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Experimental Stress Analysis of EGCR Pressure Vessel
Report regarding the structural evaluations made of the upper head of the Experimental Gas Cooled Reactor (EGCR). This report includes descriptions of the model, experimental procedures, and analyses of the results. Appendix begins on page 139.
Date:
1961
Creator:
Greenstreet, B. L.; Holland, R. W.; Maxwell, R. L.; Witt, F. J.; Shobe, L. R. & LaVerne, M. E.
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
Chemical Technology Division Annual Progress Report, May 31, 1961
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.
System:
The UNT Digital Library
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
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
Snap-8 Corrosion Program Quarterly Progress Report for Period Ending November 30, 1964
Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Snap-8 Corrosion Program. Progress in design, operation, and experimental work is presented. This report includes tables, illustrations, and photographs.
Date:
March 1965
Creator:
Savage, H. W.; Compere, E. L.; MacPherson, R. E.; Huntley, W. R. & Taboada, A.
System:
The UNT Digital Library
Health Physics Instrument Manual
Report issued by the Oak Ridge National Laboratory discussing a Health Physics Instrument Manual. Descriptions, characteristics, and applications of different instruments are presented. This report includes tables, illustrations, and photographs.
Date:
May 16, 1963
Creator:
Davis, D. M. & Gupton, E. D.
System:
The UNT Digital Library
Interim Report on Corrosion by Zirconium-Base Fluorides
Report issued by the Oak Ridge National Laboratory discussing studies conducted on corrosion by fluorides. Equipment, procedures, results, and analysis is presented. This report includes tables, illustrations, and photographs.
Date:
January 17, 1961
Creator:
Adamson, G. M.; Crouse, R. S. & Manly, W. D.
System:
The UNT Digital Library
Evaporation of Iron-, Nickel-, and Cobalt-Base Alloys at 760 to 980°C in High Vacuums
Report issued by the Oak Ridge National Laboratory discussing the evaporation of alloys in high vacuums. As stated in the introduction, "the investigation encompasses measurements of the evaporation rates, identification of the evaporating elements, and correlation of these measurements to the alloy composition for specimens in both the polished and oxidized conditions" (p. 2). This report includes tables, illustrations, and photographs.
Date:
November 1964
Creator:
Bourgette, D. T.
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
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
Microscopic and Autoradiographic Studies of Distribution of Uranium in the Rat Kidney
Report issued by the Oak Ridge National Laboratory discussing studies conducted on uranium retention in rat kidneys. Methods, equipment, and results of the studies are presented. This report includes tables, illustrations, and photographs.
Date:
February 1965
Creator:
Jones, Edith Seymour
System:
The UNT Digital Library
High-Density Concrete for Gamma and Neutron Attenuation
Report issued by the Oak Ridge National Laboratory discussing the development of a high-density concrete. As stated in the abstract, "the basic approach to high-density concrete mix design is reviewed to show that theoretical calculations for concrete mixes do give results that are reliable" (p. 1). This report includes tables, illustrations, and photographs.
Date:
March 1965
Creator:
Northup, T. E.
System:
The UNT Digital Library
Irradiation Testing of Fuel for Core B of the Enrico Fermi Fast Breeder Reactor
Report issued by the Oak Ridge National Laboratory discussing irradiation testing of fast breeder reactors. As stated in the introduction, "it is the purpose of this report to describe the irradiation studies carried out in support of the Core B fuel element development program" (p. 3). This report includes tables, illustrations, and photographs.
Date:
November 1964
Creator:
Thurber, W. C.; McQuilkin, F. R.; Long, E. L., Jr. & Osborne, M. F.
System:
The UNT Digital Library
Measurement of α, the Ratio of the Neutron Capture Cross Section to the Fission Cross Section, for ²³⁵U in the Energy Region from 3.25 eV to 1.8 keV
Report issued by the Oak Ridge National Laboratory discussing techniques to obtain measurements of alpha for enriched uranium. Descriptions of equipment and experiments used to obtain alpha are presented. This report includes tables, and illustrations.
Date:
April 1965
Creator:
deSaussure, G.; Weston, L. W.; Gwin, R.; Russell, J. E. & Hockenbury, R. W.
System:
The UNT Digital Library
Optical Mapping of Oak Ridge Research Reactor Experiment Tubes
Report issued by the Oak Ridge National Laboratory discussing optical mapping of experiment tubes. Descriptions of experiment equipment, and designs of the tubes are presented. This report includes tables, illustrations, and photographs.
Date:
April 1965
Creator:
Abbatiello, A. A.
System:
The UNT Digital Library
Type 316 Stainless Steel, Inconel, and Haynes Alloy No. 25 Natural-Circulation Boiling-Potassium Corrosion Test Loops
Report issued by the Oak Ridge National Laboratory discussing natural-circulation corrosion test loops. As stated in the abstract, "an investigation was undertaken to determine the compatibility of conventional nickel, iron, and cobalt-base high-temperature alloys with boiling potassium. The tests were designed to obtain quantitative information on the dissolution of the container alloys by condensing potassium and the subsequent deposition of solute in the subcooled liquid region of the test device" (p. 1). This report includes tables, illustrations, and illustrations.
Date:
June 1965
Creator:
Jansen, D. H. & Hoffman, E. E.
System:
The UNT Digital Library
Review of Radioisotopes Program, 1964
Report issued by the Oak Ridge National Laboratory discussing a review of the Radioisotopes Program during 1964. Research and experimental projects conducted during 1964 is presented. This report includes tables, illustrations, and photographs.
Date:
May 1965
Creator:
Gillette, J. H.
System:
The UNT Digital Library
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
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
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.
System:
The UNT Digital Library
Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 5, Fuel Element Rupture Testing Facility Analysis
This report describes the final design of the Fuel Element Rupture Testing Facility and summarizes the safeguards analyses of the design and plans for operation.
Date:
May 1963
Creator:
Hanthorn, H. E.
System:
The UNT Digital Library
Ultrasonic Resin Level Detector
This report describes the development of an ultrasonic instrument for resin level measurements in an ion exchange column.
Date:
January 15, 1960
Creator:
Hunter, D. O. & Pleasance, C. L.
System:
The UNT Digital Library
Specifications for Swaged UO2 19-Rod Cluster, PRTR Fuel Element Mark 1
Specifications including detail dimension, materials, fabrication steps, acceptance criteria, and final assembly steps for the swaged uranium dioxide, 19-rod cluster Plutonium Recycle Test Reactor fuel element.
Date:
March 15, 1960
Creator:
Millhollen, M. K.
System:
The UNT Digital Library
Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility
A series of calculations are described which evaluated the heat transfer and fluid flow aspects of the Plutonium Recycle Test Reactor Pressurized Gas-Loop Facility.
Date:
June 1961
Creator:
Muraoka, J.
System:
The UNT Digital Library