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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
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
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System
Final design for the 30 megawatt intermediate heat exchanger and steam generator.
Date:
January 31, 1962
Creator:
Alco Products (Firm)
System:
The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 2, Chemical and Stress Analysis
Chemical engineering analysis and stress analysis for design of the 3 megawatt intermediate heat exchanger and steam generator for service with a liquid sodium heat transfer fluid.
Date:
February 28, 1962
Creator:
Alco Products (Firm)
System:
The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures
Operation and maintenance procedures for 30 megawatt heat exchanger and steam generator for sodium cooled reactor system.
Date:
May 15, 1962
Creator:
Alco Products (Firm)
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
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
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, 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
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 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.
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
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.
System:
The UNT Digital Library
Salt Bath Heat Transfer Rates for Uranium Plate
Experiment to study temperature conditions during a five-minute heating cycle in the annealing of uranium sheets used as fissile material.
Date:
February 1, 1962
Creator:
Burditt, R. B.
System:
The UNT Digital Library
Ionic Equilibria and Anion Exchange of Uranyl Sulfate Solutions
Theoretical investigation on the nature of ion exchange of acidified uranyl sulfate solutions with Dowex 21K, a strong base ion exchange resin.
Date:
September 28, 1962
Creator:
Stein, P. E.
System:
The UNT Digital Library
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
Automatic Mass Spectrometer for Isotopic Analysis of Lithium
Report discussing an improvement program on lithium mass spectrometers.
Date:
March 15, 1962
Creator:
McBryde, W. T. & Gammon, E. F.
System:
The UNT Digital Library
A Computer Program for Determining First-Collision Neutron Doses
Data processing program written to compute the neutron dose received by individuals exposed in a nuclear excursion.
Date:
May 21, 1962
Creator:
McMurray, C. S.
System:
The UNT Digital Library
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
NS Savannah Upgrading Analog Computer Analysis
From abstract: "This work amplified previous design studies by considering accidents of greater severity, automatic limiting devices to preclude safety action, and more realistic parameters based on operating experience."
Date:
November 1962
Creator:
Rosser, R. M.
System:
The UNT Digital Library
Sodium Mass Transfer - I: Test Loop Design
From abstract: "This report presents the design, fabrication, assembly, operating procedures, and start-up data for six experimental test loops to examine the effect of steel exposed to sodium at temperatures as high as 1300 F."
Date:
June 1962
Creator:
Lockhart, R. W.; Billuris, G. & Lane, M. R.
System:
The UNT Digital Library
Results of Air-Water and Steam-Water Tests on Radial Vane Steam Separator Models
From introduction: "Describes progress in the development of radial vane primary separators following initial work reported in GEAP 3564."
Date:
February 1962
Creator:
Riesland, J. I.
System:
The UNT Digital Library
Comparative Study of PuC-UC and PuO₂-UO₂ as Fast Reactor Fuel
From abstract: "This section, Part II, extends the comparison of two ceramic fuel systems to include the fuel cycle cost comparison in greater detail particularly with respect to fabrication and reprocessing unit costs."
Date:
November 15, 1962
Creator:
Collins, G. D.
System:
The UNT Digital Library
Multi-Rod Burnout at High Pressure
From abstract: "Thirty-two burnout points were obtained on an electrically heated assembly of 9 simulated fuel rods in a square channel."
Date:
September 1962
Creator:
Polomik, E. & Quinn, E. P.
System:
The UNT Digital Library