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Advanced Test Reactor Burnout Heat Transfer Tests
From abstract: "Results of burnout test to determine the limiting heat flux in a simulated Advanced Test Reactor fuel element channel."
Date:
January 1964
Creator:
Croft, M. W.
System:
The UNT Digital Library
Advanced Test Reactor Turbo Report
From abstract: "The time-dependent behavior of the Advanced Test Reactor was calculated by the Babcock & Wilcox Company on the Philco 2000 computer, using the Turbo depletion program."
Date:
January 1964
Creator:
Turner, Robert A.
System:
The UNT Digital Library
Aircraft Nuclear Propulsion Project Quarterly Progress Report: Period Ending September 10, 1951
The first part of this quarterly progress report details reactor theory and design, discussing the aircraft reactor experiment, experimental reactor engineering, reactor physics, and critical experiments. The second part of this report is not included. The third part of this quarterly progress report details materials research, discussing corrosion research, physical properties and heat-transfer research, metallurgy and ceramics, chemistry of high-temperature liquids, and radiation damage. The fourth part of this quarterly progress report details alternate systems, discussing a supercritical water reactor, circulating-moderator-coolant reactors. The fifth part of this quarterly progress report includes appendixes.
Date:
January 9, 1952
Creator:
Briant, R. C.; Ellis, C. B. & Cottrell, William B.
System:
The UNT Digital Library
Analytical Chemistry Division Annual Progress Report for Period Ending November 15, 1964
Report issued by the Oak Ridge National Laboratory discussing progress and work conducted by the Analytical Chemistry Division. Instrumentation, analytical methods, reactor projects, service analysis, and special research is presented. This report includes tables, illustrations, and photographs.
Date:
January 1965
Creator:
Kelley, M. T.; Susano, C. D. & Fisher, D. J.
System:
The UNT Digital Library
Critical Path Scheduling of ETR and MTR Reactor Shutdowns
Report describing a method for planning shutdown projects and scheduling the manpower to shut down Materials Testing Reactors (MTR) and Engineering Test Reactors (ETR).
Date:
January 10, 1962
Creator:
Jacobs, R. T. & Myers, L. L.
System:
The UNT Digital Library
Design Analysis of a Prepackaged Nuclear Power Plant for an Ice Cap Location
Report describing a the design requirements of a proposed nuclear power plant for use on an ice cap.
Date:
January 15, 1959
Creator:
Alco Products (Firm)
System:
The UNT Digital Library
Design Bases for ICPP Waste Calcination Facility
Report regarding a waste calcination unit that "will convert the fission product-containing aluminum nitrate solutions" "to granular alumina and fission product oxides" (p. 5).
Date:
January 16, 1959
Creator:
MacQueen, D. K. & Stevens, J. I.
System:
The UNT Digital Library
Design Study: Sodium Modular Reactor
This study was undertaken for the USAEC under Contract AT(04-3)-189, Project Agreement No. 6, to investigate desirable features of a sodium cooled, graphite moderated uranium fueled power reactor using the modular concept, and, based on this investigation, evaluate the economic potential of this reactor type.
Date:
January 15, 1960
Creator:
General Electric Company
System:
The UNT Digital Library
Engineering Test Reactor Critical Facility Hazards Summary Report, Supplement I
Report that "is a supplement to IDO-16332, "The Engineering Test Reactor Critical Facility Hazards Summary Report", presenting information on the conduct in the Facility of certain experiments which are expected to be operated in the Engineering Test Reactor" (p. 3).
Date:
January 24, 1958
Creator:
deBoisblanc, D. R.; Burdick, Earl E. & DeBoer, T. K.
System:
The UNT Digital Library
Euratom Reactor Fuel Management Program, Final Report: Part 1, Synthesis of Results
From abstract: This report presents studies in cost analysis and plant design, and physics core thermal and fuel cycle analyses.
Date:
January 1963
Creator:
unknown
System:
The UNT Digital Library
Euratom Reactor Fuel Management Program, Final Report: Part 2, Physics Analysis
From abstract: This report presents studies in cost analysis and plant design, and physics core thermal and fuel cycle analyses.
Date:
January 1963
Creator:
unknown
System:
The UNT Digital Library
Euratom Reactor Fuel Management Program, Final Report: Part 3, Fuel Cycle Analysis
From introduction: The parameters considered in this study are of two types: core-physics dependent, resulting from various fuel-management schemes and core-physics independent, relating to various modes of plant operation.
Date:
January 1963
Creator:
unknown
System:
The UNT Digital Library
Evaluation of Diethers as Uranium Extractants
Report on the determination of several physical properties, pertinent to uranium extraction, for a number of ethers and related compounds.
Date:
January 14, 1963
Creator:
Googin, J. M.; Harper, W. L.; Phillips, L. R. & Postma, Fred W.
System:
The UNT Digital Library
Evaluation of Radiation Stabilizers for Terphenyl by High-Temperature Electron Irradiation
From summary: "Experiments to determine effectiveness of additives to reduce radiolytic damage to a mixture of isometric terphenyls in which 93 separate compounds were evaluated."
Date:
January 23, 1963
Creator:
Hartzfeld, H. A. & Regier, R. B.
System:
The UNT Digital Library
An Evaluation of the Calder Hall Type of Nuclear Power Plant
Abstract: Presented herein is the preliminary design of a natural uranium, graphite moderated, CO2-cooled reactor and power plant similar to, but larger than, the British Calder Hall plant, with a net electrical output of 130 MWE.
Date:
January 18, 1957
Creator:
Banks, William F.; Schneider, G. A.; Morgan, William T. & Ash, E. B.
System:
The UNT Digital Library
EVESR Nuclear Superheat Fuel Development Project: First Quarterly Report, May 4-August 31, 1962
Quarterly report describing progress on the EVESR Nuclear Superheat Fuel Development Project.
Date:
January 31, 1963
Creator:
Pennington, R. T.
System:
The UNT Digital Library
An "Exact" Analysis of a Cylindrical Plasma in a Magnetic Field
Abstract: "The analysis of an immobilized plasma is here extended to the case where the geometry is cylindrical rather than Cartesian. (This report, UCRL-4439 (Rev, 4 constitutes Part II of the report series (UCRL-4466, Parts I, III, and IV) dealing with this general problem.)"
Date:
January 14, 1955
Creator:
Tonks, Lewi, 1897-1971
System:
The UNT Digital Library
Facility For Photographing in-Pile Meltdown Experiments in TREAT
Report regarding the fabrication of a transparent meltdown facility for the purpose of photographing simulated meltdowns.
Date:
January 1962
Creator:
Golden, G. H.; Dickerman, C. E. & Robinson, L. E.
System:
The UNT Digital Library
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fourth Quarterly Report, July-September 1962
Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date:
January 31, 1963
Creator:
Leitz, F. J.
System:
The UNT Digital Library
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Fifth Quarterly Report, October-December 1962
Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date:
January 1963
Creator:
Leitz, F. J.
System:
The UNT Digital Library
Flight Data and Results of Radiochemical Analyses of Filter Samples Collected During 1961 and 1962
Report containing "flight data and (...) results of radiochemical analyses of stratospheric and tropospheric air filter samples collected during Project Star Dust. This report contains data for samples collected during June 1961 to December 1962, the first year and a half of the project" (p. 2).
Date:
January 1, 1965
Creator:
Feely, Herbert W.; Friend, James P.; Krey, Philip W. & Russell, Barbara A.
System:
The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: September 1963
Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Date:
January 29, 1964
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Hanford Graphite Superheat Reactor (HGSR) Design Study and Evaluation
Report containing the results of a preliminary study of a design concept for a graphite-moderated pressure tube reactor. Topics include reactor design, operating procedures, subsystems, hazards analysis, and economic potential. Appendices begin on page 174.
Date:
January 1964
Creator:
Hanford Atomic Products Operation. N-Reactor Project Section.
System:
The UNT Digital Library
Hanford Radiological Sciences Research and Development Annual Report for 1962
Report regarding ongoing research and development undertaken at Hanfdord Laboratories' physics and instruments laboratory and chemical laboratory.
Date:
January 1963
Creator:
Gamertsfelder, C. C. & Green, J. K.
System:
The UNT Digital Library