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A Gamma Ray Detector of Variable Geometry for Whole Body Counting of Small Animals
Report documenting the design and operation of a gamma ray detector for use in counting small animals housed in metabolism cages.
Date:
July 1964
Creator:
Goodrich, R. M.; Thomas, R. G. & Wright, S. R.
System:
The UNT Digital Library
Summary Report on Thorium Metal Quality for Production Reactor Use
From abstract: "Background material leading to the development of the metal quality of reactor-grade thorium is given. The metal should be sound and of uniform hardness, free of internal cracks and inclusions, and corrosion resistant. It should contain only small amounts of natural uranium, thorium oxide, and elements that act as reactor poisons. Because of their effect upon metal quality, various methods for the production of thorium are discussed. Use of consumable electrode arc melting as the final step has contributed much to the production of thorium of excellent quality for reactor use."
Date:
July 1958
Creator:
Hayes, Edgar E.
System:
The UNT Digital Library
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
In-Pile Loop Tests of GCRE Elements (I-IT and I-I'T)
Report documenting two in-pile loop experiments conducted at the Battelle Research Reactor-Gas Cooled Reactor (BRR-GCR). These experiments test heat transfer calculations and the behavior of the fuel element under severe thermal-cycling conditions.
Date:
July 2, 1959
Creator:
Nakazato, S.; Williams, P. M. & Wilson, W. D.
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
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
Siting of Fuel Reprocessing Plants and Waste Management Facilities
Report documenting the a study with the goal of identifying the factors that might influence the growth patterns of the fuel processing industry, especially regarding the siting of reprocessing and disposal facilities for high-level waste.
Date:
July 1970
Creator:
Oak Ridge National Laboratory. Chemical Technology Division.
System:
The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: March 1963
Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Date:
July 23, 1963
Creator:
Oak Ridge National Laboratory
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
Nuclear Superheat Quarterly Project Report: Third Quarter, January-March 1960
From introduction: "This is the third of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date:
July 1, 1960
Creator:
Pennington, R. T.
System:
The UNT Digital Library
Nuclear Superheat Quarterly Project Report: Tenth Quarter, October-December 1962
From introduction: "This is the tenth of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date:
July 1962
Creator:
Pennington, R. T.
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
Southwest Experimental Fast Oxide Reactor Development Program: First Quarterly Report, April-June 1964
From abstract: "This report summarizes the work performed on the Research and Development Program for the Southwest Experimental Fast Oxide Reactor."
Date:
July 1964
Creator:
Horst, K. M.
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
Molten-Salt Reactor Program Semiannual Progress Report, January 31, 1964
Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Date:
July 1964
Creator:
Oak Ridge National Laboratory
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
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
Hanford Controlled Potential Coulometer
Report describing the Hanford Laboratory controlled potential coulometer. This includes the theory behind the coulometer, details of its circuitry, and performance tests. Appendix begins on page 23.
Date:
July 11, 1960
Creator:
Connally, R. E. & Scott, F. A.
System:
The UNT Digital Library
The RBU Reactor-Burnup Code: Formulation and Operation Procedures
Report discussing the computer program RBU, which calculates the neutron, reactivity, and isotopic history of a nuclear reactor in such a way as to facilitate the predictions of fuel costs and reactor performance. This report documents RBU's various calculations and operating procedures.
Date:
July 1961
Creator:
Triplett, J. R.; Merrill, E. T. & Burr, J. R.
System:
The UNT Digital Library
MINIMIZER: A Computer Code for Determining Minimum Fuel Cost
Report that describes the Hanford Laboratories MINIMIZER code and demonstrates its accuracy in providing fissile fuel costs in a precise and automatic manner.
Date:
July 1965
Creator:
Eschbach, E. A.; Deonigi, D. E. & McConiga, A. F.
System:
The UNT Digital Library
The Hanford Isotopes Production Plant Engineering Study
Report presenting the conceptual design, estimates of capital and operating costs, and details of the operation of a plant "capable of high volume production of encapsulated heat sources" (p. 3) of radioisotopes Sr90, Cs137, Ce144, and Pm147.
Date:
July 1963
Creator:
La Riviere, J. R.; Michels, L. R.; Riches, H. C.; Rohrmann, C. A.; Smith, C. W. & Swift, W. H.
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
The Strain Aging and Heat Treatment Properties of N-Reactor Connector Tubes
Report regarding the determination of "the susceptibility to strain aging and the effect of stress-relief annealing on the properties of N-reactor connecting tubes made from ASTM A-106 Grade B high carbon steel" (p. 2).
Date:
July 30, 1963
Creator:
Pessl, H. J.
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