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Steady Darcian Transport of Fluids in Heterogeneous Partially Saturated Porous Media: Part 2, the Computer Program
The subject of this report is the generalized computer program written to solve problems involving steady fluid flow through heterogeneous, partially-saturated porous media.
Date:
May 20, 1964
Creator:
Nelson, R. William
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
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
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
A New Model Concept for Large Nuclear Reactors
Report regarding the computer assisted model for a large nuclear reactor. This includes formulas and relevant procedures.
Date:
June 1964
Creator:
Harvey, R. A.
System:
The UNT Digital Library
The Effect of Deionized Water on the Reactor Effluent Activities: Part 2 - Zirconium and Aluminum Clad Fuel
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).
Date:
October 1964
Creator:
Silker, W. B. & Thomas, C. W.
System:
The UNT Digital Library
Standardization and Evaluation of Grain Size Test for Uranium Fuel
Report that "describes the selection of "standard fuel cores for calibrating an ultrasonic tester designated UT-2C" (p. 3) at Hanford Laboratories.
Date:
July 1964
Creator:
Spice, R. D.
System:
The UNT Digital Library
Beta-Gamma Dose Rates from U232 in U233
This report defines in detail the source of the dose rate of U233 and describes a method by which they may be predicted.
Date:
April 1964
Creator:
Owen, F. E.
System:
The UNT Digital Library
Graphite Burnout Monitoring: Part 1, Monitor Preparation and Handling Techniques
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.
Date:
June 1964
Creator:
Ryan, B. A.
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
The High Flux Isotope Reactor: Volume 2, Selected Construction Drawings
Report containing a series of drawings detailing the Oak Ridge National Laboratory's high flux isotope reactor, its surroundings, and its systems.
Date:
August 1964
Creator:
Binford, F. T.; Cramer, E. N. & Cramer, E. N.
System:
The UNT Digital Library
Fire Test of Wooden-Jacket Shield for Radioisotope Shipping Container
"This report covers fire tests conducted on an experimental design of a wooden-jacket shield for radioisotope shipping containers" (p. i).
Date:
March 23, 1964
Creator:
Horn, Leonard H.
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
International Conference on Fundamental Aspects of Weak Interactions: Held at Brookhavan National Laboratory, September 9-11, 1963
Report issued by the Brookhaven National Laboratory discussing papers presented at the International Conference on Fundamental Aspects of Weak Interactions. Each paper that was presented at the conference is included. This report includes tables, illustrations, and photographs.
Date:
April 1964
Creator:
Brookhaven National Laboratory
System:
The UNT Digital Library
Condensation of Metal Vapors: Mercury and the Kinetic Theory of Condensation
Report issued by the Argonne National Laboratory discussing condensation theories of metal vapors. As stated in the introduction, "the objectives of this research then are critical analysis of condensation theories and data for metal vapors and experimental evaluation of the resistance to condensation for a representative metal such as mercury" (p. 18). This report includes tables, illustrations, and photographs.
Date:
October 1964
Creator:
Wilhelm, Donald J.
System:
The UNT Digital Library
Performance Characteristics of a Liquid Metal MHD Generator
Report issued by the Argonne National Laboratory discussing the performance of magnetohydrodynamic generators. As stated in the abstract, "an experimental study was made of the performance characteristics of a liquid metal MHD generator utilizing single-phase sodium-potassium and two-phase sodium-potassium-nitrogen fluids. The purpose of this study was to compare the generator performance with theory for single-phase flow and to determine the effects of the introduction of the gaseous phase on the generator output and efficiency" (p. 9). This report includes tables, illustrations, and photographs.
Date:
July 1964
Creator:
Petrick, Michael & Lee, Kung-You
System:
The UNT Digital Library
Topic: a Fortran Program for Calculating Transport of Particles in Cylinders
Report discussing the use of TOPIC Sn computer code in the attempt to find a solution to the Boltzmann transport equation.
Date:
April 1964
Creator:
Putnam, G. E.
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
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
Zirconium Processing Capability of the Idaho Chemical Processing Plant
Report discussing a hydrofluoric acid dissolution process that allows the processing of zirconium- or Zircaloy-clad zirconium-uranium fuels.
Date:
October 1964
Creator:
Bower, J. R.
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1964
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date:
November 13, 1964
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Geohydrology of Tatum Salt Dome Area, Lamar and Marion Counties, Mississippi
Report of the Geohydrology of the tatun salt done area of Lamar and Marion counties.
Date:
October 22, 1964
Creator:
Taylor, R. E.
System:
The UNT Digital Library
The Treatment of a Cesium Ore by Sulfur Chloride and Chlorine
From Abstract : "A Southern Rhodesian cesium ore containing essentially pollucite was chlorinated by a gaseous mixture of sulfur chloride and chlorine at temperatures between 550 and 770°C. The optimum conditions with the fixed bed reactor used in this study were chlorination at 650°C for 4 1/2 hr with an more particle size that passes a 150 mesh sieve."
Date:
1964
Creator:
Hamilton, C. B.; Young, T. L. & Wilhelm, H. A.
System:
The UNT Digital Library
Gas-Cooled Fast Reactor Concepts
Report describing the performance characteristics of gas-cooled fast reactors, which compare well with those of sodium-cooled fast reactors. With oxide fuel and helium, CO2, and SO2 coolant at pressures of 1000 to 1500 psia, the reactors have slightly higher breeding ratios than comparable sodium-cooled reactors.
Date:
September 1964
Creator:
Oak Ridge National Laboratory. Reactor Division. Gas-Cooled Reactor Project.
System:
The UNT Digital Library