: The UNT Digital Library
Zirconium Processing Capability of the Idaho Chemical Processing Plant (open access)

Zirconium Processing Capability of the Idaho Chemical Processing Plant

Report discussing a hydrofluoric acid dissolution process that allows the processing of zirconium- or Zircaloy-clad zirconium-uranium fuels.
Date: October 1964
Creator: Bower, J. R.
System: The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: May-July 1957 (open access)

Homogeneous Reactor Project Quarterly Progress Report: May-July 1957

Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: October 10, 1957
Creator: Briggs, R. B.; Winters, C. E.; Beall, S. E.; Lane, J. A.; Bohlmann, E. G.; Ferguson, D. E. et al.
System: The UNT Digital Library
Final Summary Report of the Gas-Cooled Reactor Experiment-1 (open access)

Final Summary Report of the Gas-Cooled Reactor Experiment-1

Report describing the Gas-Cooled Reactor test facility, its ongoing testing and evaluations of a test reactor, and its operating conditions and characteristics.
Date: October 1963
Creator: Chesworth, R. H.
System: The UNT Digital Library
Thermodynamic Calculations Relating to Chloride Volatility Processing of Nuclear Fuels: [Part] 2. The Capacity of Chlorine for Transporting Plutonium Tetrachloride Vapor During Reaction of U3O8-PuO2 with Carbon Tetrachloride (open access)

Thermodynamic Calculations Relating to Chloride Volatility Processing of Nuclear Fuels: [Part] 2. The Capacity of Chlorine for Transporting Plutonium Tetrachloride Vapor During Reaction of U3O8-PuO2 with Carbon Tetrachloride

Report issued by the Oak Ridge National Laboratory discussing thermodynamic calculations of nuclear fuels. As stated in the introduction, "the equations developed in this report could be used to calculate the capacity of chlorine for transporting plutonium tetrachloride" (p. 2). This report includes tables, and illustrations.
Date: October 1964
Creator: Gens, T. A.
System: The UNT Digital Library
Specifications for Swage Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-M) (open access)

Specifications for Swage Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-M)

Report containing the dimensions, materials, and fabrication details for swage compacted, mixed oxide (UO2-PuO2), fuel elements for the Plutonium Recycle Test Reactor (MARK I-M).
Date: October 1963
Creator: Hanford Atomic Products Operation
System: The UNT Digital Library
Specifications for Vibrationally Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-L) (open access)

Specifications for Vibrationally Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-L)

Report describing the dimensions, materials, and fabrication of vibrationally compacted, mixed oxide (UO2-PuO2) fuel elements for the Plutonium Recycle Test Reactor (MARK I-L). Appendix begins on page 38.
Date: October 1, 1963
Creator: Hanford Atomic Products Operation
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1964 - September 1, 1964 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1964 - September 1, 1964

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: October 1, 1964
Creator: Hardy, Edward P., Jr. & Rivera, Joseph
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1965 - September 1, 1965 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1965 - September 1, 1965

Report documenting radioactive fallout across the world, including material in the atmosphere, on land, and that has deposited into food and water supplies.
Date: October 1, 1965
Creator: Hardy, Edward P., Jr. & Rivera, Joseph
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1962 - September 1, 1962 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1962 - September 1, 1962

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: October 1, 1962
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Collins, William R., Jr.
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1963 - September 1, 1963 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1963 - September 1, 1963

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: October 1, 1963
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Collins, William R., Jr.
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1960 - September 1, 1960 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1960 - September 1, 1960

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: October 1, 1960
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1961 - September 1, 1961 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1961 - September 1, 1961

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: October 1, 1961
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
System: The UNT Digital Library
EOCR Control Rod and Driver Fuel Hydraulic Tests (open access)

EOCR Control Rod and Driver Fuel Hydraulic Tests

Report discussing the results of experiments on an EOCR prototype control rod, control rod drive, and driver fuel assembly that were extensively tested in 500 deg F Santowax and 132 deg F water. These tests not only established the operating characteristics of these assemblies but also revealed a number of deficiencies in the various components. It includes descriptions of the control rod, control rod drive, and driver fuel assembly together with descriptions of their method of operation.
Date: October 19, 1962
Creator: Harrison, L. J.
System: The UNT Digital Library
The H-4, H-5, and H-6 Irradiation Experiments: Irradiation of N-Reactor Graphite, Interim Report Number 1 (open access)

The H-4, H-5, and H-6 Irradiation Experiments: Irradiation of N-Reactor Graphite, Interim Report Number 1

Report regarding an experimental program by Hanford Laboratories' in order "to determine the long-term irradiation behavior of the graphite used as the moderator in N-Reactor. The primary objectives of the program are to provide data for predictions of the distortion of the N-Reactor moderator and the stress conditions which could arise from the difference in the the rate and extent of contraction between the transverse and parallel orientations of the graphite bars" (p. 1).
Date: October 1964
Creator: Helm, J. W.
System: The UNT Digital Library
Source Strength Information for Shielding and Stack Effluent Calculations: a Standard Practices Guide (open access)

Source Strength Information for Shielding and Stack Effluent Calculations: a Standard Practices Guide

Report presenting the curves and methods used "for determining gross fission product gamma energy in Mev/sec-watt, gross fission product beta decay in curies/sec-watt, delayed uranium fission neutrons in neutrons/sec-watt and N16 and N17 decay in photons/sec-cc of water" (p. 1).
Date: October 3, 1958
Creator: Jones, L. H.
System: The UNT Digital Library
Specifications and Procedures Used in Manufacturing U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor (open access)

Specifications and Procedures Used in Manufacturing U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor

Report containing the description and design of U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor. Topics include the requirements of core materials, materials specifications, manufacturing procedures, and shipping preparation.
Date: October 21, 1963
Creator: Kucera, W. J.; Leitten, C. F., Jr. & Beaver, R. J.
System: The UNT Digital Library
Analysis of Failure of Type 304 Stainless Steel Clad Swaged Powder Fuel Assembly (open access)

Analysis of Failure of Type 304 Stainless Steel Clad Swaged Powder Fuel Assembly

From introduction: "The purpose of this report is to describe the observations made during the post-irradiation examination of HPD-2S, and to discuss possible modes of failure.
Date: October 3, 1963
Creator: Lees, E. A.
System: The UNT Digital Library
An Evaluation of Reactor Concepts for Use As Separate Steam Superheaters (open access)

An Evaluation of Reactor Concepts for Use As Separate Steam Superheaters

Report estimating the merits of a variety of nuclear reactor concepts for use as external superheaters to be added on to a steam-producing nuclear power plant.
Date: October 1961
Creator: Lennox, D. H.; MacFarlane, D. R.; Brubaker, R. C.; Martinec, E. L.; Rohde, R. R.; Toppel, B. J. et al.
System: The UNT Digital Library
Effects of Major Parameters on Cycle Efficiency and Cost for a Gas-Cooled Reactor Turbine Power Plant (open access)

Effects of Major Parameters on Cycle Efficiency and Cost for a Gas-Cooled Reactor Turbine Power Plant

Cycle study performed on a closed loop Brayton cycle incorporating a gas-cooled nuclear reactor, regeneration, and compressor intercooling. The purpose of the study was to determine the effect of various cycle parameters on efficiency and cost.
Date: October 5, 1962
Creator: Miskell, R. V.
System: The UNT Digital Library
Distribution of the Actinide Elements in the Molten System: KCI-AICI3-AI (open access)

Distribution of the Actinide Elements in the Molten System: KCI-AICI3-AI

Report of data for the distributions of elements 90 through 96 between molten salt solutions of their chlorides and molten aluminum (or alloy) at 725 Celsius.
Date: October 20, 1959
Creator: Moore, R. H. & Lyon, W. L.
System: The UNT Digital Library
Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1969 (open access)

Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1969

Report documenting the ongoing research and development of the Oak Ridge National Laboratory's Chemical Technology Division.
Date: October 1969
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
System: The UNT Digital Library
Health Physics Division Annual Progress Report, July 31, 1961 (open access)

Health Physics Division Annual Progress Report, July 31, 1961

Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.
Date: October 31, 1961
Creator: Oak Ridge National Laboratory. Health Physics Division.
System: The UNT Digital Library