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 Decade: 1960-1969
 Year: 1964
 Collection: Technical Report Archive and Image Library
Development of Fabrication Procedures for Core B Fuel Elements for the Enrico Fermi Fast Breeder Reactor

Development of Fabrication Procedures for Core B Fuel Elements for the Enrico Fermi Fast Breeder Reactor

Date: 1964
Creator: Donnelly, R. G.; Thurber, W. C. & Slaughter, G. M.
Description: Report describing the "development procedures for fabricating the proposed Core B fuel element of the Enrico Fermi Fast Breeder Reactor" (p. 1). This includes a description of various components, reactor assembly, and reported conclusions. Appendices begin on page 57.
Contributing Partner: UNT Libraries Government Documents Department
Procedures for Fabricating Aluminum-Base ATR Fuel Elements

Procedures for Fabricating Aluminum-Base ATR Fuel Elements

Date: June 1964
Creator: Beaver, R. J.; Patriarca, P. & Adamson, G. M.
Description: Report concerning the relatively inexpensive fabrication of an aluminum-based fuel element for the Oak Ridge National Laboratory's 250-Mw Advanced Test Reactor.
Contributing Partner: UNT Libraries Government Documents Department
Evaporation of Iron-, Nickel-, and Cobalt-Base Alloys at 760 to 980°C in High Vacuums

Evaporation of Iron-, Nickel-, and Cobalt-Base Alloys at 760 to 980°C in High Vacuums

Date: November 1964
Creator: Bourgette, D. T.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
Irradiation Testing of Fuel for Core B of the Enrico Fermi Fast Breeder Reactor

Irradiation Testing of Fuel for Core B of the Enrico Fermi Fast Breeder Reactor

Date: November 1964
Creator: Thurber, W. C.; McQuilkin, F. R.; Long, E. L., Jr. & Osborne, M. F.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
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

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

Date: October 1964
Creator: Gens, T. A.
Description: 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.
Contributing Partner: UNT Libraries Government Documents Department
An Experimental Investigation of Instantaneous-Collapse and Creep-Buckling Characteristics of Cylindrical Shells

An Experimental Investigation of Instantaneous-Collapse and Creep-Buckling Characteristics of Cylindrical Shells

Date: 1964
Creator: Greenstreet, B. L. & Corum, J. M.
Description: Report tests "conducted on nominal 8.0-in.-OD by 0.25-in.-wall and 4.0-in.-OD by 0.12-in.-wall specimens made from commercial pipe and tubing" (p. 1).
Contributing Partner: UNT Libraries Government Documents Department
Graphite Burnout Monitoring: Part 1, Monitor Preparation and Handling Techniques

Graphite Burnout Monitoring: Part 1, Monitor Preparation and Handling Techniques

Date: June 1964
Creator: Ryan, B. A.
Description: Report that describes graphite oxidation monitors and their proper storage and handling, as well as the losses encountered when moving the monitors between the laboratory and the reactor.
Contributing Partner: UNT Libraries Government Documents Department
A New Model Concept for Large Nuclear Reactors

A New Model Concept for Large Nuclear Reactors

Date: June 1964
Creator: Harvey, R. A.
Description: Report regarding the computer assisted model for a large nuclear reactor. This includes formulas and relevant procedures.
Contributing Partner: UNT Libraries Government Documents Department
Solvent Extraction of Strontium, Cerium, and are Earths with D2EHPA, Part 2: Pilot Plant Studies

Solvent Extraction of Strontium, Cerium, and are Earths with D2EHPA, Part 2: Pilot Plant Studies

Date: February 1964
Creator: Richardson, G. L.
Description: Report that "presents the results of pilot plant studies on the application of the D2EHPA (di-2-ethylhexyl phosphoric acid) solvent system to the needs of the Hanford Waste Management Program" (p. 1).
Contributing Partner: UNT Libraries Government Documents Department
The H-4, H-5, and H-6 Irradiation Experiments: Irradiation of N-Reactor Graphite, Interim Report Number 1

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

Date: October 1964
Creator: Helm, J. W.
Description: 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).
Contributing Partner: UNT Libraries Government Documents Department
6144-Channel Time-of-Flight Analyzer

6144-Channel Time-of-Flight Analyzer

Date: September 1964
Creator: Walker, R. A. & Russell, J. T.
Description: Report describing a 6144-channel analyzer designed and built for the purpose of analyzing time-of-flight during studies of slow neutron scattering at Hanford Laboratories. This includes descriptions of the analyzer, its logic and circuits, and its test mode.
Contributing Partner: UNT Libraries Government Documents Department
Evaluation of an Engineering Demonstration of the Modified Zirflex and Neuflex Processes for the Preparation of Solvent Extraction Feeds from Unirradiated Zirconium-Base Reactor Fuels

Evaluation of an Engineering Demonstration of the Modified Zirflex and Neuflex Processes for the Preparation of Solvent Extraction Feeds from Unirradiated Zirconium-Base Reactor Fuels

Date: March 1964
Creator: Kitts, F. G.
Description: Report that investigates the concept of using ammonium fluoride-oxidant systems to dissolve spent U-Zr-Sn reactor fuels in both batch and continuous operation.
Contributing Partner: UNT Libraries Government Documents Department
Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model

Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model

Date: September 1, 1964
Creator: Swanson, C. D.; Coughren, K. D.; Dionne, P. J. & Thieme, G. G.
Description: Report that describes Hanford Laboratories' overall N-Reactor plant simulation model and its use to study the characteristics of the plant, plant operational procedures, and the effects of plant, operator, and control system malfunctions.
Contributing Partner: UNT Libraries Government Documents Department
Progress in Nondestructive Testing: A Summary of Hanford Achievements in These Programs Under General Electric, 1952 - 1964

Progress in Nondestructive Testing: A Summary of Hanford Achievements in These Programs Under General Electric, 1952 - 1964

Date: August 1964
Creator: Walker, R. A. & Russell, J. T.
Description: Report discussing the development of Hanford Laboratories' nondestructive testing programs and a summary of their results. Programs include AlSi fuel testing, N-Reactor fuel testing, and reactor research and development.
Contributing Partner: UNT Libraries Government Documents Department
Welding Plutonium-Containing Fuel Elements

Welding Plutonium-Containing Fuel Elements

Date: June 1964
Creator: Lemon, L. C.; Ross, W. T. & Bailey, W. J.
Description: Report discussing the manual and automatic welding techniques for fuel elements containing plutonium with Zircaloy-2 aluminum, and stainless steel cladding, 0.013 to 0.0889 cm (0.005 to 0.350 in.) thick" (p. 3).
Contributing Partner: UNT Libraries Government Documents Department
Fretting Corrosion in the Plutonium Recycle Test Reactor

Fretting Corrosion in the Plutonium Recycle Test Reactor

Date: March 1964
Creator: Winegardner, W. K.
Description: Report that summarizes out-of-reactor tests undertaken to determine operating conditions, estimate damage from and extent of fretting corrosion, and describe continuing tests planned to monitor and eliminate this corrosion.
Contributing Partner: UNT Libraries Government Documents Department
Hanford Graphite Superheat Reactor (HGSR) Design Study and Evaluation

Hanford Graphite Superheat Reactor (HGSR) Design Study and Evaluation

Date: January 1964
Creator: Hanford Atomic Products Operation. N-Reactor Project Section.
Description: Report containing the results of a preliminary study of a design concept for a graphite-moderated pressure tube reactor. Topics include reactor design, operating procedures, subsystems, hazards analysis, and economic potential. Appendices begin on page 174.
Contributing Partner: UNT Libraries Government Documents Department
The H-3 Irradiation Experiment: Irradiation of Experimental Gas Cooled Reactor Graphite, Number 2

The H-3 Irradiation Experiment: Irradiation of Experimental Gas Cooled Reactor Graphite, Number 2

Date: September 1964
Creator: Helm, J. W.
Description: Report documenting "the long-term irradiation stability of the graphite used as the moderator in the Experimental Gas Cooled Reactor (EGCR) at Oak Ridge" (p. 1) by irradiating capsules at the General Electric Test Reactor. This includes the design and construction of the experiment, experiment procedures, and results of irradiation. Appendices begin on page 83.
Contributing Partner: UNT Libraries Government Documents Department
Solidification of High-Level Radioactive Fuel Reprocessing Wastes by Spray and Pot Calcination: Hot-Cell Pilot Plant Studies

Solidification of High-Level Radioactive Fuel Reprocessing Wastes by Spray and Pot Calcination: Hot-Cell Pilot Plant Studies

Date: September 1964
Creator: Allemann, R. T.; Roberts, F. P. & Upson, U. L.
Description: Report regarding the calcination of full level Purex and Redox waste carried out "in a remotely operated pilot plant consisting of a radiant-heat spray calciner and a pot calciner and their associated off-gas equipment" (p. 4). This contains details of the calcination, effects on the waste, and difficulties encountered.
Contributing Partner: UNT Libraries Government Documents Department
The Effect of Deionized Water on the Reactor Effluent Activities: Part 2 - Zirconium and Aluminum Clad Fuel

The Effect of Deionized Water on the Reactor Effluent Activities: Part 2 - Zirconium and Aluminum Clad Fuel

Date: October 1964
Creator: Silker, W. B. & Thomas, C. W.
Description: Report containing experimental data testing the hypothesis that aluminum reactor tubes were "the site of most radioisotope production in the deionized water cooled system" and that zirconium tubes provided "only nominal participation" (p. 2).
Contributing Partner: UNT Libraries Government Documents Department
Thin Wall Tubing Tests Using Ultrasonic Shear Waves: Part 2 - Production Test Equipment, Its Operation and Test Results

Thin Wall Tubing Tests Using Ultrasonic Shear Waves: Part 2 - Production Test Equipment, Its Operation and Test Results

Date: June 30, 1964
Creator: Zeutschel, M. F. & Dixon, N. E.
Description: Report describing Hanford Laboratories' second report regarding thin wall tubing tests. This part covers "the production [of] test equipment developed, its operation, and test results" (p. 2).
Contributing Partner: UNT Libraries Government Documents Department
Recovery of Aluminum Nitrate Nonahydrate from Redox Acid Waste, Part 1: Computer Study

Recovery of Aluminum Nitrate Nonahydrate from Redox Acid Waste, Part 1: Computer Study

Date: July 1964
Creator: Godfrey, W. L. & Benham, R. D.
Description: Report describing an analog computer simulation of a counter-current crystallization process for use in the recovery of aluminum nitrate nonahydrate from redox acid waste
Contributing Partner: UNT Libraries Government Documents Department
Analog Computer Simulation of a Pulsed Extraction Column

Analog Computer Simulation of a Pulsed Extraction Column

Date: September 1964
Creator: Benham, R. D. & Wilburn, N. P.
Description: Report describing "computer techniques used in the simulation and parameter determination, how the data were prepared for inclusion in the computer simulation, (and) methods used in presenting the results" (p. 3-4).
Contributing Partner: UNT Libraries Government Documents Department
Fuel Cycle Costs for a Plutonium Recycle System

Fuel Cycle Costs for a Plutonium Recycle System

Date: January 20, 1964
Creator: Harrington, F. E.; Arnold, E. D.; Brater, D. C.; Douglas, D. A.; Smiley, S. H.; Stockdale, W. G. et al.
Description: Report containing the estimated costs of the chemical and metallurgical steps in plutonium recycling for large desalination reactors.
Contributing Partner: UNT Libraries Government Documents Department
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