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Accurate Nuclear Fuel Burnup Analyses; Second Quarterly Progress Report, (March - May 1962)
The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date:
July 1, 1962
Creator:
Rider, B. F.
System:
The UNT Digital Library
An Alpha Scintillation Tester for Uranium Surface Contamination of N-Reactor Fuel
Report that "describes a nondestructive tester and some of its applications in measuring 10 to 100 µg of uranium surface contamination on unirradiated, low enrichment, uranium fuel elements" (p. ii).
Date:
July 1963
Creator:
Jackson, C. N., Jr.
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1959
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile, low-power, nuclear power plant for Military field operation.
Date:
July 31, 1959
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date:
July 31, 1960
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: March 1964
Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project. From summary: "A study was made of the effect of the energy of extraneous source neutrons on the amplitudes of higher modes in the flux distribution of a subcritical reactor."
Date:
July 1964
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Basic Chemistry of High Temperature Inorganic Systems, Semiannual Progress Report: July-December 1956
From abstract: The vapor pressure determination of solid ThF4 has been completed. Experiments to determine the heat of formation of ThF4 by studying the reaction of ThF4 with SiO2 are described.
Date:
July 15, 1957
Creator:
Yosim, S. J. & Milne, T. A.
System:
The UNT Digital Library
Calculations of the Madelung Constant and Inverse Twelfth Power Repulsion Factors for the Wurtzite Crystal Structure
From abstract: The Madelung constant and the inverse twelfth power repulsion factor have been calculated for the wurtzite structure for wide ranges of the crystal parameters and u.
Date:
July 25, 1965
Creator:
Gehman, William G.
System:
The UNT Digital Library
The Closest Packing of Spheres (A Unifying Basis for Crystal Structures)
Abstract: An intuitive approach to the understanding of crystal structures is presented in terms of the concept of the closest packing of spheres.
Date:
July 30, 1961
Creator:
Gehman, William G.
System:
The UNT Digital Library
The Closest Packing of Spheres (A Unifying Basis for Crystal Structures)
"An intuitive approach to the understanding of crystal structures is presented in terms of the concept of the closest packing of spheres. The qualitative features of the concept are sorted out and correlated by successively treating single, double, triple, and multiple layered arrays of closest packed spheres" (p. ix).
Date:
July 30, 1961
Creator:
Gehman, William G.
System:
The UNT Digital Library
Cost Study of a 100-Mw(e) Direct-Cycle Boiling Water Reactor Plant
Report issued by the Argonne national Laboratory discussing a technical and economic evaluation of a direct-cycle light-water boiling reactor designed for natural circulation and internal steam-water separation. The reference 100-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. This report includes tables, and illustrations.
Date:
July 1960
Creator:
Bullinger, C. F. & Harrer, J. M.
System:
The UNT Digital Library
The Design of a Dynamic Corrosion and Chemical Control Test Loop and Preliminary Out-of-Pile Test Results
From abstract: "This report describes the overall loop design and the means by which this design was developed. These include critical facility measurements, analog computer calculations, hydraulic and heat transfer computations, and the construction and operation of an out-of-pile mock-up loop to determine the dynamic characteristics of the loop."
Date:
July 12, 1963
Creator:
Zelezny, W. F.
System:
The UNT Digital Library
The Ductility of Brazed Stainless Steel Joints
Abstract: "The ductility of Type 310 stainless steel T-joints brazed with GE-62 brazing alloy was measured at room temperatures 1200, 1650, and 1800 F. The measure of ductility was taken as the plastic axial strain required to crack braze fillets in T-section tensile specimens. At elevated temperatures, the ductility of as-brazed joints approximated that of the stainless steel, but at room temperature the brazed joints had only one-tenth the ductility of the base metal. Annealing for 16 hr at 1800 F in air was found to triple the room-temperature ductility of the brazed joint."
Date:
July 8, 1953
Creator:
Saller, Henry A.; Stacy, J. T. & Eddy, N. S.
System:
The UNT Digital Library
EDP Procedures in Technical Library Operations
Systems for circulation control, book ordering, journal renewal, printing a book catalog, preparing monthly acquisitions lists.
Date:
July 30, 1963
Creator:
Griffin, Hillis L.
System:
The UNT Digital Library
Effect of Plasma Oscillations on the Table-Top Model
The following report describe the effect of plasma oscillations using a table-top model and the probable magnitude of the quantities needed to reach complete ionization.
Date:
July 31, 1952
Creator:
Spitzer, Lyman, Jr.
System:
The UNT Digital Library
An Experimental Investigation of Two-Phase, Two-Component Flow in a Horizontal, Converging-Diverging Nozzle
Report that "describes an investigation of the flow characteristics in a horizontal, converging-diverging nozzle for a two-phase, two-component system" (p. 1) using air and water and "attempting to determine the effects of accelerating the liquid phase by the gaseous phase" (p. 1).
Date:
July 1963
Creator:
Vogrin, Joseph A., Jr.
System:
The UNT Digital Library
Fabrication Modification Development for OMRE Third Core Loading
Abstract: This report describes the fabrication of elements for the OMRE third core loading.
Date:
July 15, 1961
Creator:
Peters, E. & Binstock, M. H.
System:
The UNT Digital Library
Feasibility Study of a 1000-Mwe Sodium-Cooled Fast Reactor: Volume 1 - Technical and Economic Potential
From abstract: The results of a feasibility study of a 1000-Mwe sodium-cooled fast-reactor are presented.
Date:
July 1966
Creator:
Eggen, D. T.; Cochran, J. C. & Gibson, A. S.
System:
The UNT Digital Library
Feed Materials Production Center Summary Technical Report: April 1, 1963-June 30, 1963
This report summarizes several reports pertaining to uranium processing.
Date:
July 18, 1963
Creator:
unknown
System:
The UNT Digital Library
FMPC Solvent Treatment Area - Process Design
This memorandum presents the process design for the solvent reast area of the Feed Materials Production Center. The purpose ofthe transmittal is to provide the basis for the detailed mechanical design and layout of this section of the refinery. Drawings, flowsheets, and specifications are included.
Date:
July 6, 1951
Creator:
Pfeiffer, Carl & Maerker, John B.
System:
The UNT Digital Library
Fuel Core Tester - UT-2
Report that "describes an instrument that nondestructively tests uranium fuel element cores by ultrasonic methods" (p. 2).
Date:
July 18, 1960
Creator:
Frederick, C. L. & Waldkoetter, G. L.
System:
The UNT Digital Library
Fuel Cycle Program Progress Report: Fifteenth Report, January-June 1964
Quarterly progress report discussing activities related to the Vallecitos Boiling Water Reactor (VBWR) and related facilities.
Date:
July 15, 1964
Creator:
Howard, C. L.
System:
The UNT Digital Library
Fundamental and Applied Research and Development in Metallurgy: Conceptual Design of a U-233 Fuel Refabrication Plant
From abstract: A preliminary study has been made of a direct access, streamlined process for the rapid fabrication of fuel using uranium-233.
Date:
July 30, 1962
Creator:
Nowak, W. B. & Wessling, B. W.
System:
The UNT Digital Library
Fundamentals in the Operation of Nuclear Test Reactors: Volume 3 Engineering Test Design and Operation
Engineering test reactor design and operation.
Date:
July 1964
Creator:
unknown
System:
The UNT Digital Library
Further Studies on Large-Batch Melting of Uranium
The following report focuses on an investigation made to determine if vacuum melting was an absolutely necessary step in the metallurgical process of melting and casting uranium.
Date:
July 11, 1955
Creator:
Rengstorff, George W. & Lownie, Harold W., Jr.
System:
The UNT Digital Library