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Advanced Test Reactor Burnout Heat Transfer Tests
From abstract: "Results of burnout test to determine the limiting heat flux in a simulated Advanced Test Reactor fuel element channel."
Date:
January 1964
Creator:
Croft, M. W.
System:
The UNT Digital Library
Advanced Test Reactor Turbo Report
From abstract: "The time-dependent behavior of the Advanced Test Reactor was calculated by the Babcock & Wilcox Company on the Philco 2000 computer, using the Turbo depletion program."
Date:
January 1964
Creator:
Turner, Robert A.
System:
The UNT Digital Library
Argonne National Laboratory Metallurgy Division Annual Report: 1963
Annual report issued by the Argonne National Laboratory discussing work conducted by the Metallurgy Division during 1963 including progress related to experiments, programs, and studies. This report includes tables, illustrations, and photographs.
Date:
1964
Creator:
Foote, Frank G.; Chiswik, Haim H. & Macherey, Robert E.
System:
The UNT Digital Library
Development of the Assembly Method for Fuel Elements for the Advanced Test Reactor
Report regarding the development of fuel elements for the Advanced Test Reactor. The designs for the side plates and joints are documented, as well as the assembly process of the fuel element.
Date:
1964
Creator:
Knight, R. W. & Leitten, C. F., Jr.
System:
The UNT Digital Library
Engineering Development of Fluid-Bed Fluoride Volatility Processes: Part 5. Description of a Pilot-Scale Facility for Uranium Dioxide-Plutonium Dioxide Processing Studies
Report describing a pilot plant constructed at Argonne National Laboratory for studying two major process steps for the recovery of uranium and plutonium from spent nuclear fuels of power reactors. A major objective is the demonstration of optimum process conditions for the two steps for synthetic reactor fuel compositions, including those containing mixtures of inactive fission products.
Date:
1964
Creator:
Vogel, G. J.; Carls, E. L. & Mecham, W. J.
System:
The UNT Digital Library
Hanford Graphite Superheat Reactor (HGSR) Design Study and Evaluation
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.
Date:
January 1964
Creator:
Hanford Atomic Products Operation. N-Reactor Project Section.
System:
The UNT Digital Library
Hanford Radiological Sciences Research and Development Annual Report for 1963
Report regarding ongoing research and development undertaken at Hanfdord Laboratories' physics and instruments laboratory and chemical laboratory.
Date:
January 1964
Creator:
Gamertsfelder, C. C. & Green, J. K.
System:
The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: September 1, 1963 - December 1, 1963
Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date:
January 1, 1964
Creator:
Hardy, Edward P., Jr.; Rivera, Joseph & Collins, William R., Jr.
System:
The UNT Digital Library
Liquid Metal Fast Breeder Reactor Design Study
From introduction: "The primary objective of the present study was to develop a conceptual design of a large sodium cooled fast breeder reactor of a nominal electrical rating of 1000 Mw operating on the uranium-plutonium cycle."
Date:
January 1964
Creator:
unknown
System:
The UNT Digital Library
Liquid Metal Fast Breeder Reactor Design Study: Volume 1
From abstract: "A detailed description of a reference 1000-MWe fast breeder reactor plant is presented, together with design specifications and the experimental bases for the design."
Date:
January 1964
Creator:
General Electric Company
System:
The UNT Digital Library
Liquid Metal Fast Breeder Reactor Design Study: Volume 2
From introduction: "Documentation of the various considerations and design techniques involved in the design of the reference 1000-MWe fast oxide breeder reactor."
Date:
January 1964
Creator:
General Electric Company
System:
The UNT Digital Library
Scientific-Information Centers in the U.S.A. and the U.S.S.R
From foreword: This report provides a review of the Soviet and U.S. technical information systems.
Date:
1964?
Creator:
Kridler, Thomas P. & Simpson, G. S., Jr.
System:
The UNT Digital Library
A Single Stage Axial Compressor Blade Test Facility
Abstract: This report gives a general description of the single stage axial compressor blade test facility located at the Oak Ridge Gaseous Diffusion Plant, Oak Ridge, Tennessee.
Date:
January 13, 1964
Creator:
Fee, G. G.
System:
The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: September 1963
Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Date:
January 29, 1964
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Inpile Experiments on Retention of Fission Products in 500°F Sodium
Abstract: The results of three separate inpile capsule experiments are presented.
Date:
January 30, 1964
Creator:
Kunkel, W. P.; Elliot, D. M. & Gibson, A. S.
System:
The UNT Digital Library
Advanced Test Reactor Servo Regulator Rod Test Program
From abstract: "Verify rod mechanism characteristics reported by the United Shoe Machinery Corporation, demonstrate that rod mechanism characteristics were compatible with reactor kinetics and that over-all reactor system behavior was stable, and to recommend system modifications needed for satisfactory performance."
Date:
February 1964
Creator:
Pickett, R. T., III
System:
The UNT Digital Library
Flow Stability of Gas-Solids Suspensions: Final Report
From abstract: One of the principal purposes of the work reported was to study the stability of gas-solids suspensions in the presence of a thermal gradient. Previously reported experience with unstable suspensions is summarized.
Date:
February 1964
Creator:
Wachtell, G. P. & Waggener, J. P.
System:
The UNT Digital Library
Solvent Extraction of Strontium, Cerium, and are Earths with D2EHPA, Part 2: Pilot Plant Studies
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).
Date:
February 1964
Creator:
Richardson, G. L.
System:
The UNT Digital Library
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 1
From introduction: "Summary report of the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company."
Date:
February 14, 1964
Creator:
General Electric Company
System:
The UNT Digital Library
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 2
From introduction: "Presents the detailed description of a 1000 MW Electric Power Plant employing one or two Boiling Water Reactors as the steam source."
Date:
February 14, 1964
Creator:
General Electric Company
System:
The UNT Digital Library
1000 MegaWatt Boiling Water Reactor Plant Feasibility Study: Volume 3
From introduction: "Contains the appendices and a complete set of drawings related to the 1000 MWe Boiling Water Reactor Plant Feasibility Study performed by the General Electric Company for the United States Atomic Energy Commission."
Date:
February 14, 1964
Creator:
General Electric Company
System:
The UNT Digital Library
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
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.
Date:
March 1964
Creator:
Kitts, F. G.
System:
The UNT Digital Library
Fretting Corrosion in the Plutonium Recycle Test Reactor
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.
Date:
March 1964
Creator:
Winegardner, W. K.
System:
The UNT Digital Library
Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 2, March-August 1963
From summary: The full 140 element loading of the core was completed on October 10, 1962. At this point, critical operation was begun for operator training and post-critical testing purposes.
Date:
March 1, 1964
Creator:
Darley, D. K.
System:
The UNT Digital Library