Resource Type
Serial/Series Title
Atomic Energy Commission Reports
141
AEC research and development report
51
TID
44
University of California Radiation Laboratory Reports
32
General Electric Company Atomic Power Reports
27
UC (Series)
24
ORNL (Series)
23
Report (U.S. Atomic Energy Commission)
23
UCRL (Series)
21
HW (Series)
20
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298 Matching Results
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The ScCl3-Sc System
Experimental data supporting lower valence halides of scandium were not found in the literature. Our investigation was of the phase diagram of the ScCl3-Sc system, and also the vapor pressure-composition isotherm (at 960 degree) for this system. Investigation of the ScCl3-Sc system presented particular difficulties in comparison with analogous systems for rare earth elements in that ScCl3 is highly volatile (boiling pt. = 967 degree); according to our data the vapor pressure is 512 mm Hg measured at 960 degree C. Furthermore, ScCl3 and its vapors react vigorously with quartz. Because of the mentioned extent of reaction in a quartz ampule, the inside was covered with a solid layer of metallic molybdenum for use with relatively large batches of ScCl3.
Date:
April 1964
Creator:
Polyachenok, O. G. & Novikov, G. I.
Object Type:
Report
System:
The UNT Digital Library
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Tenth Quarterly Report, January-March 1964
Quarterly report discussing progress on the Fast Ceramic Reactor Development Program. Information is reported on vented fuel production, transient testing of fuel, fuel performance evaluation, fast-flux irradiation of fuel, and reactor physics and core analysis.
Date:
April 1964
Creator:
Breizy, C. E.
Object Type:
Report
System:
The UNT Digital Library
Some Major Fuel-Irradiation Test Facilities of the Oak Ridge National Laboratory
Report describing various reactors, six thermal conduction capsules, three loop facilities, miscellaneous equipment, and shop facilities maintained by the Oak Ridge National Laboratory.
Date:
April 1964
Creator:
Trauger, Donald B.
Object Type:
Report
System:
The UNT Digital Library
Thorium-Uranium-233 Oxide (Kilorod) Facility : Rod Fabrication Process and Equipment
Report documenting "the design, construction, and operation of the Kilorod Facility and its fabrication equipment" (p. 42) as well as its economic viability.
Date:
April 1964
Creator:
Sease, J. D.; Lotts, A. L. & Davis, F. C.
Object Type:
Report
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.
Object Type:
Report
System:
The UNT Digital Library
Transition Boiling Heat Transfer Program; Fifth Quarterly Progress Report, January - March 1964
Summary: Tests with the two-rod assembly were performed with liquid film trippers attached to the unheated wall, and a variation in rod spacing. Experimental data and improved high-speed motion pictures have been obtained of transition boiling behavior. The changes of the local heat transfer process between nucleate and film boiling can be readily distinguished i the motion pictures. Observational test performed with very short fins on the heated surface resulted in essentially eliminating transition boiling temperature fluctuations and doubling the film boiling coefficient. These gains were attained without reduction of the critical heat flux
Date:
April 1, 1964
Creator:
Quinn, E. P.
Object Type:
Report
System:
The UNT Digital Library
Yankee Core Evaluation Program Quarterly Progress Report: January-March 1964
Quarterly report regarding the activities of the Yankee Core Evaluation Program, the purpose of which is to evaluate the performance of the core used in the Yankee Plant and to compare actual performance with predictions, as well as the revision of designs to address any differences between actual and predicted performance.
Date:
April 1964
Creator:
Westinghouse Electric Corporation. Atomic Power Division.
Object Type:
Report
System:
The UNT Digital Library
The Design and Performance of Levitation Melting Coils
The purpose of this study was to provide a means for evaluating the various parameters involved in the design and performance of levitation coils.
Date:
April 26, 1963
Creator:
Hulsey, William Jewell
Object Type:
Report
System:
The UNT Digital Library
The Inference of Adsorption from Differential Double Layer Capacitance Measurements
From Abstract : "Dependence of boundary tension and capacitance at the mercury-aqueous 0.1 N HClO4 interface on polarization and organic solute concentration were determined for the colutes n-amyl alcohol and phenol. ... An earlier treatment proposed by this Laboratory based on a (non-thermodynamic) assumption of linear variation of surface charge density with coverage appears adequately justified for inference of fractional surface coverages near the electrocapillary maximum, but must be considered approximate for evaluation of molar area at full coverage in cases where linear variation of charge with coverage has not been demonstrated."
Date:
April 26, 1963
Creator:
Hansen, Robert S.; Kelsh, Dennis J. & Grantham, D. H.
Object Type:
Report
System:
The UNT Digital Library
The Thermal Expansion of Thirteen Tungsten Carbide Cermets from 68 to 1800 F
The linear thermal expansion of thirteen tungsten carbide cermets with cobalt binder was investigated experimentally over the temperature range from 68 to 1800 F. Cobalt contents varied from 2.5 to 60 per cent. Several compositions included additions of mixed carbides of titanium, tantalum, and columbium. The experimentally observed coefficients of thermal expansion for the various compositions were compared with coefficients analytically computed from the coefficients for the constituents. Three such analytical methods were evaluated. In one method, the coefficient of expansion of the mixture was computed by volume fractions and in a second method by weight fractions. In the third method, the computation accounted for the stresses set up in the mixture by the difference in thermal expansion of the carbide skeleton and the cobalt binder. The expansions of all these cermets agreed with the values computed by weight fractions or by the stress method within 12 per cent, and by volume fractions within 28 per cent. The cermets containing less than one per cent mixed carbides agreed with the expansion computed either by weight fractions or by stress within 8 per cent, the cermets containing more than five per cent mixed carbides agreed with values computed by volume fractions …
Date:
April 26, 1963
Creator:
Harrington, L. C. & Rowe, G. H.
Object Type:
Report
System:
The UNT Digital Library
Fast Reactor Fuel Cycle Costs and Temperature Coefficients of Reactivity for PuO2-SS and PuO2-UO2
Report comparing the fuel cycle costs and temperature coefficients of reactivity for PuO2-UO2 fuel in multiple megawatt reactors.
Date:
April 25, 1963
Creator:
Edwards, J. J.; Fischer, E. A.; Jens, W. H.; Nims, J. B.; Palmer, R. G.; Shoudy, A. A. et al.
Object Type:
Report
System:
The UNT Digital Library
Measurement of Thermal Properties by the Arc Image Furnace
Technical report. From Abstract : "A number of imaging furnace systems and sources are discussed with emphasis on the carbon arc image furnace. Several potential applications of the carbon arc image furnace in high temperature research are described and a new method of heat capacity determination is discussed."
Date:
April 16, 1963
Creator:
McMahon, W. R. & Wilder, D. R.
Object Type:
Report
System:
The UNT Digital Library
High Performance UO2 Program Quarterly Progress Report No.8 : January-March 1963
Work performed during the quarter is summarized by direct measurement of fission gas pressure, loop operations, performance of UO2 fuel.
Date:
April 15, 1963
Creator:
Weidenbaum, B.
Object Type:
Report
System:
The UNT Digital Library
High Power Density Development Project: Twelfth Quarterly Progress Report, January-March 1963
From introduction: "Development of nuclear reactor cores having high power density, long fuel life, and low fabrication costs is the objective of this program sponsored by the AEC."
Date:
April 15, 1963
Creator:
Holland, L. K.
Object Type:
Report
System:
The UNT Digital Library
Influence of a Sector Ground Screen on the Field of a Vertical Antenna
Report show the field of a short vertical antenna on a homogeneous ground is modified by the presence of a metallic screen. The screen is taken in the form of a circular disk and a concentric sector. The modification of the field is expressed in the form of surface integrals over the disk and the sector. Extensive numerical results for these basic integrals are given and a number of applications are illustrated.
Date:
April 15, 1963
Creator:
Wait, James R. & Walters, Lillie C.
Object Type:
Report
System:
The UNT Digital Library
Reactor Development Program Progress Report: March 1963
Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during March 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date:
April 15, 1963
Creator:
Adams, R. M. & Glassner, A.
Object Type:
Report
System:
The UNT Digital Library
Transition Boiling Heat Transfer Program; First Quarterly Progress Report, February - March 1963
Introduction: The Transition Boiling Heat Transfer Program is sponsored jointly by the USAEC and Euroatom and is being conducted by the General Electric Company. The work commenced on this program February 11, 1963. The objective of this program is to perform basic investigation and measurement of the transition boiling regime in high pressure bulk boiling water flows, with particular emphasis i the high range of steam qualities.
Date:
April 15, 1963
Creator:
Tippets, F. E.
Object Type:
Report
System:
The UNT Digital Library
A Versatile Spectrometer Magnet Power Supply
Early results from actual laboratory operation of a more versatile magnet supply.
Date:
April 15, 1963
Creator:
Groppe, W. A.
Object Type:
Report
System:
The UNT Digital Library
Design and Test of a Diaphragm Pump for Liquid Metals
Technical report. From Abstract : "Details are provided on the construction and operation of a two-stage diaphragm pump successfully used for the first time in liquid metal service. From the results of 5,376 hr. test of the pump it was concluded that it is well suited to the pumping of liquid metals at low flow rates where pulsating flow can be tolerated and also where remote operation is required. Operating temperatures and pressures are limited only by the availability of suitable materials of construction."
Date:
April 12, 1963
Creator:
Westerheide, D. E. & Clifford, J. C.
Object Type:
Report
System:
The UNT Digital Library
The Design Study of Fluid Engine Power Systems
From abstract: This report presents information generated during a six month feasibility study of an engine which uses a supercritical working fluid as the secondary portion of nuclear powered electric generating system.
Date:
April 12, 1963
Creator:
Baker, C. H.; Hunter, T. A.; Pauliukonis, R. S. & Pradhan, A. V.
Object Type:
Report
System:
The UNT Digital Library
Army Reactors Program Annual Progress Report: 1962
Report summarizing ongoing nuclear work performed by the ORNL for the United States Army.
Date:
April 10, 1963
Creator:
Oak Ridge National Laboratory
Object Type:
Report
System:
The UNT Digital Library
Errata for ANL-6628: Automatic Foil Activity Counting Facility and Data-Reduction Program
Errata sheet listing corrections to three pages of a report that describes a transistorized automatic counting and recording system built for the determination of foil-activation data.
Date:
April 8, 1963
Creator:
Glassner, Alvin
Object Type:
Text
System:
The UNT Digital Library
Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: January 1 - March 31, 1963.
A research program is being conducted to obtain experimental data in the irradiation of plutonium-enriched fuel to confirm a theoretical model for predicting isotopic composition and reactivity changes in plutonium-enriched, light-water-moderated reactors. All program efforts have been temporarily deferred except for those associated with the irradiation of the program fuel element in the VBWR. The program fuel element was exposed to a burnup of 465 MWD/T during the quarter which brings the total to 2334 MWD/T. On the basis of the computed isotopic composition, the burnup obtained was 1450 MWD/T.
Date:
April 8, 1963
Creator:
Robkin, M. A.
Object Type:
Report
System:
The UNT Digital Library
Fuel Cycle Program Progress Report: Eleventh Quarter, January-March 1963
Quarterly progress report discussing activities related to the Vallecitos Boiling Water Reactor (VBWR) and related facilities.
Date:
April 5, 1963
Creator:
Howard, C. L.
Object Type:
Report
System:
The UNT Digital Library