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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.
System:
The UNT Digital Library
The Radiation Leakage Survey of the Shield of the Nuclear Ship Savannah
Report containing a survey of the radiation from the nuclear ship Savannah in order to determine the dose rate for people aboard.
Date:
August 29, 1962
Creator:
Blizard, E. P.; Blosser, T. V. & Freeston, R. M., Jr.
System:
The UNT Digital Library
Pulse Amplifier Manual
Manual for the use and repair of repair pulse amplifiers. This covers general testing routines, specific tests, and a bibliography of related materials.
Date:
1962
Creator:
Fairstein, E.
System:
The UNT Digital Library
Computer Programs Using Zonal Harmonics for Magnetic Properties of Current Systems with Special Reference to the IBM 7090
Report that "discusses the magnetic vector and scalar potentials, magnetic field components and their derivatives, and flux linkage for single current systems, and the mutual inductance, forces and torques between two such systems, whose axes are coplanar but not necessarily coincident" (p. 1).
Date:
December 4, 1962
Creator:
Garrett, M. W.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
Status Report Number Three on Clinch River Study
Report describing the progress made in the Clinch River Study for the period May to October 1961. This report is based off of multiple reports of water sampling conducted across six stations in order to evaluate the safety and radioactive content of the Clinch River.
Date:
December 6, 1962
Creator:
Morton, R. J.
System:
The UNT Digital Library
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
System:
The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: March 1962
Report documenting the ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Date:
1962
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: September 1962
Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Date:
1962
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Maritime Reactor Project Annual Progress Report, November 30, 1961
Report issued by the Oak Ridge National Laboratory discussing annual progress made by the Maritime Reactor Program. Progress and studies conducted during 1961 are presented. This report includes tables, illustrations, and photographs.
Date:
1962~
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Molten-Salt Reactor Program Semiannual Progress Report, February 28, 1962
Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Descriptions of design, construction, and experimental progress are presented. This report includes tables, illustrations, and photographs.
Date:
1962
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Molten-Salt Reactor Program Semiannual Progress Report: for Period Ending August 31, 1962
Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Date:
December 12, 1962
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Molten-Salt Reactor Program Semiannual Progress Report, March 1 - August 31, 1961
Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Date:
1962
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Nuclear Safety Program Semiannual Progress Report: for Period Ending June 30, 1962
Report that describes the research and developments of the Nuclear Safety Research and Development Program of the Oak Ridge National Laboratory.
Date:
August 24, 1962
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Reactor Chemistry Division Annual Progress Report for Period Ending January 31, 1962
Report containing the ongoing research and developments of the Oak Ridge National Laboratory's Reactor Chemistry Division.
Date:
1962
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Oak Ridge Analytical Chemistry Division Annual Progress Report: 1962
Report issued by the Oak Ridge National Laboratory discussing progress and work conducted by the Analytical Chemistry Division. Instrumentation, analytical methods, reactor projects, service analysis, and special research is presented. This report includes tables, illustrations, and photographs.
Date:
1962~
Creator:
Oak Ridge National Laboratory. Analytical Chemistry Division.
System:
The UNT Digital Library
Chemical Technology Division Annual Progress Report: for Period Ending June 30, 1962
Report issued by Oak Ridge National Laboratory that discusses progress and work performed by the Chemical Technology Division.
Date:
September 21, 1962
Creator:
Oak Ridge National Laboratory. Chemical Technology Division.
System:
The UNT Digital Library
Oak Ridge Analytical Chemistry Division Annual Progress Report: 1962
Report issued by the Oak Ridge National Laboratory discussing progress and work conducted by the Chemistry Division.
Date:
December 11, 1962
Creator:
Oak Ridge National Laboratory. Chemistry Division.
System:
The UNT Digital Library
Health Physics Division Annual Progress Report, July 31, 1962
Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.
Date:
1962
Creator:
Oak Ridge National Laboratory. Health Physics Division.
System:
The UNT Digital Library
Oak Ridge Metals and Ceramics Division Annual Progress Report: 1962
Report documenting research and developments made by the Metals and Ceramic Division of the Oak Ridge National Laboratory.
Date:
1962~
Creator:
Oak Ridge National Laboratory. Metals and Ceramics Division.
System:
The UNT Digital Library
EVESR Nuclear Superheat Fuel Development Project: Second Quarterly Report, September-November 1962
Quarterly report describing progress on the EVESR Nuclear Superheat Fuel Development Project.
Date:
December 1962
Creator:
Pennington, R. T.
System:
The UNT Digital Library