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ABWR Design and Development Quarterly Progress Report, January 1 Through March 31, 1962
Quarterly design and development progress report on the activities of the Army Boiling Water Reactor (ABWR) Program.
Date:
April 15, 1962
Creator:
Combustion Engineering, inc. Nuclear Division.
System:
The UNT Digital Library
Accurate Nuclear Fuel Burnup Analyses; First Quarterly Report, (December 1961 - February 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:
April 1, 1962
Creator:
Rider, B. F.
System:
The UNT Digital Library
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development
First part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. I-ii).
Date:
April 1962
Creator:
Combustion Engineering, inc. Nuclear Division.
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
System:
The UNT Digital Library
An Automatic Monitor for As76 Concentrations in Reactor Cooling Water
Report that describes the development, design, and operation of a prototype instrument meant to monitor the As76 concentration in reactor cooling water streams.
Date:
April 1963
Creator:
Rieck, H. G. 1922-
System:
The UNT Digital Library
Corrosion of Zircaloy in Crevices under Nucleate Boiling Conditions
Abstract: The MSAR corrosion test loop was used to study the effect of VKE-shaped crevices on the corrosion resistance of Zircaloy under boiling heat-transfer condtions in both ammoniated and lithiated water at pH 10.5.
Date:
April 1962
Creator:
Anderson, W. Kermit & McGoff, M. J.
System:
The UNT Digital Library
Critical Path Scheduling in Maintenance
Summary: The following narrative interspersed with figures and attached reference exhibits is designed to acquaint the reader with the scheduling procedure developed at ORGDP, trial results and evaluation, subsequent improvement, further application, and use in conjunction with our IBM 7090 Computer.
Date:
April 10, 1961
Creator:
Gritzner, C. L.; Jones, J. P. & Ellis, J. M.
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
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.
System:
The UNT Digital Library
Determination of the Number of Double Bonds in Less-Than-Milligram Amounts of Unsaturated Fatty Acids by Catalytic Hydrogenation in the Warburg Apparatus
Report discussing the determination of the number of olefinic double bonds in less-than-milligram amounts of unsaturated fatty acid derivatives using Barcroft-Warburg tissue respirometer as a manometric microhydrogenation apparatus.
Date:
April 1949
Creator:
Mead, James F. & Howton, David R.
System:
The UNT Digital Library
The Development of an Improved Thermionic Energy Converter: Third Quarterly Technical Report
From introduction: The objective of the current program is to determine the feasibility of the reservoirless converter operation by conducting a series of tests on operating thermionic converters which contain cesium in the vapor phase only.
Date:
April 1965
Creator:
Radio Corporation of America. Direct Energy Conversion Department.
System:
The UNT Digital Library
Development Program for Increased Output in the Garigliano Nuclear Reactor. Quarterly Report No. 2
The United States and the European Atomic Energy Community (Euratom), on May 29, and June 18, 1958, signed an agreement which provides a basis for co-operation in programs for the advancement of the peaceful applications of atomic energy. The work described in this report represents the Joint U.S.-Euratom effort. The over-all development program is designed to obtain the test data and operating experience necessary to eventually realize a 50 percent increase in the output of the Garigliano Nuclear Power Station located at Sessa Aurunca (Campania, Italy). Two tasks are in progress: Task III-F involves the preparation of test specimens of reactor vessel material for irradiation; Task IV consists of the formulation of specification for a complete data logging and computer system.
Date:
April 1, 1963
Creator:
Quinn, E. P.
System:
The UNT Digital Library
An Evaluation of Four Processes for Recovering Uranium from Zirconium Fuels at the Idaho Chemical Processing Plant
Report evaluating the technical and economic feasibility of four zirconium fuel processes: the present STR process, the modified Zirflex process, the barium fluozirconate process, and the sodium formate process.
Date:
April 27, 1962
Creator:
Burn, P.
System:
The UNT Digital Library
The FAIM Code: a Multigroup, One-Dimensional Diffusion Equation Code
Abstract: FAIM is a general multigroup, one-dimensional diffusion equation code programmed in FORTRAN language for the IBM 7090 computer.
Date:
April 15, 1962
Creator:
Baller, D. C.
System:
The UNT Digital Library
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Sixth Quarterly Report, January-March 1963
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:
April 1963
Creator:
Leitz, F. J.
System:
The UNT Digital Library
Fast Flux Test Facility Studies Progress Report: April 1965
From abstract: "...limited study work was performed on the conceptual design of the proposed fast flux test facility and information was obtained in important areas of supporting technology."
Date:
April 1965
Creator:
Astley, E. R.
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.
System:
The UNT Digital Library
Feasibility Study, Optimum Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission, Idaho Operations Office
Report containing "a discussion of the feasibility design and cost estimates for a gas cooled, natural uranium, graphite moderated power plant optimized for minimum power cost" (p. 3).
Date:
April 1, 1958
Creator:
ACF Industries Incorporated. Nuclear Products - ERCO Division.
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.
System:
The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: December 1961
Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.
Date:
April 6, 1962
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
A Generalized Computer Program for Flowsheet Calculation and Process Data Reduction
Report issued by the Argonne National Laboratory discussing the PACER-65 computer program. As stated in the summary, the program "has been developed and utilized for flow sheet calculations and process-data reduction. PACER-65 is an executive program in which material- and energy-balance equations, conversion factors, etc., for each processing step are described by separate subroutines" (p. 5). This report includes tables, and illustrations.
Date:
April 1966
Creator:
Koppel, L. B.; Alfredson, P. G.; Anastasia, L. J.; Knudsen, I. E. & Vogel, G. J.
System:
The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1959 - March 1, 1960
Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date:
April 1, 1960
Creator:
Hardy, Edward P., Jr. & Klein, Stanley
System:
The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1960 - March 1, 1961
Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date:
April 1, 1961
Creator:
Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
System:
The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1961 - March 1, 1962
Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date:
April 1, 1962
Creator:
Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
System:
The UNT Digital Library