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Factors Affecting Fluidization of Uranium Trioxide Powders
Study of factors, such as the average particle size and particle-size distribution, which affect the fluidization properties of uranium trioxide powders.
Date:
March 1, 1958
Creator:
Johnson, B. M.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Design and Economic Evaluation of Mobile Blankets for Fast Reactors
Report evaluating the design characteristics and limitations of mobile blankets for breeder reactors. This also includes economic considerations for each tested blanket. Appendices begin on page 40.
Date:
March 10, 1964
Creator:
Klickman, A. E.; Ball, G. L.; Edwards, J. J.; Jens, W. H.; Segal, B. M.; Amorosi, A. et al.
Object Type:
Report
System:
The UNT Digital Library
Strength and Metallurgical Properties of the Zircaloy-2 Pressure Tubes for the Plutonium Recycle Test Reactor
Report describing the properties of the Zircaloy pressure tubes at the Plutonium Recycle Test Reactor. Topics include the fabrication of these tubes, their mechanical properties, and operating stresses.
Date:
March 1962
Creator:
Knecht, R. L. & Pankaskie, P. J.
Object Type:
Report
System:
The UNT Digital Library
Lawrence Radiation Laboratory Physics Division Quarterly Report: November 1953 - January 1954
The following report is a quarterly report done by the Physics Division of the University of California's Radiation Laboratory, covering the period of November and December of 1953, and January of 1954. This report discusses general physics research and the development and operation of the accelerator.
Date:
March 11, 1954
Creator:
Lawrence Radiation Laboratory. Physics Division.
Object Type:
Report
System:
The UNT Digital Library
The Cold Pressing of Sinterable UO₂
The intent of this work was to explore more fully the pressing of sinterable UO2 powders into cylindrical compacts in the hope that a more precise prediction of green density in terms of powder properties, pressure, and geometry could be evolved.
Date:
March 27, 1961
Creator:
Levey, R. P., Jr.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Maritime Reactor Project Annual Progress Report for Period Ending November 30, 1963
Report issued by the Oak Ridge National Laboratory discussing annual progress made by the Maritime Reactor Program. Progress and studies conducted during 1963 are presented. This report includes tables, illustrations, and photographs.
Date:
March 1965
Creator:
McCurdy, H. C.
Object Type:
Report
System:
The UNT Digital Library
Portable Mercury Vapor Detector
From abstract: "This report describes a functional mercury vapor detector which is a portable, self-contained, survey instrument, and had a minimum range from zero to two-tenths milligram of mercury per cubic meter of air."
Date:
March 14, 1958
Creator:
McMurray, C. S. & Redmond, J. W.
Object Type:
Report
System:
The UNT Digital Library
Specifications for Vibrationally Compacted UO2 Nested Tubular Fuel Element (PRTR MARK II-C)
Report describing the vibrationally compacted UO2 nested tubular fuel element, its design specifications, fabrication, and assembly.
Date:
March 1963
Creator:
Milhollen, M. K.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Nuclear Superheat Meeting: March 1962
A report regarding proceedings of the nuclear superheat meeting no. 6, held March 7, 8 and 9, 1962, in Windsor, Connecticut.
Date:
March 30, 1962
Creator:
Mravca, Andrew E.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Results of ATR Sample Fuel Plate Irradiation Experiment
From abstract: "Fuel materials proposed for use in the Advanced Test Reactor were evaluated."
Date:
March 23, 1964
Creator:
Phillips Petroleum Company
Object Type:
Report
System:
The UNT Digital Library
Symposium on Problems in Irradiation Capsule Experiments: October 1963
From introduction: The present paper gives a brief description of the NASA Plum Brook Reactor Facility, discusses the criteria used for design of the capsules, and describes the capsules.
Date:
March 1964
Creator:
Rice, William L. R.
Object Type:
Report
System:
The UNT Digital Library
Reactor Shielding Design Manual
The purpose of this manual is to help an engineer or scientist to design a practical shield by making available to them the techniques and data developed by the Naval Reactors Program and Pressurized Water Reactor Program.
Date:
March 1956
Creator:
Rockwell, Theodore, III
Object Type:
Book
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.
Object Type:
Report
System:
The UNT Digital Library
Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience: August 1960 Through November 1962
Report documenting experience gained by operating the spare PRTR Primary Process Pump. This includes descriptions of equipment used, testing procedures, and operating history.
Date:
March 1963
Creator:
Scott, P. A.
Object Type:
Report
System:
The UNT Digital Library
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H
Report describing the fabrication of of the I-H aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR), including the materials used and design specifications. Appendix begins on page 28.
Date:
March 1961
Creator:
Sharp, R. E.
Object Type:
Report
System:
The UNT Digital Library
A Study of Convective Magnetohydrodynamic Channel Flow
Analysis of a class of steady magnetohydrodynamic channel flow problems when natural, as well as forced, convection is important.
Date:
March 1965
Creator:
Singer, Ralph M.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
A Report on Some Attempts to Cast Centrifugally Fuel Elements of Small Diameter
Report issued by the Argonne national Laboratory discussing centrifugal casting of thin uranium plates. The applicability of the centrifugal casting technique to the production of multiple castings of fuel pins of small diameter and of thin fuel plates was investigated. This report includes tables, illustrations, and photographs.
Date:
March 1961
Creator:
Yaggee, F. L.
Object Type:
Report
System:
The UNT Digital Library