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Gas Cooled Nuclear Reactor Study
Study of a gas cooled reactor with design specifications providing for a source of high temperature heat to a stream of helium. This reactor, in turn, is used as a source of heat for the air stream in a gas-turbine power plant.
Date:
July 31, 1956
Creator:
Thompson, A. S.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Fabrication of Fuel Rods by Tandem Rolling
From introduction: "The purpose of this report is to present the details of the exploratory and developmental work on tandem rolling, and the subsequent fabrication of tandem rolled fuel rods for irradiation testing in the Vallecitos Boiling Water Reactor."
Date:
July 1961
Creator:
Lingafelter, J. W.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Materials for Superheated Fuel Sheaths: Relative Performance of Alloys in Superheated Steam Environments
From abstract: "Study of radiation effects upon the tensile properties of the alloys, corrosion behavior in the absence and presence of stress, effect of prolonged, high temperature exposures upon structure sensitive properties of the alloys, and physical metallurgical changes as a function of exposure in a superheat environment.
Date:
July 1963
Creator:
Comprelli, F. A.; MacMillan, D. F. & Spalaris, C. N.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Thorium Fuels for the Heavy Water Organic Cooled Reactor
From abstract: "A summary of work done by The Babcock & Wilcox Company to evaluate thorium fuels for the Heavy Water Organic Cooled Reactor (HWOCR)."
Date:
July 1966
Creator:
unknown
Object Type:
Report
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.
Object Type:
Report
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
Object Type:
Report
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
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Paper Chromatography in Synthetic Organic Chemistry: Microgram Scale Syntheses of Labeled Monoiodotyrosine, diiodotyrosine and thyroxine
A report on paper chromatography in synthetic organic chemistry.
Date:
July 8, 1949
Creator:
Lemmon, R. M.; Tarpey, Winifred & Scott, Kenneth G.
Object Type:
Report
System:
The UNT Digital Library
Liquid Metal Reactor Experiment Preliminary Hazards Evaluation, July 1957
Report containing descriptions of the Liquid Metal Fuel Reactor Experiment's reactor, containment, and plant design. Includes analyses of associated environmental hazards.
Date:
July 1957
Creator:
Babcock & Wilcox Company
Object Type:
Report
System:
The UNT Digital Library
Effect of Process Variables on Graphite Purity
Results of four experimental heats run at the end of the G-5 contract in the National Carbon Company Clarksburg production furnaces.
Date:
July 20, 1954
Creator:
Riley, W. C. & Corners, A. M.
Object Type:
Report
System:
The UNT Digital Library
Joint Design for Making Root Pass Welds without Filler Material
Investigation to evaluate some of the designs, techniques, and methods for fabrication of a root pass.
Date:
July 9, 1956
Creator:
Lemon, L. C. & Smith, W. R.
Object Type:
Report
System:
The UNT Digital Library
Program Study Report Plutonium Fuel Cycle
From introduction: "The development and demonstration of the natural uranium reprocessed plutonium cycle in power reactors is an important phase of the peaceful applications of nuclear energy."
Date:
July 30, 1956
Creator:
Albaugh, F. W. & Fryar, R. M.
Object Type:
Report
System:
The UNT Digital Library
Fabrication of the PRTR Zircaloy-2 High Pressure Process Tubes
Development of a fabrication process and the manufacture of 95 PRTR process tubes demonstrates that the commercial fabrication of high quality Zircaloy-2 pressure tubing is feasible.
Date:
July 31, 1959
Creator:
Knecht, R. L.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library