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Aircraft Reactor Test Removal and Disassembly (open access)

Aircraft Reactor Test Removal and Disassembly

Report documenting the dissection of a reactor called the Aircraft Reactor Test (ART). Includes the removal of the reactor from its test cell, component removal, and plans for a for a disassembly building facility.
Date: 1960?
Creator: Abbatiello, A. A. & McQuilkin, F. R.
System: The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1959 (open access)

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1959

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date: February 15, 1960
Creator: Aerojet-General Corporation
System: The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960 (open access)

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date: July 31, 1960
Creator: Aerojet-General Corporation
System: The UNT Digital Library
Assembly of Fifty Prototype Fuel Elements for the Experimental Gas-Cooled Reactor (open access)

Assembly of Fifty Prototype Fuel Elements for the Experimental Gas-Cooled Reactor

Report that describes the Oak Ridge National Laboratory Experimental Gas-Cooled Reactor, problems with the procurement and assembly of its components, and its economic feasibility.
Date: December 23, 1960
Creator: Wick, E. A. & Heestand, R. L.
System: The UNT Digital Library
Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C (open access)

Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C

Report discussing the "equilibrium uranium distribution between an aqueous nitric acid solution and a 30 per cent by volume solution of tributyl phosphate in a hydrocarbon diluent" (p. 2). This includes the necessary equations.
Date: August 12, 1960
Creator: Wilburn, N. P.
System: The UNT Digital Library
Calculation of Suspension Peptization (open access)

Calculation of Suspension Peptization

Report regarding the combination the theories of flocculation, particle repulsion, and particle attraction in order to "understand the flocculation characteristics of TH02 suspensions" (p. 2).
Date: 1960
Creator: Sweeton, F. H.
System: The UNT Digital Library
Critical Mass Studies of Plutonium Solutions (open access)

Critical Mass Studies of Plutonium Solutions

Chain reacting conditions for plutonium nitrate in water solution have been examined experimentally for a variety of sizes of spheres and cylinders.
Date: February 15, 1960
Creator: Kruesi, F. E.; Erkman, J. O. & Lanning, D. D.
System: The UNT Digital Library
Dissolution of Power Reactor Fuel Cores (open access)

Dissolution of Power Reactor Fuel Cores

Report discussing the dissolution of simulated fuel cores. Equipment and procedures are discussed along with significant characteristics of the core materials.
Date: August 26, 1960
Creator: Blaine, H. T.
System: The UNT Digital Library
Environmental Analysis of NS "Savannah" Operation at Camden (open access)

Environmental Analysis of NS "Savannah" Operation at Camden

Report regarding the nuclear ship "Savannah" and the consequences of nuclear activity that it would release into the surrounding area at its proposed startup site, Camden, New Jersey. Scenarios include activity being released into the atmosphere and hydrosphere, damage to equipment, and effects on a population.
Date: 1960
Creator: Cottrell, William B.; Mann, L. A.; Parker, F. L. & Schmidt, G. D.
System: The UNT Digital Library
Feasibility Study of a High Temperature Integral Liquid Metal Fuel Reactor for Low Cost Power (open access)

Feasibility Study of a High Temperature Integral Liquid Metal Fuel Reactor for Low Cost Power

Preliminary study to determine the technical and economic feasibility of a 315 eMW High-Temperature, Integral, Liquid Metal Fuel Reactor (HTIR).
Date: April 1960
Creator: unknown
System: The UNT Digital Library
Fission-Product Release from UO2 (open access)

Fission-Product Release from UO2

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.
System: The UNT Digital Library
Fuel Core Tester - UT-2 (open access)

Fuel Core Tester - UT-2

Report that "describes an instrument that nondestructively tests uranium fuel element cores by ultrasonic methods" (p. 2).
Date: July 18, 1960
Creator: Frederick, C. L. & Waldkoetter, G. L.
System: The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: September 1960 (open access)

Gas-Cooled Reactor Project Quarterly Progress Report: September 1960

Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.
Date: November 11, 1960
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Halogen Collector Test Program (open access)

Halogen Collector Test Program

Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.
Date: March 1, 1960
Creator: Arthur D. Little, Inc.
System: The UNT Digital Library
Hanford Controlled Potential Coulometer (open access)

Hanford Controlled Potential Coulometer

Report describing the Hanford Laboratory controlled potential coulometer. This includes the theory behind the coulometer, details of its circuitry, and performance tests. Appendix begins on page 23.
Date: July 11, 1960
Creator: Connally, R. E. & Scott, F. A.
System: The UNT Digital Library
Hazards Summary Report for the Hanford Plutonium Critical Mass Laboratory (open access)

Hazards Summary Report for the Hanford Plutonium Critical Mass Laboratory

Report that summarizes the potential hazards of the Hanford Critical Mass Laboratory and presents operation procedures which will limit the probability of a nuclear accident. The report also outlines the planned experimental program, descriptions of the facility, and the administration of nuclear safety in the laboratory.
Date: August 1, 1960
Creator: Reardon, W. A.; Clayton, E. D.; Brown, C. L.; Masterson, R. H.; Powell, T. J.; Richey, C. R. et al.
System: The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: November 1959-January 1960 (open access)

Homogeneous Reactor Project Quarterly Progress Report: November 1959-January 1960

From Summary: "The major objective of the run was the investigation of fuel stability. The reactor operated for long periods at the design power of 5 Mw with none of the usual indications of instability while the system pressure was kept at 1250 psig. Run 21 ended on January 22, so that the reason for an abrupt change in the mixing rate of fuel between the core and blanket could be investigated and a reactor steam-system valve could be repaired."
Date: April 29, 1960
Creator: Briggs, R. B.
System: The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: May-July 1960 (open access)

Homogeneous Reactor Project Quarterly Progress Report: May-July 1960

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: 1960
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Kinematics of Nuclear Reactions Calculated with the IBM-704 Computer (open access)

Kinematics of Nuclear Reactions Calculated with the IBM-704 Computer

Program using the IBM-704 computer to calculate certain kinematic quantities for any non-relativistic reaction of the form.
Date: December 20, 1960
Creator: Williams, B. D.
System: The UNT Digital Library
Liquid Metal Fuel Reactor Experiment: Operation and Testing of a Nonnuclear Liquid-Metal System (open access)

Liquid Metal Fuel Reactor Experiment: Operation and Testing of a Nonnuclear Liquid-Metal System

Extensive experimental program undertaken to provide data on the operation and testing of a bismuth-to-bismuth dual-loop system.
Date: May 1960
Creator: unknown
System: The UNT Digital Library
The Liquid Metal Thorium Breeder Reactor (open access)

The Liquid Metal Thorium Breeder Reactor

From introduction: "Investigation of breeding potential and technical and economic feasibility of breeding in the Liquid Metal Fuel Reactor concept."
Date: February 1960
Creator: unknown
System: The UNT Digital Library
Metallurgy Division Annual Progress Report, July 1, 1960 (open access)

Metallurgy Division Annual Progress Report, July 1, 1960

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.
System: The UNT Digital Library
Molten-Salt Reactor Program Quarterly Progress Report: July 1960 (open access)

Molten-Salt Reactor Program Quarterly Progress Report: July 1960

Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Date: December 22, 1960
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 2, Consequences of a Primary Coolant Leak (open access)

Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 2, Consequences of a Primary Coolant Leak

Review of previous work is presented in addition to the results of recent studies concerning loss of primary coolant when the system is cold and pressurized and the problem of supplying adequate cooling following the injection of light water.
Date: November 15, 1960
Creator: Wittenbrock, N. G. & Muraoka, J.
System: The UNT Digital Library